nine mile point, units 1 and 2 - semi-annual report …semi-annual report of operation for the nine...

NIAGARA MOHAWK POWER CORPORATION

NIAGARA ~ MOHAWK

300 ERIE SOULEVARO WEST

SYRACUSE, N.Y. I3202

RegulatoryCA

February 25, 1972

File Cy.

Dr. Peter A. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy CommissWashington, D. C. 20545

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Dear Dr. Morris:

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Provisional Operating License DPR-17Docket No. 50-220

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In conformance with the Technical Specifications for the

Nine Mile Point Nuclear Station, we are sending you under separate

cover, forty (40) copies of the Semi-Annual Report for the period

July 1, 1971 through December 31, 1971.

Very truly yours,

F. J. SchneiderVice President, Operations

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NIAGARA 'OHAWK

300 ERIK BOUI EVARO WEST

SYRAC US 2, N.Y. I3202 ReIaI ate ry File Cy.

February 18, 1971

Dr. Peter'. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy CommissionIIIashington, D. C. 20545

Dear Dr. Morris:

Re: Provisional Operating License DPR-17Docket No. 50-220

In conformance with the Technical Specificationsfor the Nine Mile Nuclear Station, we are sending you,under separate cover, forty (40) copies of the Semi-Annual Report for the period ending December 31, 1970

Very truly yours,

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NIAGARA MOHAWKPOWER CORPORATION

NIAGARA MOHAWK

300 ERIE BOULEVARD WEST

SYRACUSE, N.Y. l3202

February 16, 1971

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Dr. Peter A. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

Dear Dr. Morris:

I acknowledge with thanks the receipt of theFebruary 6, 1971 letter giving the conclusions of the AdvisoryCommittee on Reactor Safeguards regarding our application toincrease the licensed power level of Nine Mile Point NuclearStation to 1850 MWt.

I would like, also, to express my appreciation forthe cooperation received from you and your associates duringthe many reviews and discussions that led to the conclusionsoutlined in the Committee's report.

Sincerely,

T . BrosnanVice Pres ent and Chief Engineer

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cc: Arvin E. Upton, Esq.

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Nine Mile .Point Nuclear StationP. 0. Box 32Lycoming,,New York 13093December 9, 1970

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Dear Dr. Morris:

Dr. Peter A. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy Commissionlltashington, D. C. 20S45

Enclosed please find forty (40) copies'f'rtheSemi-Annual Report of Operation for the Nine Mile Point~ X

Nuclear Station which may be of interest toyou.'f

you,have any questions concerning this Report,please do not hesitate to contact me.

Very truly yours,

P. Allister BurtStation Superintendent

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NIAGARA MOHAWK

300 ERIE 8OUI EVARD WEST

SYRACUSE, H, Y. I3202

July 10, 1970

Dr. Peter'. Morris, DirectorDivision of -Reactor LicensingUnited States Atomic Energy CommissiontItashington, D. C. 20545

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Dear Dr. Morris:

.Re: Provisional Operating License DPR-17Docket No. 50-220

Enclosed are forty (40) copi'es of the Semi-Annual Reportof the Nine Mile Point Nuclear Station, Niagara Mohawk PowerCorporation, which was concluded December 31, 1969.

This is in agreement with the Technical Specificationsfor this facility and although they may be a bit late, wehope you understand we have had many'ituations which requiresurveillance by cognoscente personnel.

The following Semi-Annual Report, we feel, will be broughtto your attention mos't expeditiously.

Very truly yours,

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F. J. 'SchneiderVice President Operations

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ARVIN E. UPTONEUGENE B. THOMAS, JR.LEONARD M. TROSTENHARRY H. VOIGTA

WASHINGTON PARTRCRS

LAW OFFICES OF

LEBOEUF, LAM B, LE I BY 8L MACRAEl821 JEFFERSON PLACE,N.W.

WAsHINGTQN,D.C. 20036

October 5, 1972ONC CHASE MANHATTAN PLAZA

NEW YORK'.Y. IOODS

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CASLC ADDRESSLALALVyWASHINGTON D. C.

Mr. Donald J. SkovholtAssistant Director for

Operating ReactorsDirectorate of LicensingU.S. Atomic Energy CommissionWashington, D.C. 20545

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Re: Nine Mile Point Unit No. 1Docket No. 50-220

Dear Mr. Skovholt:,

As counsel for the above-named licensee, we herebytransmit thirty-nine (39) copies of Mr. Brosnan's letter ofSeptember 29, 1972 which was in answer to your letter ofAugust 3, 1972.

We are sorry if we have caused you any inconvenienceby not having sent you all forty (40) of the copies at thesame time.

Very truly yours,

LEBOEUF, LAMB, . LEIBY & MACRAE

Attorneys for Niagara MohawkPower Corporation

Enclosures

Eugen B. Thomas, Jr.Partner

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?~ia,".ara ":lobar, Power CorporationATTi~l: Nr. i~. J. Sehneidex

Vice President - Operations300 Erie Boulevard MeatSyracuse, ?few Yor?c 13202

Gentlemen:

Thanl< you for your letter of September 1>l, 1971 in reply toour notice dated August 26, 1971.

Xn our vien, certain assumptions provided in your replyconcerninp the reportability requirements of Section 3.C(2)of your license are not valid. Xnformation prov5.ded in thePinal Safety Analysis Report (PSAB), includinp performance,specifications of the type identified in Table D-18 ofAppendix D of the PSAR, serves as the basis for the rep;ula-torIt safety evaluation of systems and components incorporatedin tl:e design of your facility. Accordingly, any ubstantialvariance disclosed by operation of the facil5.ty from thesepex formance specixications must be reported to the Director,Division of Reactor Licensing, aa required by Section 3,C(2)of your license. Xf you neeci puidance relatinp to thereporting reauiremcnts of your license or TechnicalSpeciflcationa, our Regional Office in ?4cwarl:, How Jersey,vill be liappy t;o assist you.

Mc i ill review the corrective action taken by you, regardingthe control of radioactive material, du in@ the next inspec-tion of your facility.Should you have any questions concernin," these matters, wewill be pleased. Co discuss them with you.

Very truly yours,

cc: = >.r ~ P. ~ A Burt ~ Plant' 1 QFII'>

Lawrence D. Low, DirectorDivision of Compliance DRL q.>r,'~~

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AEC DISTRIBUTION FOR PART 0 DOCXET MATERIAL,TEMPORARY FORD CONTROL NO;

FROM:Niagra Mohawk Power CorporationSyracuse, New York 13202Thomas Z. Brosnan

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Donald J. SkovholtCLASS! U PROP INFO

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PLANT HAYES: Nine. Mile Point, Unit 1

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February 17, 1972

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Dr. Peter A. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy CommissionNa'shington, D. C. 20545

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Re: Docket Number 50-220Provisional, Operating License DPR-17

Dear Dr. Morris:

In order to prepare for the joint operation of'he Nine'ile'Point'uclear Station, Unit '((l,,and the James A. FitzPatrick.

