nrc: ml17208a420 - nrc.gov

1979 ANNUAL OPERATING REPORT

FLORIDA POWER & LIGHT COMPANY

ST. LUCIE UNIT f/1

FEBRUARY, 1980

Abstract: This report is submitted in compliancewith Technical Specifi.cation 6.9.1.5,4.4.11.3, 4.7.6.1.2, and 10 CFR 50.59.

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SUBJECT

Summary of Design Changes Per 10 CFR 50.59

PAGE NUHBER

Summary of Procedure Changes andSpecial Tests Per 10 CFR 50.59

41

Core Barrel Hovement Summary 42

Steam Generator Tube Inservice Inspection

Radiation Exposure Summary

Hangrove Survey

43

46

47

DESIGN CHANGES

On the following pages are descriptions, including a summary of the

safety analyses, of the design changes implemented at St. Lucie Unit

i'/1 during the period January 1, 1979 through December 31, 1979 in

accordance with 10 CFR 50.59.

PLANT CHANGE/MODIFICATION 111-76 PSL UNIT f/1

MODIFICATION OF THE INCORE CABLE CONNECTOR ASSEMBLIES

A high rate of failure of the original incore cable connector assemblieswas experienced. The vendor redesigned the connector to provide greaterreliability and modifications in accordance with the vendor's new designwere implemented.

This change does not constitute an unreviewed safety question as definedby 10 CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased because nocredit was taken in the accident analysis for the incore detectors,as discussed in Section 4.2.2.2.8, and because the system reliabilityhas been increased.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis" P port has not been created because the function,location, or significant physical configuration of the incore cableassemblies has not changed.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since Technical Specification 3.3.3.2for the incore detectors has not changed.

This change does not represent a change to the facility as described in theFinal Safety Analysis Report.

PLANT'CHANGE/MODIFICATIONNO. 132-76 PSL UNIT //1

STEAM GENERATOR WIDE RANGE WATER LEVEL INDICATION

The steam generator narrow range level indication provides indicationonly in the normal" operating range.'ide range indication would beextremely useful in any steam generator level excursion, and the appro-priate transmitters indicators and circuitry were installed to providewide range indication.

This change does not constitute an unreviewed safety question as definedby 10CFR,50. 59 because:

1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased since the modi-fication was implemented using category two, Seismic I requirementswhich is identical to the affected piping classification, Class IEcable and separation criteria required by the FSAR, and the wide rangesystem provides no safety function.

2. The possibility of an accident or malfunction of equipment importantto, safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created because the widerange level indication provides no safety function and cannot affectany system that does provide a safety function.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Technical Specificationshave been changed or are applicable.

PLANT CHANGE/MODIFICATION NO. 150-76

Page 4

PSL UNIT /$ 1

(LOSS OF DIESEL GENERATOR CONTROL POWER ANNUNCIATION

In order to enhance the reliability of the diesel generators, relays wereinstalled across the control power fuses to detect and annunciate blownor pulled fuses.

This change does not consititue an unreviewed safety question as definedby 10CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased because theModification does not change the function, operation or response ofthe diesel generators and could increase the reliability.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than'ny previously evaluated in theFinal, Safety Analysis Report has not been created by the addition ofa blown fuse annunciato'r circuit on the diesel generator controlpower fuses. 'I

3. The margin of safety as defined in the bases'f'he Technical Speci-fications has not been decreased since Technical Specification 3.8.1governing the diesel generators has not been changed.



Page 5

PSL UNIT l/1

RELOCATE SAMPLE VALVES CONTROL SWITCHES

Local control switches for primary sample valves V5200, V5201, V5202, V5203,V5204 and V5205 were located remote from the sampling point. New location insample room will enhance sampling operations.

This change does not constitute an unreviewed safety question as definedby 10CFR 50.59 beacuse:

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased because system flowpaths, flow rates, thermal capacity, mechanical operability or controllogic (CIS) has not changed.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created by physically relocatinga contxol switch without changing system function or reliability.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Tech Specs have changed.

/PLANT CHANGE/MODIFICATION NO 355-78

Page 6

PSL UNIT

foal

REPLACE LETDOWN FLOW LIMITER

PC/M 355-78 Replaced Fischer Porter Model 55EL 3000 Flow Limiter withRochester Instruments Model 1362 which has a sharper cut off.

This change does not constitute an unreviewed safety question as defined by10 CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or malfunc-tion of equipment important to safety previously evaluated in the FinalSafety Analysis Report has not been increased by substituting a moreaccurate instrument of equal reliability.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created because the function of thesystem and instrument remains the same.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased. No Technical Specifications have been changed.


