sucaan esoouction department .[th b · 2020. 4. 9. · 27. 1586(n46) electro-etching of section iii...

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! MISSISSIPPI POWER & LIGHT COMPANYHelping Build Mississippi

P. O. B O X 16 4 0, J A C K S O N. MISSISSIPPI 39205

.[th bsucaan esooucTioN DEPARTMENT Augus t 25, 1981

U. S. Nuclear Regulatory Commissio<. -

Office of Nuclear Reactor Regulat'.on ( [iUG 2 3 Jggj g gWashington, D. C. 20555 ,- g

cowssangg g^Attention: Mr. Harold R1r Denton, Director , gf)

IM b.Dear Mr. Denton:

SUBJECT: Grand Gulf Nuclear StationUnits 1 and 2Docket Nos. 50-416 and 50-417File 0260/0862Transmittal of Proposed FSAR

Changes and Responses to NRCSER Open Items

AECM-81/322

References: 1. Materials Engineering Branch SER Open Item - Code Case1644/ Regulatory Guide 1.85 Compliance

2. Hydrologic and Geotechnical Engineering Branch SER OpenItem - Design Basis Flood for Stream B and in Plant Area

3. Hydrologic and Geotechnical Engineering Branch SER OpenItem - Design Basis Water Level on Roof s

4. Chemical Engineering Branch SER Open Item - Organic Materials

1

: In response to your request for additional information, Mississippi Power& Light Company is submitting the enclosed materials updating informationpertaining to the above referenced items.

i This information represents proposed changes and additions to the GrandGulf Nuclear Station Final Safety Analysis Report ( FS AR) .

These proposed FSAR changes will be incorporated into the next availableamendment to the FSAR unless noted otherwise. If you have any questions, pleasecontact this office.

Yours truly,

,' #:r-

L. F. DaleManager of Nuclear Services

DWF/JDR:dn

Attachments: (See Next Page) !

8108280341 810825 hI g

[DRADOCKOSOOOPDR Member Middle South Utilities System

..

MIC01%2iPPI POWER O LIGHT COMPANY

U. S. Nuclear Regulatory Commission AECM-81/322Of fice of Nuclear Reactor Regulation

Attachments: 1. IfrEB SER Open Item - Code Case 1644/ Regulatory Guide 1.85Compliance

2. 10EB SER Open Item - Design Basis Flood for Stream B & in PlantArea

3. IIGEB SER Open Item - Design Basis Water Level on Roofs

4. CEB SER Open Item - Organic Materials

cc: Mr. N. L. StampleyMr. G. B. Taylo r

Mr. R. B. McGeheeMr. T. B. Conner

Mr. Victor Stello, Jr., DirectorOf fice of Inspection & EnforcementU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

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Attachment I to AECM-81/ 322Page 1 of 3

SER Open Item - (tfTEB)

We have evaluated the ASME Code Cases listed as applicable to the reactor coolantpressure boundary by the applicant in FSAR Table 5.2-1. Code Case 1644-4, 5 and6 are listed, however, no mention is made of the additional requirements imposedfor acceptance in Regulatory Guide 1.85, " Materials Code Case Acceptability, ASMESection III, Division 1. Accordingly, the applicant is required to determine ifthe additional requirements imposed by Regulatory Guide 1.85 were met in theGrand Gulf Units. If the additional requirements were not met, the applicantshall justify his position.

Response

The maximum measured ultimate tensile strength of the component suppart materialat Grand Gulf Nuclear Station has not exceeded 170 ksi per Regulatory Guide 1.85.See revised Table 5.2-1. This change will be incorporated into the next availableamendment to the FSAR. Code Case 1644-4 has not been used at Grand Gulf Nuclearstation.

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Attachment I to AECM-81/322 OGPage 2 of 3 FSAR

TABLE 5. 2-1 (Cont . )

18. 1516-1 Welding of Seats or Minor Internal Permanent Attachments >

in Valves for Section III application

19. 1535 Hydro Testing, Section 3, Class 1 valves

20. 1541-1, Hydrostatic Testing of Embedded Class 2 and 3 Piping for1541-3 Section III Construction

21. 1557-1 Steel Product Refined by Section Melting

22. 1562 Qualification of Forming and Bending Procedures for Class1, 2, and 3 Components

23. 1567 Testing Lots of Carbon and Low Alloy Steel CoveredElectrodes

24. 1572 Fracture Toughness, Section Class 1 Components

25. 1578 SB 167 Nickel Chrome Iron ( Alloy 600) Pipe or Tube,Section III

26. 1580-1 Butt-welded Alignment Tolerances and Acceptable Slopes forConcentric Centerlines for Section III, Classes 1, 2, and 3