Nuclear Plant, sever'al changes have bee'n made in the Nine Mile,Point Operating Organization.

Mr. P. A. Burt has been changed from Station Superintendent,"Nine Mile 'Point, to General Superintendent, Nuclear Generation,

'ithadministration on site of bo'th plants.

Mr. T. J. Perkins has been changed from Assistant St'ationSuperintendent, Nine Mile Point, to Station 'Superintendent, NineMile Point Nuclear Station, reporting to General Superintendent, '

Nuclear Generation.

Mr. T. E. Lempges has been changed from Operations Super-visor, Nine 'Mile Point, to Station Superintendent, J. A. FitzPatrickPlant, reporting to General Superintendent, Nuclear Generation.

Duties of the Operations'upervisor have been'aken overby Mr: G. L. Stuart Jr. 'with title of Assistant to the Superintendentreporting to Station Superintendent", Nine .Mile Point'uclear Station.He is 'a licensed Senior Reacto'r Operator.

These changes were effected February -1, 1972. Others willbe forthcoming as plans,'develop.- '" I

Very truly'ours,

cc: Region I Compliance

F. J. SchneiderVice Presi'dent - Operations

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Nine Mile Point Nuclear StationPost Office Box 32Lycoming, New York 13093

January 20, 1972


Dear Dr. Morris:

Re: Provisional Operating License: DPR-17Docket No/I 50-220

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The second stage of reheat was removed from service atNine Mile Point Nuclear Station Unit tl on January 18, 1972. Acrack had developed in the drain line from the coil of reheater8112. This heating coil is supplied with primary steam, andcondensate from the coil drains by gravity to a receiving tank.

tYhen the crack was located, the second stage reheaterwas secured. The part having the defect was an 8" schedule 80seamless weld "tee" ASTM A-234 Grade l<PB.

A crack developed at the edge of weld deposit metaland extended about an inch through the heat affected zone in adirection longitudinal to the major axis of the tee.

This system will remain out of service until the turbineis next removed from service when a better appraisal of the causeof the difficulty can be obtained and proper repairs affected.

The next scheduled outage is to commence April 2, 1972.

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January 20, 1972CU


Dear Dr. Morris:

Re: Provisional Operating License DPR-17Docket No.: 50-220

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On December 31, 1971 at 10:08 am, the Nine Mile Point NuclearStation Unit ¹1 tripped off line as the result of surveillance testing.

Introduction:

Routine surveillance testing of the reactor protection high/lowwater level sensors was being conducted at the time of the trip. Thesensor support was accidently bumped causing each high level trip sensorto operate resulting in a turbine trip. Because the turbine was above45~~ load, an anticipatory trip signal was generated to scram the reactoron a turbine trip.

Following the reactor scram, the reactor water level decreasedrapidly. The feedwater control system responded by overfeeding, as itshould, when in the automatic mode. The feedwater system was left in theautomatic mode for approximately 20 seconds after the trip, and thenswitched to the manual mode, because the feedwater flow to the reactorwas high in the operator's opinion. Manual action was too slow andexcessive feedwater flow continued to the reactor. Feedwater flow wasreduced to zero at approximately the time the reactor level reached themain steam leads causing some water to go into these lines.

Analysis and sequence of events:

At 10:08:02 am, a turbine trip occurred from an erroneous highreactor water level signal caused by bumping the sensors.

At 10:08:02 am, the reactor scrammed from the turbine anticipatorytrip. The turbine load was greater than 45~o. All control systems followedthe expected transient response characteristic for the first 18 secondsfollowing the trip. There were three feedwater pumps all running in auto-matic mode. Two motor pumps, each delivering about 1.5 X 106 lbs/hr and

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Dr. Peter A. MorrisDivision of Reactor Licensing

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1/20/72

the shaft pump which was delivering about 5.2 X 10 lbs/hr at 18 secondsafter the trip. This accounts for the high flow the operator observed.The analysis show that the water level was beginning to recover and thatthe flow was backing down when switched to manual mode on the shaft pump.At 27 and 33 seconds, the motor pumps were placed in the manual mode. At33 seconds, one of the motor pump's .flow had already reduced to zero flowin response to the automatic signal. Operator action on this pump in themanual mode was to increase flow. At 70 seconds after the trip, theanalysis showed the water level to be three feet above normal with flowbeing reduced manually on the shaft pump and a constant flow being main-tained on both motor pumps. Flow on the shaft pump was reduced to zeroat approximately 120 seconds after the trip. Flow on the motor pumps wasreduced to zero at approximately 150 seconds after the trip. Analysisshows that some water may have spilled into the main steam leads at 131seconds after the trip. This water flashed in the hot steam leads causingthe steam line break sensors to operate.

Conclusion:

The trip resulted during surveillance testing from an accidentalbump to the level sensors.

The feedwater response in the automatic mode was normal for thetransient conditions that existed.

Placing the feedwater system in manual when fast response isrequired may cause a level problem if the operator does not respond fastenough.

Corrective action:

A review of expected system responses will be given to the oper-ators as part of the continuous educational program. This would help theoperators in making the right decision during future trips.

Very truly yours,

EP. Allister BurtStation Superintendent

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Docket No. 50-220

Niagara 2~hawk Power CorporationATTN: Ym. F. J. Schneider

Uice President AOperations300 Erie Boulevard. NestSyracuse, New York 13202

DISTRIBUTIONPDR

~Docket FileDRL ReadingBranch ReadingK% D. J. SkovholtR. H. UollmerD. L. ZiemannC. J. DeBevecR. M. DiggsOGC

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Gentlemen.'our

letter dated December 15, 1971, described your plans for interimoperation of Nine lQ.le Point reactor at the full stretch power of1850 ILHt without having performed certain system transient tests.Your letter included summary results of power escalation tests whichhave been performed that indicate the system is operating within designpredictions.

He have reviewed the information you provided and have concluded thatthe proposed deferment unti1 April 1972 for performing the 1850 HMttests of the maximum recirculation flow rate change, the five-recirculation-pump trip, and the turbine trip is acceptable, in viewof the circumstances you have described, and does not involve an unduerisk to the health and safety of the public. No licensing action isbeing taken since this deferment does not involve an unreviewed safetyquestion, nor does it require a change to the Technical Specificationsof Facility License No, DPK-17.