LANT CHANGE/MODIFICATION NO. 359-78 PSL UNIT 81

CEA BLOCK CIRCUIT TEST EQUIPMENT

A permanently installed test circuit with key lock switch was installed to allowoperators to perform required CEA block circuit surveillance without the needof adding jumpers for a simulated signal.

This change does not constitute an unreviewed safety question as definedby 10CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or malfunc-tion of equipment important to safety previously evaluated in the FinalSafety Analysis Report has not been increased. This has been assured by theinstallation of a key operated switch and properly written procedures toprevent inadvertant operation of the system.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since CEA misalignment haspreviously been evaluated and this modification cannot affect any othersafety related systems or equipment.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased since Tech Spec 3.1.3 on the CEA's has not changed.


PLANT CHANGE/MODIFICATION NO. 369-78 PSL UNIT 81

ALARM AND TROUBLE SWITCH FOR FIRE DETECTION ZONES

Fire Protection Technical Specifications require periodic test for open circuitindication. Addition of test switches will expedite testing.

This change does not constitute an unreviewed safety question as-defined by10 CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or malfunc-tion of equipment important to safety previously evaluated in the FinalSafety Analysis Report has not been increased because this modification doesnot affect any safety related systems or equipment.

:2. The possibility of an accident or malfunction of equipment important to

safety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created by the addition of testswitches in the fire protection system since it is non safety related anddoes not affect any safety related systems or equipment.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased since no Technical Specifications have been changed.



FUEL HANDLING BUILDING VENT STACK AND EFFULENT MONITOR

Under certain postulated wind conditions, the potential existed forthe fuel handling building exhaust to be drawn into the RAB intake.An exhause stack was added to increase dispersion and a new radiationmonitor and flow transmitter were also added to simplify effluentaccounting.


l. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased. The FHB

HV&AC system is not safety related and cannot affect any safetyrelated systems or equipment.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created because the FHB

HV&AC system function has not changed and the new installation can-not affect any safety related systems or equipment.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Mchnical Specifications havebeen changed.


REPLACE SELECTED HYDRAULIC SEISMIC RESTRAINTS WITH MECHANICAL SEISMICRESTRAINTS

Experience has shown that hydraulic "snubbers" have had seal leakageproblems and that mechanical "snubbers" have had an excellent record ofreliability. 42 selected hydraulic snubbers were replaced with mechanicalsnubbers by this PC/M.


1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased. The replace-ment snubbers are consistent with the original design philosophy, willperform the same function and are more reliable than the originalhydraulic snubbers.

., 2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created since the functionof all safety related systems and components remain the same. Failureof a mechanical snubber would be no different than failure of theoriginal hydraulic snubber.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased, The 42 snubbers affected will bedeleted from Table 3.7-2 of the Technical Specifications. The TechSpecification was developed to assure that seal leakage was discoveredand is not applicable to mechanical snubbers.

This change does not represent a change to the facility.as described in theFinal Safety Analysis Report.

Page ll

PLANT CHANGE/MODIFICATION NO. 388-78 PSL UNIT Pil

FlHQfAHITE MSCV'S 1A 6 1B

Mainsteam check valves 1A & 1B flanges were drilled and furmanitepumped in to elimina~e steam leaks while at power to eliminate aunit outage.

This change does not constitute an unreviewed safety question as defined„ by 10 CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluatedin the Final Safety Analysis Report has not been increased. An

engineering analysis was completed prior to implementing this PC/Mand it was determined that using the furmanite process would notinduce any unacceptable stresses on the valve> however, a continuedleak could cause further degradation to the valve.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created since the functionof the valve has not changed and a main steam line break has pre-viously been evaluated.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Technical Specificationshave been changed.

This change does not represent a change to the facility as described inthe Final Safety Analysis Report.

PLANT CHANGE/MODIFICATION NO. 395-78V

FUEL TRANSFER TUBE SHIELDING

PSL UNIT /l1

Additional lead shielding was added over the fuel transfer tube atEL 62 between the FHB and the RCB to reduce radiation during transferof a spent fuel bundle through the tube.


1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased. The instal-lation of lead shielding cannot affect any safety related systems orequipment.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created since no safetyrelated systems have been affected.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Technical Specifications have beenchanged.

PLANT CHANGE/MODIFICATION NO. 411-78 PSL UNIT Pil

CONTAINMENT COOLERS RELIEF VALVES FLANGES INSTALLATION

Suction and discharge flanges were installed on the component coolingwater discharge line relief valves from the containment coolers. Thismodification will allow testing of these relief valves in accordancewith the 1974 ASM'ode, Section Zl, Paragraph EMV-3510.