27. 1586(N46) Electro-Etching of Section III Code Symbols

28. 1620 Stress Category for Partial Penetration Welded PenetrationSection III, Class 1 Construction

29 1622 PWHT of Repair Welds in Carbon Steel Castings, Section III,Classes 1, 2, and 3

30. 1637 Effective date for Completion With NA-3700 of Section III

31. 1644-5, Additional Materials for Component Supports - Section III,1644-6, Subsection NF, Classes 1, 2, 3, and MC Constrection1644-7 (Note (1))

32. 1651 Interim Requirements for Certification of Component Supports,Section III, Subsection NF

33. 1677 Clarification of Flange Design Loads, Section III, Classes1, 2, and 3

34. 1682, Alternate Rules for Material Manuf acturers and Suppliers1682-1 and MC Construction, Section III, Subarticle NA 3700

Sheet 2 of 4

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Attacnment 1 to AECM-81/322Page 3 of 2 GG

FSAR

TABLE 5. 2-1 ( Cont . )

50. 1614 Hydrostatic Testing of Piping Prior to or Followingthe Installation of Spray Nozzles for Section III,Class 1, 2, and 3 Piping Systems

51. 1588 Electroetching of Section III Code Symbols

52. N-240 Hydroststic Testing of Open-Ended Piping

53. N-241 Hydrostatic Testing of Piping

54. N242 Materials Certification

Restrictions set forth in Regulatory Guides 1.84 and 1.85 are followed asdelineated in Appendix 3A.

Note (1) The maximum measured ultimate tensile strength of the componentsupport aaterial has not exceeded 170 ksi per Regulatory Guide 1.85.

Sheet 4 of 4

,, .-.

Attachment 2 to AECM-81/322Page 1 of 2

SER Open Item

Design Basis Flood for Stream B (llGEB)Design Basis Flood in Plant Area

Response

Attached is a response evaluating the integrity of Culvert 1 into whichStream 3 drains. Since it is shown that Culvert I will not collapse.Maximum flood water elevation assuming 45% blockage of the culvert, isshown in FSAR subsection 2.4.3.5.2 to be less than the plant yard elet:ationof 132.8 feet. Therefore, there will not be flood water in the plantarea.

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Culvert 1, as stated in FSAR Table 2.4-28, is a 180 inch diameter corrugatedmetal pipe. The " Handbook of Steel Drainage and Highway ConstructionProducts" (PSAR Pg. 2.4-44 Ref. 41), specifies corrugated metal pipe to bein conformance with ASTM Specification A444 which states that the metal isto be steel with a minimum yield strength (Fy) of 33 ksi. Table HC-6 ofReference 41 indicates that the culvert (7 ga. w/6 x 2 corrugations) iscapable of withstanding a Cooper E80 live load along with a maximum coverof 52 feet. The Culvert I design requirements are for a H2O highway liveload and a cover of 15.1 feet.

Since the actual cover is greater than the 36 inch minimum required tosustain an E80 live load, Culvert 1 is capable of supporting all highwayand construction live loads up to an equivalent E80 railroad load withoutdanger of structural collapse. The culvert was tested in excess of 400 tons whenthe stator for the turbine generator was transported over the culvert.There was no damage to the culvert or surrounding soil. The maximum periodic loadthe culvert is expected to see during plant operation is 150 tons when the spentfuel casks are transported over the culvert.

Under these same conditions, slope stability of the road fill is maintained.The drainage basin which empties into Culvert 1 is specified in FSAR subsection2.4.3.5.2 as concrete lined, with riprap above the concrete. The concreteextends approximately 4000 ft. upstream of the culvert. Therefore , thepossibility of erosion or sloughing of soil or debris blocking theculvert is very low.

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SER Open Item

Design Basis Water Level on Roofs - (HGEB)

Response

Attached is response indicating the allowable maximum water level and the actualmaximum water level on the roofs of all safety related buildings. The numberand dimensions of all scupper drains and roof drains on these buildings are shown below.

Auxiliary Building - (14) 6" scupper drainsDiesel Building - (5) 6" roof drainsWater Treatment - (4) 6" roof drainsRadwaste Building - (9) 6" roof drainsRadwaste Building - (4) 6" scupper drainsCirculating Water Pump House - (4) 4" roof drainsControl Building - (6) 6" roof drainsFire Water Pump House - (3) 4" roof drainsS.S.W. Pump House - (4) 6" x 12" overflow drains

Controi building

The control building roof is capable of supporting 47 1/2 inches of water atwhich point the weakest supporting member is at its code allowable stress fornormal operating conditions. This value considers the effect of dead and liveloads only. Pressure effects from wind conditions were neglected.