Sincerely,

/g( T~35kov(,oi+Donald J. SkovholtAssistant Director for

Reactor OperationsDivision of Reactor Licensing

cc. Arvin E. Upton, EsquireLeBoeuf, Lamb, Leiby 6 Ma@0e1821 Jefferson Place, N. H.Mashington, D. C. 20036

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Niagara I4ohawk Power CorporationATTN: Nr. P. J. Schneidex™

Vice President - Operations300 Erie Boulevard VestSyracuse, New York 13202

Gentlemen:

Thank you for your letter oi September 14, 1971 in reply toour notice date4 August 26, 19'.Xn our view, certain assumptions provided in your replyconcerning the reportability requirements of Section 3.C(2)of your license are not valid. Xnformat1on provided in thePenal Safety Analysis Report (FSAR), including performancespec1fications of the type'dentified in Table 0-18 ofAppendix 9 of thy PSAR, serves as the basis for the regula-tory safety evaluation of systems and components incorporatedin the design of your f'ac1lity.. Accordingly, .any'ubstantialvariance disclosed by operation of the facilLty from theseperformance specifications must be reported. to the Director,Division oi'eactor Licensing, as required by Section 3.C(2)of your license. Xf you need guidance relating to thereporting requirements of your'icense or TechnicalSpecifications, oux'egiona1 Office in Newark, Hew Jersey,will be happy'o assist you.

Ve will review the corrective action taken by you, regardingthe control of radioactive .material, during the next inspec-tion of youx facility.Should you have any questions concerning 'these matters, >rewill be pleased. to discuss them w1th you.

Very truly yours~

cc: t''Lr. P.. A. Burt, Plant

Lawrence 9. Low, DirectorDivision of Compliance DRL

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Nine Mile Point Nu'clear StationPost Office Box 32Lycoming, New York 13093

December 13, 1971

Dr. Peter A. Morris, DirectorDivision of,Reactor LicensingUnited States Atomic Energy Commissionwashington, D. C. 20545

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Re: Provisional Operating License DPR-17Docket No. 50-220 'f

During a routine examination, of various components ofthe Nine Mile Point Nuclear Station turbine, the seats of all nineby-pass valves were found to be cracked. These seats are fabri-cated of 2 1/4 Cr - 1 Mo (B50A179) alloy steel forgings having astellite inlay fused into the seat at point of contact with thedisc. The cracking was confined to the stellited insert runningradially between the fusion lines and across the insert.

The stellite insert was removed entirely and a new weldprep machined into the seat. After liquid penetrant inspection,the seats were welded with a much more ductile austenitic stain-less steel electrode, 25 Cr — 20 Ni (AWS A5.4 Clas E310) to fillthe weld prep. They were machined to contour and reinstalled inthe valve chest after passing another liquid penetrant test.

Three of the valve discs were found by liquid penetranttesting to have several tight cracks. These were removed by lightmachining. They will be inspected again at the next outage inApril 1972.

Very truly yours,

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December 13, 1971

Dr. Peter A. hIorris, DirectorDivision of Reactor LicensingUnited States Atomic Energy Commissionl(ashington, D. C. 20545

Dear Dr. Morris:

Re: Provisional Operating License DPR-17Docket No. 50-220Nine Mile Point Nuclear Station

After returning to power following a "scram" onAugust 30, 1971, it was observed that the steam flow indication ofone of the two main steam lines was only two thirds the value ofthe other. Investigation revealed erroneous pressure differentialreadings being produced by the primary measuring device, a BuildersIron Foundry 24 (21.564) X 12.45 Venturi insert nozzle, hlodel NZll'l.In this design, a casting having a smooth contour to the "throat"is welded at one end only, fastening it to the inner circumferenceof the steam pipe and permitting expansion at the unwelded end. Acavity is formed between the steam pipe inner surface and thecasting at the throat. Therefore, it is necessary to carry thestatic pressure at the throat, K2, through this cavity in tubing.The leading edge of the casting is the unwelded one and therefore,the outside of the tubing carrying the K2 pressure is surroundedby K~ pressure. A leak in the tubing would reduce the differentialpressure and cause the steam flow meter to read low.

Shortly thereafter, with the unit shutdown, examinationdisclosed an open crack in the tubing at a point where a bend hadbeen provided for expansion. Subsequent examination of the similartube in the other steam line venturi revealed a tight crack in thesame location. (However, it had not apparently started to leak.)The failed tubes were seamless type 304 per ASTM-A269-63T withnominal dimensions of 7/8" O.D. and .035" wall thickness. Allother parts of the assembly, except a stainless steel insert at thethroat, were of carbon steel.

Metallurgical analysis of the failed tubes revealed that.failure had occurred by stress corrosion cracking of heavily sensi-tized material that had been cold worked prior to sensitization.

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In manufacture, the entire assemb'le was welded togetherand then subjected to,a normalizing heat. It is then readilyapparent as to how the stainless steel tubes became sensitized.

Replacement of both tubes was made with Inconel tubing,non-sensitized and of slightly heavier wall. The slight bend wasnot .included as stress analysis indicated a lower stress levelwith straight configuration.

Very truly yours,

P. A. BurtStation Superintendent

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GOO ERIK BOULKVARO WEST

SYRACUSE, N.Y. 13202

September 17, 1971


" Dear Dr. Morris:

I wish to acknowledge with thanks the receiptof the letter released by Mr. Frank Schroeder authorizingus to proceed with the partial refueling of the Nine MilePoint reactor.

The Nine Mile Point unit is scheduled tocome out of operation today, September 17, 1971, in orderto initiate this refueling.

Sincerely,

T . BrosnanVice Presi ent and Chief Engineer

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f,'earDr. Morris:,f

I want to acknowledge the letter of September 8,

1971 sent out for you by Mr. Schroeder. We are endeavoringI

to assemble the information requested in that letter and will

have a representative at the meeting in your Bethesda office

on September 23, 1971.

Sincerely,

7. BrosnanVice Pr >dent and Chief Engineer

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August 26, 1971

Dr. Peter'. Morris, DirectorDivision of Reactor LicensingUnited States Atomic Energy Commissionwashington, D. C. 20545

Dear Dr. Morris:

Re: Provisional Operating License DPR-17Docket No. 50-220

In conformance with the Te'chnical 'Specificationsfor the Nine Mile Point'uclear Station, we are sendingyou under separat'e cover, forty (40) copies 'of theSemi-Annual Report for the period January 1,,1971through June 30, 1971.

Very truly yours,

F. J, SchneiderVice President,'perations

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June 24, 1971

Dr Peter A. Norms, DizectorDivision of Beactor LicensingUnited States Atomic Enez'gy CommissionVashington, D. C'..20545

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Be: Docket Number 50-220Provisional Operrrting License DPB-17

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viZZ z*ecall that part of the pzegz'am containedin a special r'eport dated May 10, 1970, to restore NineNile Point Nuclear Station to service, twas a completeinspection of the safe-ends at the end of oz dure'ng thefiz'st yeaz of opezation following the start-up. Theinspection twas completed and toe are happy to repozt thatno nm relevant indications ureze detected that mouldindicate pz'ogression of the pz'evious pzoblem.

