ML17222A764

From kanterella
Jump to navigation Jump to search
Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facility.Printout of TMI Items Annotated Where Tracking Sys Indicates That Implementation incomplete,encl.Mark-up of Encl Requested
ML17222A764
Person / Time
Site: Saint Lucie  
Issue date: 04/14/1989
From: Murley T
Office of Nuclear Reactor Regulation
To: Conway W
FLORIDA POWER & LIGHT CO.
References
TASK-***, TASK-TM NUDOCS 8904240272
Download: ML17222A764 (21)
v • d • e


Text

t UNITED STATES t

NUCLEAR R EG ULATORY COMMISSION WASHINGTON, O. C. 20555 April 14, 1989 Docket Nos. 50-335 and 50-389 Mr. W. F.

Conway Senior Vfce President-Nuclear Nuclear Energy Department Florida Power and Light Company Post Office Box 14000 Juno Beach, Florida 33408-0420 Gentlemen:

The purpose of this letter is to request your prompt review and reporting of the status of implementation of TMI Action Plan Items at your facility.

As an enclosure we are providing a printout of all TMI items annotated where our tracking system indicates that implementation fs not complete.

For the purpose of this request, implementation should be considered complete when, to the best of your knowledge, all actions necessary to satisfactorily meet the requirements of NUREG-0737 and NUREG-0737 Supplement 1 have been completed.

Where you have not fully completed an item as described

above, we request that you mark-up the enclosure to reflect your projected implementation date.

Add a short note identifying remaining work (e.g.,

hardware, procedures,
training, technical specifications).

More explicit instructfons are provided as part of the enclosure.

We request that this information reach this office by April 18, 1989.

The information we are requesting will be utilized to validate our existing data base so that we can accurately respond to congressional inquiries concerning the status of implementation of TMI Action Plan Items.

In view

'f the importance of the information, we request your personal attention and certification that the information is correct to the best of your knowledge.

This request is covered by Office of Management and Budget Clearance Number 3150-0011, which expires December 31, 1989.

The estimated average burden hours fs 40 person hours per owner response, including searching data sources, gathering and analyzing the data, and preparfng the required letter.

Send coments regarding this burden estimate or any other aspect of this collection of information. including suggestions for reducing thfs burden, to the Records and Reports Management Branch, Division of Informatfon Support Services, Office of Informatfon Resources Management, U.S. Nuclear Regulatory Coamissfon, Washington, D.C.

20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C.

20503.

Nr.

W. F.

Conway April 14, 1989 Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely,

/s/

Enclosure:

As stated cc w/enclosure:

See next page Thomas E. thurley, Director Office of Nuclear Reactor Regulation DISTRIBUTION ~

(~7

-NRC 8 Local PDRs PDI I-2 Reading TMurley/JSniezek JPartlow SVarga GLainas HBerkow DNille r JNorris OGC (info only)

EJordan BGrimes ACRS(10) 8Wi1son

P I 2 Nor

.bd 0( /

D:

II-HBerkow 04 89 D.

R urley 04jg/89

v<

J 0

) /H

'1

~

a II N

II L,

g N

H l

'J

Yr. W. F.

Conway Florida Power

& Light Company St. Lucie Plant CC:

Mr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.

NRC 7585 S.

Hwy A1A Jensen Beach, Florida 34957 State Planning

& Development Clearinghouse Office of Planning

& Budget Executive Office of the Governor The Capitol Building Tallahassee, F lorida 32301 Harold F. Reis, Esq.

Newman

& Holtzinger 1615 L Street, N.M.

Mashington, DC 20036 John T. Butler, Esq.

Steel, Hector and Davis 4000 Southeast Financial Center t1i ami, Florida 33131-2398 Adminis trator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Store Road Ta 1 lahassee, Florida 32301 Yr. Weldon B. Lewis, County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 Hr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockv i lie, Maryland 20852 I

Hr. Jacob Daniel Nash Office of Radiation Control Department of Health and Rehabi litati ve Serv ices 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700-Regional Administrator, Region.II U.S. Nuclear Regulatory Conmission 101 Na riet ta St r eet N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Campbell Rich 4626 S.E. Pilot Avenue Stuart, Flori da 34997

GUIDELINES FOR UPOAT1 fl STATUS Si L 1.