Since the center line of scuppers are located 8 inches above the roofing and theparapet height itself is 18 1/2 inches, the maximum control building roof stresswill be well below code all wables.

Enclosure Building

The enclosure building roof is sloped at 1/4 inch per foot and is constructedof built up roofing on rigid insulation supported by 1 1/2 inch - 18 gage metaldeck. The maximum depth of water that the metal deck roof system can supportwithout exceeding code allowable stresses is 9 3/4 inches. The centerlines ofscuppers and parapet overflows are below 9 3/4 inches therefore the roof systemwill perform without impairing structural capability due to accumulation of water.

Standby Service Water Pump House

The SSW Cooling Tower Basin Pump House, by conservative analysis methods, iscapable of supporting 19 inches of water at w' ich point the weakest supportingcomponent is at its code allowable stress fo. normal operation conditions.This value considers the effect of dead and live loads only. Pressure effectsfrom wind conditions were neglected.

Since the height of the parapet is 18", the maximum pump house roof stress willbe below code allowables.

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Attachment 3 to AECM-81/ 322Page 2 of 2

Auxiliary Building

The auxiliary building roof consists of six roof s at dif ferent elevations,each enclosed with a separate parapet wall.

The maximum water level that can be carried by these roofs without a structuraldistress is significantly higher than the top of the parapet walls. However,since this level cannot occur, the results presented below indicate the maximumwater level to be equal to tb- top elevation of the parapet walls:

1. Roof above the refueling areaT.O.C. El. 266'-0"Parapet El. 269'-0"3'-?? of water

2. Partial roofT.O.C. El. 242'-0"Parapet El. 243'-6"l'-6" of water

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3. Two partial roofsT.O.C. El. 228'-O'Parapet El. 229'-6"l'-6" of water

4. Roof above cable structureT.O.C. El. 206'-0"Parapet El. 207'-E"l'-8" of water

5. Partial roofT.O.C. EL. 185'-0"Parapet El. 187'-0"2'-0" of water

In all cases the roof is a reinforced concrete slab with a nominal thickness of2 feet.

The scuppers and parapet wall overflows are located below the maximum waterlevel on all roofs. No tornado effects have been considered in the evaluationof the auxiliary building roofs.

| Diesel Generator Building

I

( The roof of the diesel generator building is a two feet thick reinforced concreteslab. The T.O.C. elevation is 172'-0". The maximum water level that can becarried by the roof without structural distress is significantly higher than thetop of the parapet wall. The scuppers are located below the top of the parapet

| wall. lae top of the parapet is at elevstion 174'-0". Since the water willoverflow the parapet wall at this elevation the maximum water level is 2'-0".

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SER Open Item

Organic Materials - (CEB)

NRC Questior 281.8 Indicate the total amount of protective coatings and(6.1.2) organic materials used inside the containment that do

not meet the requirements of ANSI N101.2 (1972) andRegulatory Guide 1.54. Evaluate the generation rateas a function of time of combustible gases that canbe formed f rom these unqualified organic materials underDBA conditions. Also evaluate the amount (volume) ofsolid debris that can be formed f rom these unqualifiedorganic mmaterials under DBA conditions that can reachthe containment sump. Provide the technical basis andassumptions used for this evaluation.

RESPONSE

Item 1. The total amount of protective coatings and organic materials usedinside containment that do not meet the requirements of ANSI N101.2 (1972)and Reg. Guide 1.54.

This item is addressed in the attached revisions to FSAR subsection6.1.2.1, Table 6.1-2, and Table 6.2-53, which will be incorporated intothe next available amendment to the FSAR.

Item 2. The generation rate of hydrogen that can be formed from these unqualifiedorganic materials under DBA conditions as a function of time.

This itcm is provided in Figures 281.8-1 and 281.8-2 indicating thegeneration rates of all sources of hydrogen due to a main steam linebreak or a recirculation line break. The calculation on the hydrogengeneration rate of organics used a conservative value of G = 5.0obtained frc the insulation vendor.

Item 3. The amount of solid debris that can be formed from these unqualifiedorganic materials under DBA conditions that can reach the containmentsump.