Under'eparate covez'e aze sending you forty(40) copies of a zepozt entitled "Beactor Pzima S stem1nte rit l'ns ections". I'ncluded is not only the summaryan ta pertinent to safe-end inspections, but alsoinformation on pipe movements and pnmary system leakagedetection methods and ezpemence.

On the basis of ouz'xperience during the period,ve have re-evaluated the program and included the revisionsve expect to make in it.

Vez'y truly yours,

DOCKETEDUSAEC

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Regulatory File Gy.

ARVIN E. UPTONEUGENE B. THOMAS,JR.LEONARD M. TROSTCN

WASNINOTON PARTNCRS

May 26, 1971ONC CHASE MANHATTAN PLAZA

NCW YORK, N. Y. IOOOS

Dr. Peter A. MorrisDirector'ivision of Reactor LicensingU.S. Atomic Energy CommissionWashington, D.C. 20545

WASHINGTON TCLCPHONC:202 FEDERAL 8 OIII

Re: Niagara Mohawk Power CorporationDocket No. 50-220

Dear Dr. Morris:

As counsel for the above-named licensee andpursuant to Section 50.71(b) of the Commission'sRegulations, we hereby transmit ten (10) copies ofNiagara Mohawk's 1970 Annual Report.

Very truly yours,

LeBoeuf, Lamb, Leiby & MacRaeAttorneys for Niagara Mohawk

Power Corporation

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April 15, 1971

Dr. Peter A. Morris, DirectorDivision of .Reactor LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

Dear Dr. Morris:

I acknowledge with thanks the receipt of your letter

of April 14, 1971 and the Amendment No. 2 to Provisional

Operating License No. DPR-17 which accompanied it. This

is the amendment that authorizes the operation of Nine Mile

Point Nuclear Station at power levels up to 1850 megawatts

(thermal) .

Sincerely,

T J. BrosnanVice P ident and Chief Engineer

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Dear Dr. Morris:

Thank you for the Notice of Proposed Issuance ofAmendment to Provisional Operating License and the supple-mentary material which accompanied your letter of March 3,1971.

After the amendment is issued, we will send to youa reissued set of Technical Specifications for Nine Mile Pointincorporating all of the changes to date.

Sincerely,

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WAsHINGToN, D. C. 20036August 1~7, 1970 ONC CHASC MANHATTAN PLAZA

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WASHINOTON TCLCPHDNCI202 FEDERAL B OIII

Dr. Peter A. MorrisDirectorDivision of Reactor LicensingU.S. Atomic Energy CommissionWashington, D.C. 20545

Re: Nia ara Mohawk Power CorUSAEC Docket, No. 50-220

Dear Dr. Morris: Regulate rjj Filo Cy.

I transmit to you herewith on behalf of'iagaraMohawk Power Corp. a chec'k for $ 624.00 in payment of the fee,due pursuant to section 170.21 of the Commission's regulations,in connection with Niagara Mohawk's Petition Requesting Amendmentof License to authorize operation of the Nine Mile Point Plantat stretch capacity which was filed with the Commission byletter dated April 20, 1970.

Very truly yours,

John A. Lodge

JAL:cgbEnclosure

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Check No. 287506

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July 22, 1970

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Dear Dr. Morris:

Re: Docket Number 50-220Provisional Operating License DPR-17

We have completed the leak testing of the main steam isolationvalves of the Nine Mile Point Nuclear Station. This is in con'form-ity with your request of March 27, 1970, and our letter of agree-ment dated April 8, 1970.

On the first test, all valves except one were within theleakage criteria of 13.8 SCFH. The valve which was above thisvalue failed because a limit switch did not allow sufficient com-pression between seat and disc. Adjustment of the limit switchon the valve drive rectified the condition as verified by test of22 psig air pressure on June 24, 1970.

Results for all valves follow:

¹11 Inside¹ll Outside¹12 Inside¹12 Outside

8.5 SCFH3.1 SCFH4.2 SCFH0.7 SCFH

Details of tests, calculations, and procedures are on fileat the station and may be examined or supplied to you if required.

Very truly yours,

F. J. SchneiderVice President - Operations

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Docket No.- 50-220

Niagara Pohauk Power Corporation300 Erie Boulevard H'estSyracuse, hex York 13202

Attention". 'r. Minot H. PrattVice President and

Executive Engineer

DISTRIBUTIONDocument Room

>Socket FileDR ReadingDRL ReadingBranch ReadingCompliance (2)OGC (2)ACRS (3)D. J. Skovholt, DRLR. H. Vollmer, DRLD. L. Ziemann, DRL

C. J. DeBevec, DRLR. M. Diggs, DRL

Gentlemen)

Your 'WX dated June 26, 1970, requested that your surveillance programfor system expansion monitoring during hcatup, in accordance withPage 2-1, Paragraph 3, of your report, "Program for Restoration toService of gina Nile Point Nuclear Station", be considered a startuptest so that the inerting of the primary con'tainment nay be delayeduntil the completion of this test.

Ma note that this test is analogous to "Test; No. 10 - System Expansion"of the Startup Test Program described in FSAR Supplement No. 6, withrefinements in measurements and increased sensitivities being utilizedto assure system movemcnt as designed for restoration of the plant toservice, Mo agree that this test falls vithin the meaning of startuptesting as set forth in paragraph 3.3.1 of the Technical Specificationsto Provisional Operating License No. DPR-17.

Sincerely,

Peter A. kforris, DirectorDivision of Reactor Licensing

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May 8, 1970

Dr. Peter A. MorrisDirector of Reactor LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

Dear Dr. Morris:

Re: Docket No. 50-220

Submitted herewith aa e two documents entitled,respectively, "Reactor Primary System Investigation AtNine Mile Point Nuclear Station Report No. 2" datedMay 11, 1970, and "Program For Restoration To ServiceBased On Reports Of Primary System InvestigationNine Mile Point Nuclear Station" dated May 11, 1970.

Very truly yours,

M. H. PrattVice President and Executive Engineer

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April 30, 1970

Dr. Peter A. Morris,Division of Reactor LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

Dear Dr. Morris:

Re: Docket No. 50-220 I gegu'latoT'JFile Cy.

Submitted herewith is a document entitled "Reactor PrimarySystem Investigation at Nine Mile Point Nuclear Station" datedMay 1, 1970.