The enclosure provides a coiplete listing of a'll llfI requfrelents free NUREG-0737 and HUREG-0737 Supplelent 1.

Regulatory Gufde 1.g7 requiem.nts, although addressed 1n Supplesant 1 to NURE6-0737, are excluded since they dfd not orfg1nate froa the 90 Action Plan.

This lfst1ng cons1sts of a slatrfX Of fteaS aPPlicable to both operating reactors and operating license applicants (KTOI.S) as of November,

1980, as sho>>n 1n NUREG737 Enclosure 1 and 2, respectively.

All items>>hich are not listed identically fn Enclosure 1 and 2 are aarked with aster1sks to indicate differences bet>>een operat1ng reactor and XTOI. requfreaents.

Whenever these differences occur, enter data fn accordance>>fth the appropriate title, regardless of the TNI Act1on Plan ftea nulber 11sted.

Your NRC Pro]ect Manager has 1nd1cated>>hfch 1ssues are sham as unfaplcaented 1n the NRC tracking systca.

Please revfe>> the ent1re lfst1ng for each licensed reactor unit.

Mhere an ftea was not applicable for your facility, aerk N/A fn the fsjpleeentatfon status colum.

2.

Nhere an fteI >>as applicable to your facility but no changes>>ere necessary, act k NC 1n the fepleawntatfon status coluen.

3.

Qhere an ftea>>as applicable to your facility and changes are canplete sark C fn the 1lplelentatfon status coluejn. lf the date fs readily available (Nonth and year)>>e request you provide ft, ho>>aver, C is suff1 c1ent.

i.

Nhere an itea>>as applicable to your facility and 1s not fully fiplemented, provide your pro)<<cted fapleaentatfon date (aonth and year ) and a short note 1dentffying the outstanding ftea (e.g. hard>>are, procedures, training, techn1cal specff1catfons).

HULTI-PLANT ISSUL NUHBER ACTIOH NO.

ISSUE TITLE LICENSEE III'lOKNTATIONSTATUS F001 F002 F002 F003 F004 F004 F005 F005 F006 F007 FOOD C F071)

F009 l. A. l. l. I I. A. I. l. 2 "I. A. l. 1. 3 A I ~ A. I ~ 1.4 I.A. 1.2 l.A. l. 3. I I. A. 1. 3. 2 I. A. 2. l. 1 l.A.2.1.2 I.A. 2. 1. 3 I. A.2. l. 4 I. A. 2. I. 5 I.A.2.3 I,A.3.1.1 I.A. 3. 1. 2 I.A.3. 1.3.A I. A. 3. I. 3. 8

'l U. 1.2 I

C. I. I I.C.1.2.A I.C. 1.2.8 I.C. 1.3.A I.C.1.3.8 I.C.2 I.C.3 I.C.4 I.C.5 I.C.G

. C. 1. I "I.C.1.2

'I C.8

'..U. I (See I.U.2. I

~ ~ ~ ~ ~ ~ 0 ~ ~

~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Vt

~ ~ ~ ~ ~

I; 'e':

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

QIIFT TECHNICAL ADVISOR - OH DUTY.

SHIFT TECHHICAL ADVISOR - TECH SPECS....................................................

SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT 8.

SHIFT TECHNICAL ADVISOR - DESCRIBE LOHG TERH PROGRAH.

SHIFT SUPERVISOR RESPOHSIBILITIES.

SHIFT NANNIHG - LIHIT OVERTIHES..

. SHIFT SONING - HIN SHIFT CREM.

IltlEOIATE UPGRADIHG OF RO 4 SRO TRAIHIHG AHD QUAL. -

SRO EXPER.