As discussed in FSt.n subsection 6.1.2.1, all significant protective coatings appliedto surf aces inside containment have been tested to ensure they will remain intactfollowing a LOCA and applied with a quality assurance program that meets the intentof ANSI N101.2. As indicated in Table 281.8, certain mechanical equipment insidecontainment is coated with non qualified organic coatings. These items are procuredfrom several different vendors and are painted by the vendor in accordance withconvential industry practices. The total surf ace area of the non-qualified coatingsis 6224 sq. ft./ unit (2 cu. ft.) with a total weight of approximately 160 lbs.This small amount of non qualified coatings is not considered a detriment tosafety for the following reasons:

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o The source of the non qualified coatinge is from several relativelyL'

small components spread throughout the :ontainment interior.

The ECCS suction piping is located in the suppression pool and isocontinuously submerged in a minimum of 4 feet of water. If some of thenon qualified paint is stripped f rom its components, it will likelyeither float in the pool surface or be dispersed throughout the pool.,

,

1 o As discussed in FSAR subsection 6.2.2.2, ECCS analyses have beenconservatively performed assuming 50% of each strainer is clogged.

o The ECCS system line strainers are designed to prevent passage ofparticles larger than 0.1 inch diameter. This value is less than the1

; diameter of the RHR heat exchanger tubes, contaiament and ECCS sprayj nozzles, reactor coolant flow channels, and the ECCS pump running

clearances so that paint particles which could-potentially block-'

| engineered safety features are filtered out.!

o As discussed in FSAR subsection 6.2.2.2, the low approach velocityfor the strainers minimizes the possibility of paint particles migrating.,

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toward the strainers and causing clogging.

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' ttachment 4 to AECM-81/322Page 3 of 9

GG

FSAR,

| b. Paragraph B.3.a of Interim Position

Meeaetic measurements of production welds for delta ferrite contentsce unnecessary when austenitic stainless steel welding materials arecontrolled to deposit 8 to 25 percent delta ferrite, based on chemistry,except for Type 309 and 309L welding materials,- which are controlled to -'

i deposit 5 to 15 percent delta ferrite based on chemsitry.

c. Paragraphs B.4.a, B.4.b, and B.4.c of Interim Position,

Measurement of production welds for delta ferrite is not performed.1

] 6.1.1. 2 oomposition, Compatibility and Stability of Containment and Core Spray-Coolants

Demineralized water, with no additives, is employed in the core cooling wateri and containment sprays. No detrimental effects will occur on any of the ESFj materials from this high purity water. In addition, following an accident, the! containment and drywell atmospheres are maintained below 4 percent (by volume)f hydrogen in accordance with Regulatory Guide 1.7.

! 6.1.2 Organic Materials

6.1.2.1 Protective Coatings!

The use of organic protective coating with the containment is kept to a minimum.

Certain items of mechanical equipment and miscellaneous supports are painted withunqualified organic coatings. The total area is approximately 5744 sq f t.

{ Approximately 72,500 square feet of concrete surface is coated within the containment.

( Out of this, approximately 52,400 square feet of concrete floors and wall surfacesj are coated with a thick film surfacer and catalized epoxy, approximately 12,100| square feet of concrete wall surfaces are coated with 12.0 mils of catalyzed epoxy

and approximately 8,000 s ;uare feet of concrete walls are sealed. All significant. protective coatings applied to surfaces within the containment and drywell have been

tested to demonstrate that they will remain intact on the surface to which they areapplied during postulated IDCA conditions. Tests are performed in accordance withSection 4 of ANSI N101.2, Protective Coatings (Paints) for Light Water NuclearReactor Containment Facilities, to meet or exceed DBA conditions described in-subsection 6.2.1.

'Major carbon steel components, such as the containment liner plates, structural

'

and miscellaneous steel, polar crane, etc. are protected with an inorganiczine primer only, with no organic topcoat (with exception of approximately11,500 square feet which is topcoated with catalyzed epoxy). The suppliersof inorganic zine primer have issued written statements' certifying that

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any coating leaving the surface during a LOCA would be in the form of apowder that would not clog the ECCS suction screens of strainers.


All organic coatings applied to iteel and concrete surfaces are controlled by |a quality assurance program which assures that the coatings are applied inaccordance with project specifications and manufacturers' recommendations.

Documentation required by the quality assurance program provides the samedegree of documentation as listed in Section 7, ANSI N101.4. The projectposition on Regulatory Guide 1.54 is discussed in Appendix 3A to this FSAR.

6.1.2.2 Other Organic Materials

A listing of exposed insulation, lubricants, plastics, etc., in the containmentis included in Table 6.1-2.

6.1. 3 Post-Accident Chemistry

Not applicable to Grand Gulf since chemicals are not added to containment spraysor primary cooling systems.