This document brings the results of the current investigationon the reactor primary system at Nine Mile Point up to date. Thisreport supersedes and replaces the "Preliminary Report Core SprayNozzle Safe End Nine Mile Point Power Station" dated March 27, 1970and submitted by my letter of transmittal of April 3, 1970.

Very truly yours,

M. H. PrattVice President and Executive Engineer

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April 8, 1970

Dr. Peter A. Morris',,DirectorDivision of Reactor LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

Dear Dr. Morris:

Persuant to your request of March 27, 1970, that our mainsteam line isolation valves be retested, we, will perform thetest on each individual valve during .the current outage.

A.E.C. Division of Compliance will be notified sufficientlyahead of the test date in order that they may witness the testif so desired.

Tests will be performed at 22 psig in accordance withTechnical Specification 4.3.3.f;(1) .(b) .(2) .

Very truly yours,

ot H. PrattVice President and

Executive Engineer

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April 3, 1970


Dear Dr. Morris:

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Re: Docket No, 50-220

Submitted herewith is a document entitled "Preliminary Report,Core Spray Nozzle Safe End, Nine Mile Point Power Station, NEKM-10159,March 27, 1970". This document is preliminary in nature as a progressreport, only. She investigation is continuing and no definitive con-clusions oi'ny kind can be drawn from the material in this report.A final report will 'be submitted later which will supercede and replacethis report and at that time conclusions may then be drawn.

Very truly yours,

M. H. PrattVice President and

Executive Engineer

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Niagara lhhavk Povor Corporation300 Eric Boulevard UestSyracuse, Nov York, 13202

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Wocket FileDR RhadingDRL ReadingBranch ReadingD. L. ZiemannR. H. VollmerR. M. DiggsOGCACRS (3)

Attention: Yw. 'lQnot H,Pratt'ice

President andExecutive Engineer

Contlomenl

. Recent experience vith SktR main stcam lino isolation valves indicatesthat the leak rate follovihg tho valve closure tasting during initialpover operation may bo greater'han that measured in the preoporational3.cafe rato tost. 's a result, vo'are revieving tho adequacy of the'currant ledk-testing requirements vith regard to tost method andfrequency.

Ue understand that you consider that tho Mno Silo Point main steamline isolation valves'meet the allovable leakage limit establishedin Technical Specification 4.3.3.f.(1).(b).(2). based on your eval-uation that tho initial leak rata test results vere satisfactory andthat the valve closure time tests performed at povor vere indicativeof continued satisfactory pcrformanco. Mc do not have complete infor-mation regarding the valve closure test„ hovcver, based on the infor-mation ve have, it is not clear Chat tho allovablo lealc rate is notexceeded folloving tho closuro test.. In any event, the testing thathas been performed does not relate to potential deterioration in thescaling capability of tho Nine Milo Point valves. lfc believe thata retest of those valves should be performed during your current outageto establish that the valve 1oakagc rate is currently vithin allovablelird.ts. Please inform us promptly of any plans you have in this regard.Me villbe pleased Co discuss tho mattor if you vish.

Sincerely,

Peter A. Norris, DirectorDivision of Reactor Licensing

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Regulatory FBe Cy.

Sanuary 22, 1970

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Dr. Peter A. Morris,, DirectorDivision of Reactor, LicensingUnited States Atomic Energy CommissionWashington, D. C. 20545

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Dear Dr. Morris:

This is in reply to your letter of August 22, 1969requesting radiological and other environmental information onprograms, studies, surveys and work carried out pertaining torecommendations made by'the United States Fish and WildlifeService.

In answering this letter, we wanted to'be able to give youthe latest and most<comprehensive information as completely aspossible. We have just completed a report covering and includingall the available information requested pertaining to the area of ourNine Mile Point Nuclear Station. This report is entitled "Environ-mental Pre-Operational Survey Nine Mile Point." As requested,'e are sending under separate cover fifteen copies of this reportfor your distribution within AEC and Fish and Wildlife Service. '

In connection with this subject, we would like to referyou to the additionally pertinent information on environmentalmatters, other than xadiological, which was included in the summaryof reports and studies and the four specific reports related tothermal effects of nuclear, plants sent to you on August 12, 1969in answer to Mr. Price's letter of June 27, 1969 requesting suchinformation.

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M. H. PrattVice President

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Gentlemen:

Nine Mile Point Nuclear StationP. 0. Box 32Lycoming, New York 13093October 23, 1969

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DOCKEIED

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OCTS V $69 —eAttention: Dr. Peter A. Morris, Director QV RECUQ'JOIE / 5

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fg.Reference: P.O.L. - IfDPR-17 I

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Start-up testing of the Nine Mile Point Nuclear Station requires that each of thesix solenoid actuated pressure relief valves (Consolidated Electro-Matic ff1525VX)be opened individually by remote-manual means with the reactor at full pressureand by-passing 20 percent steam flow to the condenser. Five valves opened satis-factorily; the sixth, ff121, failed to open when tried at 10:05 a.m., October 19,1969.

Technical Specifications (pg. 34, 3.1.5) require all six valves to be operablewhen the reactor pressure is greater than 110 psig, or reduction to that pressuremust be accomplished within ten hours.

With 250 psig reactor pressure and all rods in, at 3:00 p.m. the drywell wasentered and the difficulty located as the armature of the actuating solenoidbinding in its passage through a hole in the solenoid support plate. The arma-ture is built up of laminated iron with 1/8 inch thick brass straps on each sidewhich carry a roller between them below the support plate.

This valve had been tested four times during pre-operational testing withoutpressure on the reactor and had been blown during the hot functional test with-out malfunction. However, with the reactor operating at 20 percent power, theambient temperature surrounding the valve superstructure was considerably higherand caused the roller and brass strips to expand taking up the existing clear-ance. Repositioning of the brass strips by machining the roller provided thenecessary clearance. The other five valves were checked and found to have ade-quate clearance. Valve t121 was successfully tested on October 20, 1969.

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LAW OFFICES OF

LEBOEUF, LAMB,LEIBY 8I MACRAEI82I JEFFERSON PLACEI N.W.

WAsHINGToN, D. C. 20036

July 22, 1969

ONE CHASE M'ANHATTAN PLAEANEW YORK, N. Y. IOOOS

WASHINGTON TELEPHONE:202 FEDERAL 8-0 Ill

Regulatory Rle Cy.

Dr. Peter A. MorrisDirectorDivision of Reactor 'LicensingU. S. Atomic Energy CommissionWashington, D. C. 20545

Re: Niagara Mohawk Power CorporationDocket No. 50-220

Dear Dr. Morris:

As counsel for the Niagara Mohawk PowerCorporation we enclose, pursuant to 50.71 (b) of theCommission's regulations, ten (10) copies ofNiagara Mohawk's 1968 Annual Report.