This change is not an unreviewed safety question because:

1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased. Stressanalysis studies have shown that the addition of flanges, as comparedto welded fittings, will not affect the integrity of the system andtherefore the ability of the containment coolers to mitigate theconsequences of an accident will not be decreased.

I

2. The possibility for an accident or malfunction of a different type .

than any evaluated previously in the Final Safety Analysis Reporthas not been created. Loss of cooling water to the containment coolershas been evaluated in the single failure analysis of Section 6.2.2.3,Table 6.2-10 of the Final Safety Analysis Report. No other failureassociated with this modification can be postulated.

3. The margin of safety as defined in the basis for Technical Specification3.6.2.2 has not been decreased.



4160V SWITCH GEAR DIESEL GENERATOR LOAD SE UENCING RELAYS

The Diesel Generator sequencing time delay relays were replaced with relays witha smaller adjustable time range. This will allow a more accurate time delaysetting.

This change does not constitute an unreviewed safety question as defined by10CFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The replacementrelays are made by the same manufacturer to the same standards as theoriginal and therefore the resultant system is equal to the original,

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created. The function ofthe Diesel Generator and affected safety systems remains the same,and the loading sequence has not changed.

3. The. margin of safety as defined in the bases of the Technical Specificationshas not been decreased because no Technical Specifications have changed.

This change does not represent a change to the facility as described in the FinalSafety Analysis Report.


Page 15

PSL UNIT //1

EXPLOSIVE DETECTOR INSTALLATION

An electronic personnel explosive detector was installed at the main entrancestation for evaluation of meeting the requirements of 10 CFR 73.55.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety A'nalysis Report has not been increased. This installationis non nuclear safety related and cannot affect any safety related systemsor equipment.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Technical Specifications havechanged.

This change does not represent a change to the facility as described in the Finalfety Analysis Report.


,Page 16

PSL UNIT /31

SECURITY COMMUNICATIONS WITH LOCAL LAW ENFORCEMENT

PC/M 452-78 provided uninterruptable power supplies to communications consolesand a tie from the SAS to the radio transmitter on 43'levation to meet therequirements of 10CFR 73.55.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The abovemodification is non nuclear safety related and does not affect anysafety related systems or equipment.


3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Tech Specs are involved.


LANT CHANGE/MODIFICATION NO. 454-78

Page 17

PSL UNIT 81

CHARGING PUMP DISCHARGE PULSATION DAMPENER — PHASE IThis PC/M relocated the discharge valves for B&C Charging Pumps to a new locationnearer the pumps in preparation for the installation of a discharge dampener and

recirculation system in later phases.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased because only thevalve location has been changed, and the new installation was built tothe same standards as the original system.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function andquality of the charging system remain the same.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased since no Technical Specifications have changed.

'LANT CHANGE/MODIFICATION NO. 461-78

MODIFY COMPONENT COOLING WATER PUMPS MISSILE SHIELDS

PSL "UNIT !/1

Existing missile shields were welded making it difficult to remove for maintenance.This PC/M modified shields so they are bolted and can be removed.

This change does not constitute an unreviewed safety question as defined bylOCFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The reliabilityof the CCW system has not been decreased, the missile shields meet thesame criteria as the original welded ones,

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function andreliability of the CCW system remains the same.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased since no Technical Specifications have changed.


PLANT CHANGE/MODIFICATION NO. 479 PSL UNIT 81

CHARGING PUMP HEAD MODIFICATION

A crack in the original charging pump cylinder head required replacement of thehead. New head was manufactured with integral flanges instead of welded flangesof original head.

/This change does not constitute an unreviewed safety question as defined by10CFR 50.S9 because:

.1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased . A reanalysis of theseismic supports showed that the extra weight will not degrade, the seismiccapability; new materials and dimensions have been fully evaluated and willnot result in any degradation of the system.

.2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Rcport has not been created since the function and reli-ability of the system has not changed.

.3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Technical Specifications havechanged.



Page 20

PSL UNIT i/1

V'TEAMGENERATOR MODIFICATIONS RIM CUT)

The /f9 and 10 support plate lugs and rims were removed and certain tubes extendedto stake support plates to eliminate potential support plate cracking caused bytube denting.


The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. Evaluations havedetermined that this modification will not degrade the integrity, createexcessive stresses in or technically change the characteristics of theSteam Generators.