ISlEDIATE UPGRADING OF RO 8 SRO TRAIHIHG AHD QUAL. - SRO'S BE RO'S lYR.

IISEDIATE UPGRADING OF RO 8 SRO TRAIHING AND QUAL. - 3 HO.

TRAINING.

IHHEDIATE UPGRADING OF RO 8 SRO TRAINING ANO QUAL. - HOOIFY TRAINING..................

IHHEDIATE UPGRADING OF RO 8 SRO TRAINING AND QUAL. - FACILITY CERTIF ADHIHISTRATION OF TRAIHIHG PROGRAHS

~ ~ ~ ~

~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~

~ ~ ~ ~ ~

~ ~ ~ ~

~

~

'EVISE SCOPE 4 CRITERIA FOR LICEHSIHG EXAHS -

INCREASE SCOPE.

REVISE SCOPE 4 CRITERIA FOR LICEHSIHG EXAHS -

INCREASE PASSIHG GRADE

~ ~

REVISE SCOPE 5 CRIT.

FOR LIC. EXAHS - SINJLATOR PLANTS MITH SIHULATORS.

~ ~

REVISE SCOPE 8 CRIT.

FOR LIC. EXAHS - SIHULATOR - OTHER PLANTS..

EVALUATIOH OF ORGANIZATION 4 HANAGEHENT

~

~ ~

~ ~ ~

~

~

~

SHORT'-TERH ACCIDENT 4 PROCEDURES REVIEW - SB LOCA.

SHORT-TERN ACCID.

Ia PROCEDURES REV. - INADEQ.

CORE COOL.

REANAL. GUIDELINES SHORT-TERN ACCID. 5 PROCEDURES REV. - IHADEQ.

CORE COOL.

REVISE PROCEDURES.

SHORT'-TERH ACCID. 4 PROCEDURES REV - TRANSIENTS 6 ACCOTS.

REAHAL GUIDELINES (PROC.

GEN. PKG.).

SHORT TERH ACCID. 4 PROCEDURES REV. - TRANSIENTS 8 ACCORS.

REVISE PROCEDURES (UPGRADED EOP'S)

SHIFT 4 RELIEF TURHOVER PROCEDURES..

SHIFT-SUPERVISOR RESPONSIBILITY.................... ~.....

~.""-"""" ~". ~ ~ ~ ~ ~ ~

~ ~ ~

~

~

COHTROL ROOH ACCESS

~ ~

~

~

~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

FEEDBACK OF OPERATIHG EXPERIENCE.

VERIFY CORRECT PERFORHANCE OF OPERATIHG ACTIVITIES

~ ~". ~ ~

~

NSSS VENDOR REV.

OF PROC - LN PNER TEST PROGRAH.

NSSS VEHDOR REV.

OF PROC - POVER ASCEHSION 6 EHER.

PROCS.

~ ~ ~

~

~

~

~

~ ~

~

PILOT HON OF SELECTED EHERGEHCY PROC FOR HTOLS.

~ ~

~ \\ ~ ~

~

~

~

CONTROL-ROON DESIGH REVIEWS (EHTER DATA FOR HPA f008 8 HPA F-071).

PLANT-SAFETY PARAHETER DISPLAY CONSOLE - DESCRIPIION.

~ ~

~ ~ ~ ~

~

HULTI-PLANT l SSUE HUHBER ACTION NO.

ISSUE TITLE LICEHSEE IHPLEHEHTATION STATUS I.D.2.2 I.0.2.3 "l.G. 1. 1

<<I.G. 1. 2

<<I.G. 1. 3 II. B. 1. 1 Il.8.1.2 I I.B. 1. 3 II.B.2.1

<< II. 8. 2. 2

<< II. 8.2. 3 "ll.8.2.4 "11.8.3.1

<<ll.8.3.2

<<ll.8.3.3

  • II.8.3.4 II. 8.4. 1 "ll.8.4.2.A

<<Il.8.4.2.8 Il.0.1.1 "Il.0.1.2.A

  • II 0 1 2 8 II.D.1.3

<<II.D.3.1

<<II.D.3.2

<< II. E. 1. 1. 1 (SEE NOTE 1)

<<II.E.1.1.2 (SEE NOTE 2)

II.E.1.1.3 (SEE NOTE 3)

F009 F009 F010 F010 F011 F012 F013 F013 F013 F014 f015 F015 F015

'PLANT-SAFETY PARAHETER DISPLAY CONSOLE - INSTALLED.