Very truly yours,1$

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June 4 1969

United States Atomic Energy CommissionWashington, D. C.20545

Attention:

Gentlemen:

Mr. Peter A. Morris, DirectorDivision of Reactors icensing

"-, Docket No. 50-220Ew

In reply to your letter of May 23 1969, a strong-motionseismograph willbe installed at the Nine Mile Point Nuclear Stationprior to the first major refueling outage.

Present plans anticipate use of a device having threetriaxial sensor packages mounted remotely from a magnetic taperecorder for detailed information. In addition, a number of peakrecording accelerographs which could be analyzed immediately atthe Station willbe installed. We shall plan to meet with your staffto discuss the details of these installations before firm arrangementsare made to procure equipment.

Very truly ou

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M. H. PrattVice President and

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DOC KETEOUSAEC

JUN6 1969 5—REGUlATORY

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Docket Ho. 50-220MAY 8 3 1969

magea aloha>rk PaIrer Corporation300 Erie Boulevard infestSyracuse~ Hm York l3202

DistributionAEC PDocket FileDRL Reading,DR ReadingRPB-2

Reading'.

DeYoung,R. S, BoydV. StelloHSteele (2)Compliance (2)

Attention: 5h'i Hinot Bc PrattVice President 5

Executive Engineer

Gentlemen:

At a meeting on Apr&. 10> 1969, >re discussed our rectuirementsfor providing at least one strongmotion seismograph at theHine Mile Point nuclear Station. Ve indicated that such adevice could be installed any time prior to the first ma)orrefueling outage. lee mould appreciate your discussing arithus the specif1c requirements~ including sensitivity'ndlocation of the seismograph at the facilitybefore arrange-ments are made to procure equipment,

Sincere yours~

X'eter A. Norris~ DirectorDivision of Reactor Licensing

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WAsHINGTQNe D.C. 2OOS6

May 16, 1969

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ONE CHASE MANHATTAN PLAZANEW YORK, N. Y. IOOOS

WASHINGTON TELEPHONE:202 FEDERAL 8 OIII

Dr. Peter A. MorrisDirectorDivision of Reactor LiceIIIisingU. S. Atomic Energy CommissionWashington, D. C. 20545

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Re: AEC Docket 50-220Regulatory (,File CQ

Dear Dr. Morris:

Enclosed herewith is a copy of Niagara

Mohawk Power Corporation's 1968 Annual Report which

is submitted in accordance with Amendment No. 9 to

the Application for Licenses.

Sincerely yours,

gK/

LeBoeuf, Lamb, Leiby & MacRaeAttorneys for

Niagara Mohawk Power Corporation

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LAW OFFICES OF

LEBOEUF, LAMB,LEIBY eT. MACRAEl82I JEFFERSON PLACE, N.W.

WAsHINGToN, D.C. 20036

May 16, 1969

ONE CHASE MANHATTAN PLAZANEW YORKI N. Y. IOOOS

WASHINGTON TELEPHONE:202 FEOERAI. 8 Olll

Mr. Victor Stello, Jr.Division of Reactor LicensingU. S. Atomic Energy CommissionWashington, D. C. 20545

Re: AEC Docket 50-220

Dear Vic:

We have filed a copy of the Annual Report

with Dr. Morris by letter of this date. Enclosed

are nine additional copies for your use.

Sincerely,

Enclosures: I

Niagara Mohawk PowerCorporation 1968 Annual Report(9 copies)Letter LLL&N to Dr. Morris,5/16/69

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Attention: He. 5Hnot H. PrattVice President S Executive Engr.

Gentlemen'.

Ue have followed the progress of your program for pre-service inspec-tion of the various Hine Ktle Point reactor pressure vessel internals.Results of your program, as reported to us, demonstrate that none ofthe sensitized stainless steel reactor pressure vessel ceaponentsstum any indication of intergranuXar attack. Hmrever, certain fieldwelds that goin the contxol xod drive housings to the'tub tube" merofound to be defective. We understand that these field velds have been.repaired and inspected follmgng the hydrostatic test of the primarysystem. This matter was discussed in our Xetter of Jam3ary 6, X969.The results of these tests should ba submitted for our review.

Based on the prel&dnary results of our rcvieT<, me believe that asurveillance program xd3.1 be necessary for the Nine ale Point pres-sure vesseX, sensitized stainless steel material. Xt is our opinionthat such a program Twould provide assurance against the effects ofharmful corrosion of the furnace sensitized stainless steel. Thisnatter @as discussed at a meeting held on January 23, X969, TrLthxepxesentativcs of your company and the General KIectric Company.We need to keno@ your plans for implmenting a surveiXXance program,as mell as the technical details of. the. pxogram. TtIis informationshould be submitted for our revieTz.

We are milling to discuss any of the foregoing Td.th you if you sodesire.

Sincerely yours,

cc: Arvin Z. Upton, Esquire

Peter A. It'orris, MrectorDiviaion of Reactor Licensing

OFFICE >

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DATE >Form hEC-318 (Rev. 9-53) hECM 0240

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Niagara Hohavk Povex Corporation300 Erie Boulevard VestSyracuse, New York 13202

DISTRIBUTION:AEC Document RoomFormalSuppl.DR ReadingDRL ReadingRPB-2 Reading

"'rig:'LTedescoR. S. BoydCompliance (2)H. Steele (2)R. DeYoungV. Ste110

'.

Ferguson

Attention: Hr 1'Knot H. PrattPico President and

Executive Engineer

Gentlemen!

This refers to your letter dated December 31, 1968 in vhichyou presented a proposal to complete your reactor pressuxevessel stub tube ~ection program folloviag the fieldhydrostatic tost. You requested that subsequent dye pene-trant inspection of tho remaining 54 stub tubes be limitedto the field velds and need aot include the shop'oids andstub tube surfaces. You also indicated that the inspectionvould be performed using procedures agreed upon by x'opre-sentatives of tho Division of Compliance,

'Pe have removed your 1equost and conclude that because 75stub tubes have already been completely inspected and foundto be free of defects, further testing of the remaining 54stub tubes beyond the stub tube to control rod drive housingfield veld vould aot be necessary.