2. The possibility of an accident or malfunction of equipment important tosafety of a different'ype than any previously evaluated in the FinalSafety Analysis Report has not been created since function and reliabilityof the Steam Generators has not decreased.

3. The margin -of safety as defined in the bases of the Technical Specifi-cations has not. been decreased since no Technical Specifications havechanged.



Page 21

PSL UNIT Ill

MODIFY HARDWARE TO INCORPORATE NEW AND DELETED SECURITY POINTS

This PC/M documents numerous changes to upgrade the Security System.

This change does not constitute an unreviewed safety question as defined bylOCFR 50.59 because:

.l. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased because this modifi-cation is non-safety related and does not affect any safety related systems.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since no safety related systemsare affected.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Technical Specificationshave changed.



Page 22

PSL UNIT /I1

ESFAS RELAY CHANGES

The main steam isolation system auxiliary (isolation) relays were modified fromnormally closed to normally open and from "de-energize" to actuate to "energize"to actuate, and their power supply changed to a monitored bus annunciated inthe control room on "loss of power". This will allow maintenance on the auxiliarycircuit without the danger of inadvertant MSIS actuation.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The function ofthe above relays is to provide isolation between "A" .(B) MSIS and "B"(A) MSIV close circuits. The change from NC to NO changes the mechanismbut not the function of these relays. Failure of these relays alonecould not prevent MSIS actuation.


3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. Since no Tech Specs have been affected.



Page 23

PSL UNIT i/1

INSTALL HOUR METERS ON CHARGING PUMP BREAKERS

Hour meters were installed on the charging pump breakers to assist in planningpreventive maintenance.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The above metersare powered from a source (120 VAC) to cubicle heaters separate from thecharging pump control power via an auxiliary contact of the breaker andcannot affect charging pump operation in any manner.


3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Tech Specs are affected.



Page 24

PSL UNIT f31

ADD POWER OFF SWITCHES TO ALL CARD READERS

Switches were installed to isolate a single card reader for maintenance rather thanremove an entire loop from service.


1. The probability of occurrence or 'the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased because no safetyrelated systems or equipment were affected.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created because no safety relatedsystems or equipment were affected.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Technical Specifications werechanged.,


PLANT CHANGE/MODIFICATION NO.

Page 25

PSL UNIT //1

CCW PUMP MISSILE SHIELD STRUCTURAL CHANGE

A previous PC/M (461-78) modified the shielding so that the plates could be removed

for maintenance, however, a structural support beam remained to interfere with pump

removal. This PC/M provi'des for a bolted splice in the beam to facilitate removal.

{ This change does not constitute an unreviewed safety question as defined by10CFR 50.59 because:

„1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The added spliceis designed to be as strong as the original beam, therefore, the systemreliability has not decreased.

I

,2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function of theCCW system remains the same and the reliability has not decreased.

.3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because Technical Specification 3/4.7.3on the CCW System has not changed.



Page 26

PSL UNIT /f1

REGENERATIVE HEAT EXCHANGER SHELL DRAIN VALVE REPLACEMENT

An existing non-repairable valve was replaced by two more reliable valves.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased since the system was mademore reliable.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function of thesystem did not change and the system was made more r'eliable.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Technical Specifications werechanged.

PLANT CHANGE/MODIFICATION NO. 521-79Page 27

PSL UNIT /I1

ADD UNION TO AUXILIARYFEEDWATER PUMP TURBINE BEARING COOLING MATER LINE

A union was required in the cooling waterline to the 1C Auxiliary Feedwater PumpTurbine Bearings to allow removing the Auxiliary Feedwater Pump Cover.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The new installationmeets the same criteria as the original and therefore the reliability of thesystem has not decreased.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function and reliabilityof the system have not changed.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since Technical Specifications 3.7.1.2 onthe Auxiliary Feedwater system has not changed.



Page 28

PSL UNIT //1

HARD PIPING FOR INTEGRATED LEAK RATE TEST

Permanent piping was installed from existing ILRT connections near thecontainment penetration to extend to the area east of the diesel generatorbuilding to facilitate ILR testing.

This change does not constitute an unreviewed safety question as definedby lOCFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. Containment integrityhas been maintained to the same degree as the original installation byspecifying design standards equal to or better than that of existingpiping. No other safety related systems or equipment have been affected.


3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Tech Specs have changed.

This change does not represent a change to the facility as described in the FinalSafety Analysis'Report.

PLANT CHANGE/?JODIFICATION NO. 535-79

Page 29

PSL UNIT 81

STEAN GENERATOR PRIMARY MAtJJJAY GASKET RETAINER CLIP

This PC/H provides for the addition of clips to retain the steam generatorprimary gasket retainer plate while the primary manway cover is being secured.These clips will reduce manway cover replacement time and reduce personnelexposure.