PUNT-SAFETY PARAHETER DISPLAY CONSOLE - FULLY IHPLEHENTEO.

TRAINING DURING LOW-POWER TESTIHG - PROPOSE TESTS TRAINIHG OURIHG LOW-POWER TESTING - SUBHIT ANAL. 5 PROCS.

TRAIHIHG DURING LOW-POWER TESTING - TRAINING & RESULTS..

REACTOR-COOLANT SYSTEH VENTS - DESIGN VENTS..

REACTOR-COOLANT SYSTEH VEHTS - IHSTALL VENTS (LL CAT 8).

REACTOR-COOLANT SYSTEH VEHTS - PROCEDURES PLANT SHIELDING - REVIEW DESIGNS...

PUNT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS.

PLANT SHIELDING - PLANT HODIFICATIONS (LL CAT 8).

PLANT SHIELDING - EQUIPHEHT QUALIFICATION-NOT TRACKED AS A THI ACTIOH ITEN.

POSTACCIDEHT SAHPLIHG - INTERIH SYSTEH.

POSTACCIDENT SAHPLING - CORRECTIVE ACTIONS..

POSTACCIOENT SAHPLING - PROCEDURES.

POSTACCIDEHT SAHPLING - PLANT HODIFICATIONS (LL CAT 8).

TRAIHING FOR HITIGATIHG CORE DANAGE - DEVELOP TRAINING PROGRAH.

TRAIHIHG FOR HITIGATING CORE OAHAGE - INITIAL TRAINIHG FOR HITIGATING CORE DAHAGE - COHPLETE.

RELIEF 5 SAFETY VALVE TEST REQUIREHEHTS - SUBHIT PROGRAH.

RELIEF 4 SAFETY VALVE TEST REQUIREHENTS - COHPLETE TESTING.

RELIEF 4 SAFETY VALVE TEST REQUIREHEHTS - PLANT SPECIFIC REPORT.

RELIEF 4 SAFETY VAVLE TEST REQUIREHENTS - BLOCK-VALVE TESTING.

VALVE POSITIOH INDICATION - INSTALL DIRECT IHOICATIONS OF VALVE POS...

VALVE POSTION INDICATIOH - TECH SPECS.

AFS EVALUATIOH-ANALYSIS AFS EVALUATION-SHORt TERH NODS AFS -LONG TERH NODS.

NOTE 1 - THE ITEH LISTED 15 FROH NUREG-0737, EHCLOSURE 2 AND IS APPLICABLE TO NTOLS'5 ONLY NOTE'2 -

THE ITEH LISTED 15 FOR ALL PLAHTS (OPERATING REACTORS AND HTOL'5)

NOTE 3 -

THE ITEH LISTED IS FOR ALL PLANTS (OPERATIHG REACTORS AND NTOL'5)

HULTI-PLANT ISSUE NUNBER ACTION HO.

ISSUE TITLE LICENSEE IHPLEHENTATIOH STATUS II. E. 1.2. 1.A I I. E. 1.2. 1.8 I I. E. 1.2.2.A

<<I I. E. 1.2.2.8

<<I I.E.1.2.2.C

<<II E 3 1

1

<<I I. E.3.1.2 I I. E.4.1.1

<< I I. E.4. 1. 2

<<I I. E.4. 1. 3 II.E.4.2.1-4

<<I I.E.4.2.5.A "II E.4.2.5.8 I I. E.4. 2. 6 I I. E.4. 2. 7 "II. E.4.2.8

<< I I. F. l. 1

<< I I. F. l. 2. A

<<I I. F. 1.2.8

<<II.F.1.2.C

<<l I. F. 1.2.0

<<I I. F.1.2. E

<<II F.l.2.F

<< I I. F.2. 1

  • I I. F. 2. 2

<<I I.F.2. 3

<< I I. F. 2.4

<< I I.G. l. 1

<<II G 1 2 I I.K.I (Oper.