Sincerely yours,

ORIGINAL SIGNEO ByPeter A. Morris

Peter A. Nor'ris, DirectorDivision of Reactor Licensiag

cc: Axvin E. Upton, EsquireLeBoeuf, Lamb~ Leiby 5 NacRao

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DISTRIBUTION:AEC Pub. Doc. Rm.PormalSupplDR ReadingDRL ReadingRPB-2 ReadingOrig: HSteele (2)R. S. BoydT. B. Conner, OGC

C. A. Lovejoy, OC

V. Stello

Xn order to coDpletc our review of p'our financia1 Qualificationsconcerning your application for a license to opcrata tho IZneHile Point nuclear reactors itw~ be 'necessary that you provide-additional financhQ. data in accordance eith the enclosed amend-ment to 10 CPE Part M. TMs infoxantion should include:

1. Eatiaated annual costa of operating the nuclearfacilityfor a. Hve +ear periods

20 Zstitiated coats of 'pcrmanent1$ 'hutting dole thefacility and staining 9.t ilx. a dafo coItdition,if.and T1hca. it stay occur.

3. 1968 Annual Ecport of Biagara lmItmrh Pot:crCorporation IIIIcnit beccnao nVailable,

'iLhe aB070 date, 'QIIould be, filed GQ an QHOQQclent to Qonr application pIdth three copies aione4- Under .oath or aHirnation and. thirty tltoconf'omcd copies.

Sincerely yours,ORIGINAL SIGNED BY

Peter A Morris

Peter A. Puxxis> Mx'cctor'viciomef Reactor X icenoinIp

Eclclo8ure a

Amend. to 10 Cigar 5Q

cc: Axvia, B. UPtonp Esp. - vw(enc.K.oBocuf, Xeab~ Leiby' ~~cEao

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Attention: Nr. John Lodge

Gentlemen:

AUG I 6 196IUU

DIUTIIZUUTXON:Document Boom, w/encls. 1 86 3State Heal.th, license onlyCompliance, Beg. 1, v/encls.

1%3ubject file, w/encls. 1 8a 3H. J. McAlduff, OBOO, v/encl. 1

D. George, NMM, w/encl., 1N. Doulos, DML, v/encl. 1C. Luke, DML;CB, w/encl. 1T. Engelhardt, OGC, w/encls.

1%3L. Baumgarden, OC, v/encls.1%3

STBBr. reading file, w/encl. 1Div. reading file, w/o encl.

L'ncloscd io Special Nuclear Material License No. GR4-1029 for tbc Ninekiile Point Station of the Diacara Po"ex Corporation. Also enclosed ioXndcmnity AErcement No. 3-36 1'or your review, acceptanco and return ofone signed copyr

The ABC usco electronic data processing equipment to record thc location~by licensee~ of special nuclear materLal, This system uses a thrcc-lcttcr Reporting identification Symbol to identify licensceo who submitmaterial transfer reports and p riodic material status reports inaccordance with 6 70.>3 and 070.j' of the Co~ooion'o regIQ.ationo.

~ ror this purpose~ ve have asoig:eel to you the following Reporting identi-fication Symbol: YGX, An czManation of when and, how the symbol io tobe used io given in the attached instruction oheet. Your cooperationvillbe approciate6T ~

I

Please note the attached leab, teat condition for the plutonium neutronsource r

Sincereiy youro~

Robert L. Layt'icldSource 5 Special Hucloar khterialo

BranchDivision of'aterials Liccnoing

Hncloourco:1. License No. GNtf-1028

n

OFF IC)I Xndcmnity Ag cment Ho, B

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rorm AEC-401'-ss) UNITED STATES

ATOMIC ENERGY COMMISSION

SPECIAL NUCLEAR MRTERIRL LICENSE

Pursuant to the Atomic Energy Act of 1954 and Title 10, Code of Federal Regulations, Chapter1, Part 70, "Special Nuclear Material Regulations," a license is hereby issued authorizing the licenseeto receive and possess the special nuclear material designated below; to use such special nuclearmaterial for the purpose(s) and at the place(s) designated below; and to transfer such material topersons authorized to receive it in accordance with the regulations in said Part. This license shallbe deemed to contain the conditions specified in Section 70.32(a) of said regulations, and is subjectto all applicable rules, regulations, and orders of the Atomic Energy Commission now or hereafter ineffect and to any conditions specified below.

1. Name

2. Address

Licensee

Niagara Mohawk Power Corporation

300 Erie Boulevard. WestSyracuse, New York 13202

3. License No.

SNM-10284. Expiration Date

December 31, 1968, or uponconversion + cont. next a e

5. Docket No.

70-10726. Special Nuclear Material

Uranium enriched. in the U-235isotope; and plutonium.

7. Maximum quantity of special nuclear materialwhich licensee may possess at any one timeunder this license U-235: 2230.2 kilogramscontained. in 540 fuel elements, and5.54 grams contained, in in-coredetectors. + cont. next age)

S. Authorized use Fuel elements: For storage and inspection only in accordanceith the statements, representations, and conditions specified in the licensee'spplication dated. July 7, 1967, and supplement submitted. by the licensee's

oxne s Le Hoeut'aml> and. Letl> dated. Au st 10 1 6 . s: cont nex~t .a e9. Quantity of special nuclear material allocated to licensee pursuant to Section 70.31(b) of said part

CONDITIONS

10. Unless otherwise specified, the authorized place of use is the licensee's address stated in Item 2above.Authorized. place of storage for the fuel elements: The fresh fuel vault and

the spent fuel pool at the licensee's Reactor Building, Nine Mile PointNuclear Station, Scriba, New York.

Authorized place for inspection of the fuel elements and. for using the otherspecial nuclear material listed. in Item 7, above: The Nine Mile PointNuclear Station, Scriba, New York.

FORM AEC 401/410A

JqlglP

U. S. MIC ENERGY COMMISSION page 2 of 2 pages

SPECXAL NUCLEAR

MATERIALLICENSEn

SupplemenIary Sheet

License Number

Pursuant to 10 CFR 70.24(d) the licensee is exempted from the requirements of10 CFR 70.24(a)(l) in the spent fuel storage area during the period of time that thespent fuel pit is flooded, provided. that the procedures described in the licensee'ssupplementary application submitted by the licensee's attorneys, Le Boeuf, Lamb,8c Leiby, dated. August 10, 1967, are followed.,

12. The licensee shall comply with the attached, leak test condition for the sealedplutonium source.

<4. of Construction Permit CPPR-16 to an operating license, whichever is earlier.

+7. Plutonium: 1.0 microgram contained in plated discs and. 480 milligrams encapsulated.as a Pu-Be neutron source.

+8. Xn-core detectors, plated discs, and. the Pu-Be neutron source: For use inaccordance with the procedures described in the licensee's application dated July 7,1967, and supplement submitted by the licensee's attorneys, Le Boeuf, Lamb, 8o Leiby,dated. August 10, 1967,

P8 8/tv/~ZFor the U. S. Atomic Energy Commission

August 16~ 1967 by Robert L . LayfieldDivision of Motorial s Licensing

Washington, Di C 20545

LICENSE CONDITION FOR

LEAK TESTING SEALED PLUTO'UM SOURCES

A. Each plutonium source shall be tested for leakage at intervals notto exceed six (6) months, 'n the absence of a certificate from atransferor indicating that a test has been made within six (6)months prior to the transfer, the sealed source shall not be putinto use until tested.