1. The probability of occurrence or th'e consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased be'cause the manwaygasket retainer clips do not affect the structural integrity or thepressure boundary of the steam generators.

2. The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created since the function of thesteam generators has not changed and the reliability has not been decreased.

3. The margin of safety as defined in the bases of the Technical Specificationshas not been decreased since no Tech Specs have changed.



Page 30

PSL UNIT /$ 1

ADD SECURITY CARD READER AT RADIATION CHECKPOINT

This PC/M added a card reader at the radiation check point in the RAB

to enhance personnel movement and accountability.


1. The probability of occurrence or the consequences of an accident ormalfunction of equipment important to safety previously evaluated inthe Final Safety Analysis Report has not been increased since thischange is not safety related and will not affect any safety relatedsystems or equipment.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created because this changewill not affect any safety related systems or equipment.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Tech Specs have changed.


N


Page 31

PSL UNIT //1

VOLTAGE SWING MODIFICATIONS

An engineering evaluation stemming from the System Voltage Swing Study hasconcluded that MOV motors without temperature compensated thermal overloadrelays and with long valve stroke times (> 60 sec.) are not conservativelysized for all voltage variations. It was calculated that the thermal over-load relay might trip the MOV prematurely during repeated valve operation.This PC/M provides for resizing the thermal overloads for 13 MOV's to producemore conservative ratings. The PC/M also revises the normal and emergencypower supply to MCC 1C because of calculated .normal .loadings.


1. 'he probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. The portion of thePC/M concerning MCC 1C power supply is non-safety related, and will not affectany safety related equipment. All of the protective thermal overloads on safetyrelated MOV's are automatically bypassed on initiation of a safety actuationsignal, therefore, they will have no affect on the safety system.

The possibility of an accident or malfunction of equipment important tosafety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created. The circuitry, functionoperation or original design criteria of any safety related systems'utilizing any of the MOV's has not been changed.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased because no Technical Specifications havechanged.



Page 32

PSL UNIT //1

AUXILIARYFEEDPUMP 1C GOVERNOR IMPROVKKNTS

Improvements to the Auxiliary Feedwater Pump 1C Steam Turbine governor controlswere made as recommended by the manufacturer. These improvements included re-routing the governor servo drain line from the low point oil sump to the EGR

actuator to insure the hydraulic control loop is continuously oil filled, andaddition .of a support bracket to the oil sump assembly.


/

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. Since the improvementswere made to improve the reliability based on operating experience and thevendor's recommendation.

2. .- The possibility of an accident or malfunction of equipment important to, safety of a different type than any previously evaluated in the FinalSafety Analysis Report has not been created because the function of theauxiliary pump remains the same and the reliability should be increased.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Technical Specifications havechanged.



Page 33

PSL UNIT f)1

CEA GUIDE TUBE MODIFICATION

Wear sleeves were inserted into the guide tubes of selected fuel assemblies toprevent vibration caused wear. This PC/M is an extension of PC/Ms 397-78 and421-78 previously reported.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created. Report CEN-90 (F)-Psubmitted to the NRC for PC/M 397-78 and 421-78 is applicable to thismodification.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased.



Page 34

PSL UNIT dl

MODIFY DIESEL GENERATOR COUPLING (D.G. TO RADIATOR FAN)

~~ ~The D.G. vendor informed FP&L that the crank shaft coupling originally

supplied with the units had failed in other applications and recommendedthis modification.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased since this modificationwas implemented to improve upon original design.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created since the systemfunction has not changed and reliability has been improved.



Page. 35

PLANT CHANGE/MODIFICATION NO. 565-79 PSL UNIT /ll

AUTOMATIC INITIATION OF ESFAS "CIS" UPON ACTUATION OF "SIAS"

This modification was required by the NRC as a result of TMI-2 Lessons Learned.

This change does not constitute an unreviewed safety question as definedby lOCFR 50.59 because:

1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. Only 4 accidentswere identified that initiated "SIAS"wi.thout "CIS" under the previouslogic. The additional functions initiated by "CIS" will not impair theability to mitigate the consequences of any of these accidents.


3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. The revisions required to the TechSpecs will not decrease the margin of safety.


Page 36

PSL UNIT 81

COMPONENT COOLING WATER LINES RESTRAINT DISCREPANCY

Discrepancies in CCW lines 4-CC-142 and 4-CC-116 restraints were discoveredduring the "As-Builting" Program and corrected by this modification.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased since thismodification upgraded a deficient area to original design criteria.