F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 F024 F025 F026 F026 Reactors Only)

AFS INITIATIOH6 FLOW-CONTROL GRADE.

AFS INITIATIOH8 FLOW - SAFETY GRADE.

AFS INITIATIOH8 FLOW - FLOW INDICATIOH COHTROL GRADE AFS IHITIATION6 FLOW - LL CAT A TECH SPECS................................

AFS INITIAT10N 6 FLOW - SAFETY GRADE EHERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY.

EHERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS.

DEDICATED HYDROGEN PEHETRATIONS - OESIGH.

DEDICATED NYOROGEH PEHETRATIOHS - REVIE'W 4 REVISE H2 CONTROL PROC...

DEDICATED HYDROGEH PENETRATION - INSTALL.

CONTAIHHENT ISOLATIOH DEPENDABILITY - IHP.

DIVERSE ISOLATIOH.

COHTAINHENT ISOLAT. DEPENDABILITY - CNTHT PRESS.

SETPT.

SEECIFIY PRESS CONTAINHEHT ISOLATION DEPENDABILITY-CNTHT PRESSURE SETPT.

NODS.

COHTAINHENT ISOLATION DEPEHDABILITY-CNTHT PURGE VALVES CONTAIHHENT ISOLATION DEPENDABILITY-RADIATION SIGNAL ON PURGE VALVES..

CONTAIHHENT ISOLATION OEPENDABLITY - TECH SPECS.

ACCIDENT - HOHITORIHG - PROCEDURES ACCIOEHT - NNITORIHG - NOBLE GAS HONITOR.

ACCIDENT - N)HITORIHG - IODINE/PARTICULATE SAHPLING.

ACCIDENT - NHITORING - CONTAINHEHT HIGH-RANGE NONITOR.

ACCIOEHT HOHITORING - CONTAINHEHT PRESSURE ACCIDENT - HONITORIHG - CONTAINHEHT 'WATER LEVEL ACCIDENT - NONITORIHG - CONTAINNEHT HYDROGEN.

INSTRUNEHTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

PROCEDURES INSTRUHEHTATIOH FOR DETECT.

OF INADEQUATE CORE COOLING - SUBCOOL HETER.

IHSTRUHEHTATION FOR DETECT.

OF INADEQUATE CORE COOLING - DESC.

OTHER.

IHSTRUHEHTATIOH FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD' IHSTRUHENTATION.

POWER SUPP.

FOR PRESSURIZER RELIEF, BLOCK VALVES 4 LEVEL IND. - UPGRADE POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 6 LEVEL IND. - TECH SP IE BULLETINS 05, 79-06, 79-08.

~

~

~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

~ ~ ~

~ ~ ~

~

NULTI-PLANT ISSUE NUHBER ACTION HO.

ISSUE TITLE LICENSEE INPLENEHTATIDN STATUS

<<II.K.1.5

<<II.K.1.10

<<II.K.1.20

<< I I. K. 1. 21

<< I I. K. 1. 22

<< II. K. 1. 23

<<I I. K.2.2

<<II.K.2.8 II.K.2.9 II.K.2.10

<< I I. K.2. 11 I I. K. 2. 13 I I. K. 2. 14 I. K. 2. 15 I I. K.2. 16 F032 I I. K. 2. 17 F033 II.K.2.19

<< I I. K. 2. 20 F035

<< I I. K. 3. 1. A F036

" I I. K. 3. 1. 8 I I. K. 3. 2 F037 I I. K. 3. 3 F038 II.K.3.5.A F039 I I. K. 3. 5. 8 F039 I I. K. 3. 7 I I. K. 3. 9 F040 I I. K. 3. 10 F041 II.K.3.11 II.K.3.12.A I I. K. 3. 12. 8 F042 I I. K. 3. 13. A F043 I l. K. 3. 13. 8 F043

'IE BULLETIHS " REVIEW ESF VALVES......:..