B. The test shall be capable of detecting the presence of 0.005 micro-curie of alpha contamination on the test sample, The test sampleshall bo taken from the source or from appropriate accessible sur-faces of the device in which the sealed source is pormanently orsemipermanontly mounted or stored. Records of leak test resultsshall be kept in units of microcuries and maintained for inspectionby the Commission.

C. If the test reveals the presence of 0.005 microcurie or moro of ro-movable alpha contamination, the licensee shall immediately withdrawthe sealod source from use and shall cause it to be decontaminatedand repaired or to be disposed of in accordance with tho Commissionregulations. lecithin five (5) days after determining that any sourcehas leaked, the licensee shall file a report with the Director, Div-ision of Materials Liconsing, U. S. Atomic Energy Commission', i'(ash-ington, D. C. 20545, 'describing the source, the test results, theextent of contamination and the correctivo action taken. A copy ofthe report shall be sent to the Director of the nearest AEC RegionalCompliance Offi'ce listed in Appondix D of Title 10, Code of FederalRegulations, Part 20,

D, The periodic leak test required by this condition does not apply tosealed sources that are stored and not being used. The sourcesexcepted from this test shall be tested for leakago prior to any useor transfer to another person unless they have been leak tested withinsix (6) months prior to tho date of use or transfer.

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Ua ihall aypdeciate your rrahinp Cbia inÃortraCion availabla Co

ua no fata@ than Pcbruary XY,1967'inccraly

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Attentions Ih. J. S. &<artChief System Pro)oct Engineer

CCQ tlcmenve

Xn order that Me cay co~iota our forecast of ppecial nuclear eateria1requirements, ue request that you advise us at your earliest conven-ience of your current estimated schedu1o of vithdrmals,and returns ofspecial nuclear aateria1 for 1967 under Construction Per@itNo. CPPR-16. This inforaation should be furnished on a quarterlybasis for the period froo January 1, 1967, to December 31, 1967„ and

should include the corresponding assaya of urania@-2$ S.

Uc sha11 greatly appreciate your aching this inforoation available tous by October 6, 1966

Sincerelg yours,

DISTRIBUTION:AEC Public Doc. Rm.FormalSuppl+~DRL ReadingR&PRSB, ReadingE. G. CaseL. Kornblith (2)N. Mason (Originator)

I.t"De - -.„.)Cd'.80gcf $, Jog

Roger S. Boyd, ChiefResearch & Povcr Reactor Safety BranchDivision of Reactor Licensing

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Attention: „ t5r. J 8, EtiartCMof Spate~ Pro/oct Engineer

'ln order that Uc guy co@piete our forecast, of "pecial nuclearmaterial requirements,.vo reqaeat t1>at yolk advise ua at yourcarcoat conmnienca of your currant ostivwted achedulo ofuithdravaia an4 returns ef apccivL nuclear materia't for FS.ac@iYear 1967 ~nder'onstruction Pcmit Co. CPKbi.6 this inforea;tion s'honi8 be Xurniahe8 on a quarterly baaia for the pcrS.odZro~ July l, 1966 to 'JuT|o, 30, lN7 and. ahquM. include the,corresponQ,Gp~'sanga of „nraniQQ 235+

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Uo shn?l „rents approcf.ate your eahinp this inforr.atf.onzvaiiabld to ea by ~Snrch 3, 1966

Sinccrclg Qonra p

Ol'igMtet sSygf $pRoger S, Boy/

Roger 8 ~ Boyd~ ChiefHcaearc'h 5, Poser Poactor Safety BranchDivision of Coactor Licens j.qg

OFFmE > RL .............SURNAME ~

DATE 0Form AEC-318 (Rqv. ~)

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Attention: Hr. Hovard Phillips

Can t1em"n s

Xn ordar that UQ Say comp 1 Qte our foracGs t ofspecial nuclearaiatar$ al reguirenants, vc request that you advise us at yourearl ies t convenience of your

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qa timated schedule byquarters of'uithdravals and raturns of special nucloar xraterial 0includinp enrickn nt 1eve 1a for the third and fourth quartersof L is cal Year 1966 and the firat and second quartoro oK %sealYear 1967 undor Construction Parfit P»o. CPPR-16.

Tfo shall ~eatly appreciate your cabins this Informationavai labia to ua by Cctobar 4, 1965.

8 incerc ly yours,

png1nal signe4 bV:,

Roger S. BoY4

Rocar 3. Boyd,Chick'es

oarch 6 Poplar Reactor Bafety BranchMvision of Itaoctor X,icons in@

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HXACAHA NOHAMK NEETIHG- AEC STAFF - 8/26 65

G. R. ParkerM. S. CollettJay ForsterC. L. HillerR. S. LemanJ. H. EwartN. H. PrattG. K. RhodeH. D. PhilippF. J. SchneiderE. G. Thomas, Jx'.C. A. 3urtH. C. BarnherH. R. DentonR. T. CarsonL. Kox'nblith, Jr.D. R. NullexD. SullivanV. HooreB. GrimesS. HanauerN. GaskoR, Boyd ,

General ElectricGeneral ElectricGeneral ElectricGeneral ElectricGeneral ElectricHie@era NohowHie@era MohawkHiagara NohavkHis@era NohavkHie@are NohavkLe9oeuf, Lamb 6 LeibyHiagara NohawhGeneral ElectricAEC0AECWOAECWOAEC-RLAEC-RLAEC-SSAEC-RLACES

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INASHIROTON PARTNERS

LAW OFFICES OF

LEBO E UF, LAM B 8I LE IBYI82I JEFFERSON PLACE, N.W.

WASHINGTON 36, D.C.

June 11, 1964 ONE CHASE MANHATTANPLAZANEW YORK S, N.Y.

Mr. Robert Lowenstei.nAssi.stant Director of Regulati.onUnited States Atomic Energy Commi.ssi.onWashington 25, D. C.

Dear Mr. Lowenstein:

Re: Docket No. 50-220 2 ~ /~

Enclosed for your information are two copi.esof a brochure which were di.stributed yesterday torepresentatives of the ACRS and of the AEC staff whovi.sited the site of the proposed Ni.ne Mile Point NuclearStation to be constructed by Niagara Mohawk Power Cor-poration.

Very truly yours,

Enclosure

VItj '„JUN1 5 1964

93 b~ . i,'cIcIciccicII

eoFUCTNSIIIII & IIEQUUITION Rec'd I'0"

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nine mile point, units 1 and 2 - semi-annual report …semi-annual report of operation for the nine...

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