2. The possibility of an accident or malfunction of equipment important.to safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created.




Page 37

PSL UNIT 81

MAIN STEAM CHECK VALVE ROCKSHAFT MODIFICATION

Repairs to tail link bushings and replacement of rockshaft were required dueto damage.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. Engineeringevaluation shows that new dimensions will slightly decrease the stiffnessof the rockshaft. At the same time it will improve the design withrespect to excessive radial deflection. The net result is there is nodecrease in reliability.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report has not been created, since the reliabilityand function of the system remain the same.




Page 38

PSL UNIT //1

RE/OVAL OF CONTAINMENT COOLER FANS LOCAL CONTROL STATIONS

The ability of the local push button stations to withstand LOCA conditions wasquestionable and since local control was not required, the local control circuitwas disconnected at the switch gear.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased, since the functionand reliability of the fan cooler has not changed.


'3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased. No Tech Specs are affected.


Page 39

PSL UNIT //1

POWER OPERATED RELIEF VALVE MODIFICATIONS

These modifications to the PORV disc and pilot valve actuating lever wererecommended by the manufacturer to improve operation and reliability.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased since the modificationswere made to improve original design.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety ANalysis Report has not been created since function ofthe PORV remains the same and reliability has been increased.




Page 40

PSL UNIT

//1'EPLACE

V 6478 WITH A TEE AND DIAPHRAGM VALVE

V 6478 is a 3-way valve discharging into A 6 B'aundry drain tanks. This PC/Meliminates this valve which traps debris and installs a more reliable system.


1. The probability of occurrence or the consequences of an accident or mal-function of equipment important to safety previously evaluated in theFinal Safety Analysis Report has not been increased. This installationis non-nuclear safety related and cannot affect any safety related systemsor equipment.

2. The possibility of an accident or malfunction of equipment importantto safety of a different type than any previously evaluated in theFinal Safety Analysis Report. has not been created.

3. The margin of safety as defined in the bases of the Technical Specifi-cations has not been decreased since no Technical Specifications areinvolved.

PROCEDURE CHANGES

Operatin Procedure 1630024 Refuelin Machine

A temporary change was made to this procedure to allow extensive adjust-ments to be made to the refueling machine. This involved a fuel assemblystuck in the refueling machine approximately 20 inches from lowest exten-sion. The changes involved the use of a temporary elevator to ungrappleand lower the fuel assembly to the upender cavity bottom and then loadtest following the repairs. Repairs were made to the refueling machinebut retest prior to use was not possible because the test weight was inthe spent fuel pool. The fuel assembly was carefully raised to removethe temporary lifting unit and then lowered into the unender cavity. Itwas then transferred to the spent fuel pool. The test weight was trans-ferred to the refueling cavity and the refueling machine was subsequentlytested satisfactorily. This evolution did not increase the consequenceof the analyzed fuel assembly drop. Neither did it create a new accidentor affect the margins specified in the Technical Specifications. Detailedprocedure and close supervision of the evolution reduced the probabilityof a fue'1 assembly being dropped. This temporary change did not involvean unreviewed safety question.

0 eratin Procedure 0540021 Boric Acid Concentrator 0 eration

The change involved adding a step to the procedure which allowed pumoingconcentrator condensate directly to the Primary Water Tank (PWT) ratherthan the Boric Acid Condensate Tank and then to the PWT. Relief valveleakage to the quench tank had resulted in using large volumes of waterfrom the PWT to cool the quench tank. Oxygen absorbed by the water inthe Boric Acid Condensate Tanks would eventually end up in the quenchtank and result in a potentially explosive mixture of hydrogen which isnormally present in the quench tank. Pumping directly to the PWT elimi-nated the oxygen absorption problem. This change did not cause potentialfor a new accident nor increase the severity of any analyzed accident.If boric acid reached the PWT it would not affect system materials. Ifit eventually reached the RCS it would add negative reactivity which isconservative. No Technical Specification margins were effected by thischange. The change did not involve an unreviewed safety question. Thechange was incorporated on a temporary basis while pursuing repairs tothe relief valves which were subsequently accomplished.

CORE BARREL MOVEMENT

Section 4.4.11.3 of PSL gl Technical Specifications requiresthe results of all periodic Amplitude Probability Distribu-tions (APD) and Spectral Analysis (SA) Monitoring to be in-

, cluded in this report.

Routine monitoring in 1979 included weekly APD processingand SA processing which was done in March, June, and October.SA measurements in June included analysis at nominal thermalpower levels of 20fo, 50fo, 80fo, and '100fo at the beginning offuel cycle 3. At no time during the year were the alert oraction levels exceeded.