IE BULLETINS - OPERABILITY STATUS.

IE BULLETIHS - PROHPT HANUAL REACTOR TRIP IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP IE BULLETINS - AUX. HEAT REH SYSTEN, PROC IE BULLETINS - RV LEVEL, PROCEDURES..........................

~..............

ORDERS ON 8&W PLANTS - PROCEDURES TO CONTROL AFW IHD OF ICS ORDERS OH 8&W PLANTS - UPGRADE AFW SYSTEM.

ORDERS ON 8&W PlANTS - FEHA OH ICS.....................................................

ORDERS OH 8&W PLANTS - SAFETY-GRADE TRIP ORDERS ON MW PLANTS - OPERATOR TRAINING.

ORDERS OH 8&W PLANTS - TNERHAL HECHAHICAL REPORT (CE & 'W PLANTS ALSO).

ORDERS OH 8&W PLANTS - LIFT FREQUENCY OF PORV'S & SV's.

ORDERS OH 8&W PLANTS - EFFECTS OF SLUG FLOW.

ORDERS ON 8&W PLANTS -

RCP SEAL DAHAGE.

ORDERS OH 8&W PLANTS - VOIDING IN RCS (CE & W PLANTS ALSO).

BENCNARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STH GENERATOR.

ORDERS ON 8&W PLANTS - SYSTEH RESPONSE TO SB LOCA.

8&0 TASK FORCE - AUTOHATIC PORV ISOLATION DESIGN.

FINAL RECOISENDATIONS, 8&0 TASK FORCE - AUTO PORV ISO TEST/INSTALL 8&0 TASK FORCE - REPORT ON PORV FAILURES.

8&0 TASK FORCE - REPORTING SV & RV FAILURES AND CHALLENGES..........

8&0 TASK FORCE - AUTO TRIP OF RCP'S PROPOSED HODIFICATIONS.

8&0 TASK FORCE - AUTO TRIP OF RCP'S NODIFICATIONS.

8&0 TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES..

8&0 TASK FORCE - PID CONTROLLER NODIFICATION.

8&0 TASK FORCE - PROPOSEO ANTICIPATORY TRIP NODIFICATIONS.

8&0 TASK FORCE - JUSTIFY USE OF CERTAIH PORV.

8&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED N)DS.....

8&0 TASK FORCE - ANTICIPATORY TRIP OH TURBINE TRIP INSTALL NODS.

8&0 TASK FORCE - HPCI & RCIC SYSTEH IHITIATION LEVELS ANALYSIS 8&0 TASK FORCE - HPCI & RCIC INITIATION LEVELS NODIFICATION.

HULTI-PLANT ISSUE NUHBER ACTIOH HO.

ISSUE TITLE LICENSEE IHPLEHENTATIOH STATUS

  • II.K.3.14 II. K. 3. 15 I I. K. 3. 16A I I. K. 3. 16. 8 I I.K.3.17 I I. K.3. IB.A I I. K. 3. 18. 8 II. K. 3. 18. C "II.K.3. 19 iI I. K. 3. 20 I I. K. 3.21.A I I. K. 3. 21.8 I I. K. 3. 22. A II.K.3.22.8 II.K.3.24 II.K.3.25.A II.K.3.25.8 II.K.3.27 II.K.3.28 "II.K.3. 29 II.K.3.30.A I I. K.3. 30. 8 I I. K. 3. 30. C