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6.1-5


CG

FSAR

TABLE 6.1-2

OTilER ORGANIC MATERIALS

Containment Buiiding (Excluding Drywell)_

Ltem bb te rial Amount Remarks

llVAC duct. insulation Fiberglass 200 lbs.Electrical cable insulation EPR, Hypalon, or 176,400 lbs. Designed to withstand

cross-linked radiation dosepolyethylene

Motor electrical insulation Synthetic enamel 90 lbs . *

or plastic filmActivated charcoal Coconut base 4,370 lbs. *

Lubricating oil Petroleum base 125 gals. *Rodo Foam II joint filler Polyethylene 270 lbs.Protective Coatings Unqualified Paint 160 lbs. |

Drywell Section

Item Ma te rial Amount Remarks

llVAC duct insulation Fiberglass 280 l bs .Electrical cable insulation FPR, llypalon, or 9,835 lbs. Designed to wit hstand

cross-linked radiation dos >polye thylene

; Motor electrical insulation Synthetic enamel 3,815 1.b.s *'

or plastic filmi Lubricating oil Petroleum base 110 gals. Rust-inhibiting, i.e.,

Shell Ensis 10J.*Rodo Foam II joint filler Polyethylene 35 lbs.

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O Contained within an enclosure or vessel

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Attachment 4 to AEC3-81/332 FSARPage 6 of 9 TABLE 6.2-53

SURFACE AREA 0F CORRODlBLES

Source Surface Volume of Volume ofArea in Corrodible Source Surface Corridible

Containment Material Area in Drywell MaterialsSource (ft2) (See Notes) (ft2) (See Notes)

Galvanized 6,104.0 a 6,104.0 asteel 18,874.0 a 1,642.0 a

9,743.0 e 612.0 a11,260.0 c b,558.0 e11,792.0 c 16,490.098,300.0 b 11,625.0 .

5,032.0 a -- --

13,100.0 a,d -- --

2 3TOTAL 174,205.0 f t 25.76 ft 32 43,031.0 ft 6.17 ft

Zinc-basedpaint

Dome 24,153.0 a

Containment 46,520.0 a 10,750.0-Drywell liner aliner(excludingsuppressionpool)

Struct. SteelElev. 208' 10,400.0 a 21,000.0-Total a

184' 5,000.0 a161' 10,250.0 a142' 14,500.0 a117' 17,600.0 a

Misc. steel, 52,686.0 a 22,608.0 asupports,hangers,equipment,iiP P ng

2 3 2 3TOTAL 181,109.0 ft 60.37 ft 54,358 f t 18.12 ft

2 3Aluminum 3,222.0 ft 138.8 fryOrganic Paint Unqualified - 6,224.0 ft

2Qualified - 11,500.0 ft

TOTAL 17,724.0 f t 5,908 ft 3 (3)2

Notes: Corrodible material thicknesses as follows:

a. 2-5 tils; average 4 mils used in calculationb. 0.625 oz/f t = 0.731 mils E 1.0 mil, conservative value usedc. 1.0 oz/ f t = 1.17 milsd. 31,000 oz total; average 4 mil thickness calculated.

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TABLE 281. 8

UNQUALIFIEI PAINTS INSIDE CONTAINMENTS

GRAND GULF UNITS 1 AND 2

Square Ft. Area

Unit 1 Unit 2 Total

Catalog ilanger Supports (Estimated) 2000 2000 4000

Containment Coolers 165 165 330

Steam Tunnel Cooler Fans 150 150 300

Drywell Cooler Fans 900 90 0 1800

Reactor Recirc. Pump floist 60 60 120

Containment Cooler Hoist 5 5 10

CRD Removal lloist 5 5 10

CTMT Cooling System Charcoal Filter Trains Unit 795 795 1590

CTMT Dome Access Platform 170 170 340

' CTMT Lower Personnel Air Lock Air Shower 77 77 154

(CTMT Dome Access lloist 5 5 10

Miscellaneous Screens 14 14 28

Pressure Relief Valves 14 14 28

CTMT and Drywell Sump and Transfer Pumps 34 34 68

| Safety Relief Line Vacuum Breaker Valves 300 300 600

2" and Smaller C.S. Valves 200 200 400

Actuators for Valves 75 75 150|

| Lighting Fixtures 85 85 170|

Lighting Transformer and Panels 155 155 310

P.A. System 220 220 440

Miscellaneous 850 850 1700

TOTAL 6224 6224 12448

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GRAND GULF NUCLEAR STATION UNITS 1 & 2100 0

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