As previously observed and reported in 1977 and 1978, the RMSlevels of all excore neutron detector signals showed a grad-ual increase throughout 1979 with the exception of a stepdecrease following refueling. This pattern was similar tothat observed in 1978 and was as expected.

The RMS levels at the end of 1979 over the frequency bandgenerally associated with core motion (0-10 Hz) provide anestimate of 2.I to 0.5 mils motion at core midplane as com-pared to 2. 3 to 3. 8 mils at the end of 1978. This slightincrease in level is not deemed. significant and the APDanalysis continues to confirm that the core barrel motionis normally distributed.

"STEAM GENERATOR TUBE INSPECTIONS"

An inservice eddy current examination of selected tubes in the No. 1A and1B St. Lucie Unit No. 1 Steam Generators was performed during the periodof May 9 through May 16, 1979, by C-E Power. Systems,'ystem IntegrityServices personnel. The inspection was conducted in accordance with C-ETest Procedures Nos. 00000-ESS-105, Revision 01 and 00000-ESS-070, Revision02, and satisfied the requirements of the St. Lucie Plant TechnicalSpecification 3/4 4-5 and the ASME Boiler and Pressure Vessel Code, SectionXI, 1974 Edition through the Summer 1976 Addenda.

The inspection program consisted of 400KHz testing for the detection oftube wall anomalies and the assessment of tube denting with both data beingtaken simultaneously with one pass of the eddy current probe through thetube. Included in the test pattern for dent and defect detection wastesting of 100% of the peripheral tubes which pass through the Number 9

and 10 drilled support plates. This test was carried out to ascertain ifany damage had occurred during flame cutting of the support plates'naddition, 25KHz testing for sludge accumulation on the secondary side ofthe hot side tube sheets was carried out. Selection of tubes to beexamined was based on an evaluation of where, in the tube bundle, problemshad occurred in other steam generators in service. Additionally, whenrequested by the Data Analyst, certain tubes were re-examined at 200KHz forconfirmation of tne 400KHz data.

The data from the inspection was recorded on magnetic tape and also on a four-channel strip chart recorder with the first two channels recording flaw dataand the second two channels recording dent data. These recordings wereevaluated by the data analyst and the results recorded on Eddy CurrentExamination Report Sheets.

Approximately ten percent of the tubes in both the 1A. and 1B steam Generatorswere inspected from the Hot Side, over the "U" bend, and part way down theCold Leg Side past the Numbers 9 and 10 Drilled Support Plates. By use ofspecially adapted electronic circuitry both dent and defect data weretaken simultaneously with one pass of the Eddy Current Probe. A summary ofthe numbers and magnitude of dents is included in Table I.

Analysis of the data indicated no detectable progression of service induceddenting when comparing the data taken during this inspection period withthat taken during the November 1978 Dent Assessment Examination.

Two tubes in the No. 1B Steam Generator were found to have one hundred percentthrough wall defects. These tubes, identified as Line 21 Row 91 and Line 110Row 134, are outer peripheral tubes which had incurred damage during the flamecutting of the rim of the Drilled Support Plates on the Secondary Side of thesteam generator prior to the Eddy Current Examination. Both of the tubes weresubsequently plugged.

In addition to the dent and defect data, sludge measurements were takenindicating a maximum of 5.6" in the 1A generator and 6" in the 1B generatoron the Hot Side Tube Sheet.

TABLE I

SENARY OP EDDY CURRENT TEST RESULTS INSPECTION CONDUCTED HAY 1979

Total No. of Tubes (By design)Tubes thru partial support Plate No. 9Tubes thru partial support plate No. 10

Tubes Examined

Notside tubes thru partial support No. 9

85192225 (26.1%)

771 (9.1%)

S/G No. Tubes Examined

800

Notes: 1) No tubes inspected from cold side2) Total tube count exceeds that of

support plate region because all tubes testeddo not pass thru support plates.

% of Total

35.9% No Tube Wall Degradation Indications

1B 799 35.9% No Tube Wall Degradation 'Indications

Coldside tubes thru partial support No. 9 800 35.9% No Tube Wall Degradation Indications

1B 799 35.9% No Tube Wall Degradation Indications

Notside tubes thru partial support No. 10 380 49.3% No Tube Mall Degradation Indications

1B 379 49.3% No Tube Mall Degradation Indications

Coldside tubes thru partial support No. 10 1A 380 49. 3% No Tube Wall Degradation Indications

Total tubes inspected from hot side

Notside sludge measurement

1B

lB

379

894

900

62




.73% Hax 5.6 inches

lB 62 .73% Hax 6.0 inches

TABLE I (cont)DENT ASSESSMENT RESULTS MAY 1979

S/G SupportPlate No.