' I. K. 3. 31

  • II. K. 3. 40 iI I. K. 3.43 I I. K. 3.44 II.K.3.45 I I.K.3.46 aII K 3 I I I.A. 1. 1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 SLO TASK BM TASK BM TASK BM TASK 8&0 TASK 8&0 TASK BM TASK BM TASK BM TASK BLO TASK BM TASK BM TASK 8&0 TASK 8&0 TASK BM TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK BLO TASK 8&0 TASK 8&0 TASK 8&0 TASK BLO TASK 8&0 TASK 8&0 TASK-8&0 TASK 8&0 TASK

RESPONSE

IDENTIFY EHERGENCY FORCE - ISO CONDENSER ISOLATION ON HIGH RAD.

FORCE - HODIFY HPCI & RCIC BRK DETECTION CIRCUITRY.

FORCE - CNLLENGE & FAILURE OF RELIEF VALVES STUDY.

FORCE - CNLLENGE & FAILURE OF RELIEF VALVES HODIFICATIONS.

FORCE - ECC SYSTEH OUTAGES.........................................................................

FORCE - ADS ACTUATION STUDY.

FORCE - ADS ACTUATION PROPOSEO HODIFICATIONS.

FORCE - ADS ACTUATIOH HODIFICATIONS.

FORCE - IHTERLOCK RECIRCULATORY PUHP HODIFICATIONS.

FORCE - LOSS OF SVC MATER AT BRP FORCE - RESTART OF CSS & LPCI LOGIC DESIGN.

FORCE - RESTART OF CSS & LPCI LOGIC DESIGN HODIFICATIONS.

FORCE - RCIC SUCTION VERIFICATION PROCEDURES.

FORCE - RCIC SUCTION HODIFICATION.

FORCE - SPACE COOLING FOR NPCI/RCI LOSS OF AC POWER.............

FORCE - POMER ON PUHP SEALS PROPOSED MODIFICATIONS.

FORCE - POWER OH PUHP SEALS HDDIFICATIONS.

FORCE - COSIGN REFERENCE LEVEL FOR BWRS.

FORCE - QUALIFICATIONOF ADS ACCUHULATORS..

FORCE - PERFORHANCE OF ISOLATION CONDENSERS.

FORCE - SCHEDULE FOR OUTLINE OF SB LOCA HODEL.

FORCE - SB LOCA HODEL, JUSTIFICATION.

FORCE - SB LOCA HETHODS NEM ANALYSES.

FORCE - COHPLIANCE WITH CFR 50.46.

FORCE -

RCP SEAL DAHAGE - COVERED BY II.K.2.16 AND II.K.3.25.

FORCE - EFFECTS OF SLUG FLOW - COVERED BY II.K.2.15.

FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE.

FORCE " ANALYSES TO SUPPORT.

TO LIST OF CONCERNS FROH ACRS CONSULTANT.

WATER SOURCES PRIOR TO HANUAL ACTIVATION OF ADS.

PREPAREDNESS, SHORT TERN.

MJLTI-PLANT ISSUE NUHBER ACTIOH NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I I I.A. 1.2. 1 I II.A.1.2.2 (SEE F063, III.A.1.2.3 (SEE F063, I II.A.2. 1 I II.A.2. 2 AI I I.D. 1. 1. 1

  • III.D. 1. l. 2 I I I.D. 3. 3. 1 I I I.D. 3. 3. 2 111.0.3.4.1 "II I.D. 3.4. 2 AII 1.0. 3.4. 3 MPA-FOOB HPA-f063 MPA-F064 HPA-F065 MPA-F071 MPA-8072 MPA-B083 67.4. 1
F064, F065)
F064, F065)

F067 F068 F069 F070 F070 F008 F063 F064 F065 F071 8072 B083 G001 UPGRADE PREPAREDNESS - UPGRADE EMERGENCY PUNS TO APP.

E.

10 CFR 50.

UPGRADE PREPAREDNESS - HETEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE CONTAINHEHT - LEAK REDUCTION.

PRIHARY COOLANT OUTSIDE COHTAINMEHT - TECH SPECS.