Side No. TubesInspected

PercentOccurrence

Xmils

D

mils

HotCold

800800

11.50.6

1. 211. 68

0. 190.02

10 HotCold

380380

32. 97.6

l.962. 10

0. 760.22

1B HotCold

799799

18. 7

4.21.601.64

0.360.10

10 HotCold

379379

46. 227. 2

2. 472. 20

1.280.70

Notes:

1) All tubes inspected from Hot side.

2) X value is the average dent size for observed dents (9 not included)

3) D value includes the 9 dent tubes and add a statistical error correspondingto a 95% confidence level to provide a conservative assessment on tubecondition at the support plates.

ST. LUCI ~ T UNIT 81

APPENDIX BSTANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION

Yun>bcr ot I'crsonncl (> 100 n>rcm) Total Klan.Rem

'IV»rk k. Jol> I>unction

ltcactor Operations E. SurveillanceM;>intcn:u>cc PcrsunnclOpcratill" PersonnelIl«al(h I'hysics I'crsonnclSupervisory I'crsonnclL>noh)«crn>" I «rsol11'>cl

l<ou tinc!>Iain tcnancc1>laintcnan<v PersonnelOpcraliii" Personnelllcalth Physics Pcrsonn«lSu p 'rvisory I'crsonnclI!opine«riot: Personnel

Inscrvice Inspection>>Iallltcnancc I cfsa>unctOpcratlllp I crsullltclI lcalth I'hy>i«s I'crsunnelSupcrvi>ory Personnellan"inccrint; Personnel

Special hIaintcnanccMi>intcnauc« I'crsonnclOpcral lll"I clsonncIlie>>1th Phys>«s P«rsonnclSupcn'i>orI I'crsunnclL>n dnccrin ~ Personnel

4'aste Processing «

!>Iaintcnancc I'crsonnctOp«rat int; Personnelll«alth I'hysics Pcr>onnclSup'rvisory I'crsonncIIin in«crine Pcr>onncl

ItctuctingMaintc>rance I'crsonnclOI>erat>lip Pcrsoln>clllcali!iI'hysics I'«rsonnclSupervisory P«rsonn«lLnplnccrlng I cfsunncl

TOTALNtalntcnancc PcrsoilllclOp«mting Pcr>onnclI leal th Physics Pcr>onnclSilp«fvisofy I crsonncilingin««rinp I crsonncl

Grand Total

Station I:mptoyccs

-0-32

6-0--0-83-0-

-0--0--0-

4-0--0--0--0-

4-0--0-12

87-0-

-0-512410

83

102511011

3177

Utility I'.mployecs

-0--0--0--0--0-

3

-0--0--0--0--0--0--0--0--0--0--0--0--0-24-0--0-

31

24-0--0-

3

28

Contract Workersand Others

-0--0-

2-0--0--0--0-

33-0-63

-0-36-0-

422

-0--0-

2-0--0-

134-0-42-0--0-

203-0-55

5

265

Station Lmptoyccs

-0-17. 03l. 35

-0--0-28.87-0-

7:98-0--0--0-0.80-0-

-0--0--0-

2.15-0--0-

6. 753.751.87

-0--0-65. 369.516.026.870.85

100.9830.2915.098.07

155.28

UtilityI."mptoyccs

-0--0--0--0-l.11

-0-

-0--0--0--0--0--0--0--0--0-

-0--0--0--0--0-15. 37-0-0.660.14

16.48-0--0-

.6)17. 28

Contract Iyorkcrsand Others

-0--0-0.30

-0--0--0--0-

$.92

-0-24. 93-0-1.331.34

-0-13. 21-0-0.671.322.90

-0--0-1.42-0-

-0-84.54-0-23.36-0--0-

122.68-0-29.00

157. 2

Man rove Surve

This information is submitted in accordance with St. Lucie Unit 1Technical Specification 4.7.6.1.2.

A comparison of the December, 1975 aerial photograph FS-8770-310 withthe December, 1979 aerial false color infrared photo indicates nonatural or man-made deterioration of the mangroves. There continues tobe indication of additional plant growth in the area, which would tendto provide flood protection at or greater than the design criteria level.

On-site inspection has confirmed the above.

The aerial photos are available for review in our documentary controlfacilities at the plant site.

W

~ a

I

nrc: ml17208a420 - nrc.gov

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