INPLANT RAD. HONIT. - PROVIDE HEANS TO DETER.

PRESENCE OF RADIOIODINE.

INPLANT RADIATION MOHIT. - HODIFICATIOHS TO ACCURATELY HEAS.

IODINE.

COHTROL ROOM HABITABILITY-REVIE'N.

CONTROL ROOH HABITABILITY-SCHEDULE MODIFICATIONS.

CONTROL ROOH HABITABILITY-IMPLEHEHT HODIFICATIONS.

I.D.1.1 DETAILED CONTROL ROOH DESIGN REVIEH PROGRAH PLAN III.A.1.2 TECHHICAL SUPPORT CEHTER.

III.A.1.2 OPERATIONAL SUPPORT CENTER.

III.h. l. 2 EHERGENCY OPERATIONS FACILITY.

1.0.1.2 DETAILED CONTROL ROOM REVIEW (FOLLShJP TO F-B).

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 4 83-02).

TECH SPEC COVERED BY GENERIC LETTERS 83-26 6 83-37 FOR NUREG-0737.

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)

~

~ ~

~

~ ~

~

~

~

~

0 ~

~

~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~

~ ~

LB,'TB, ader.xH......<................

tJPGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC 8 EOF UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-IHCORP. INTO f063/F064/F065........................

UPGRADE EHER SUPPORT FACILITIES " HODS INCORPOR.

INTO F063, F064 4 F065.

GUIDELINES FOR UPOAT HI STATUS z.~ J 1.

The enclosure provides a complete 11stfng of all TNI requirements from KUREG-0737 and KUREG-0737 Supplement I.

Regulatory Guide 1,97 requf~nts, although addressed 1n Supplea>>nt I to NURE6-0737, are excluded s1nce they dfd not originate fata the TKI Action Plan.

This listing consists of a Natrfx of items applicable to both operating reactors aad operating license applicants (KTOLS) as of Koveaber,

1980, as shown fn KUREG<737 Enclosure I and 2, respectively.

All fteas which are not listed fdent1cally 1n Enclosure I and 2 are marked w1th asterisks to fnd1cate differences between operating reactor and XTOL requires>>nts.

Whenever these differences occur, enter data fn accordance with the appropriate t1tle, regardless of the TNI Action Plan 1 tesa nutbar listed.

Your KRC ProSect Kanager has 1ndfcated which 1ssues are shown as unfmplewented in the KRC tracking system.

Please review the ent1re 11stfng for each licensed reactor unit.

Where an item was not applicable for your fac111ty, mark K/A 1n the fmplee>>ntatfon status colum.

2.

Where an iten was applicabl ~ to your fac111ty but no changes were necessary, mark KC fn the fmplementatfon status column.

3.

Where an ftea was app11cable to your facility and changes are complete mark C 1n the fapiementatfon status column. If the date fs readily available (senth and year) we request you provide ft, however, C is suff1 c1ent.

Where an item was applfcable to your fac111ty and fs not fully fmp1ea>>nted, provide your pro)ected fap1es>>ntatfon date (anth and year) and a short note fdentffy1ng the outstanding ftea (e.g. hardware, procedures, training, technical spec1f fcatfons).

r

+L

HULTI-PLANT I SEOUL HUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEKHTATIOH STATUS I.A. 1. l. 1

. A. 1. 1. 2 "I A I 1 3

'. A. 1. 1. 4 l.h. 1.2 I.A.1.3.1 I. A. 1. 3. 2 I.A. 2. 1. 1 I.A.2. 1.2 I. A. 2. I. 3 I. A. 2. l. 4 I.A.2.1.5 I.A.2.3 I. A. 3. 1. 1 l.A.3.1.2 I.A. 3. 1.3.A I.A. 3. 1.3.8

'I 8.1.2 I

C. I. I I.C. 1.2.A I. C. I. 2. 8 I. C. 1. 3. A

!. C. 1. 3. 8 I.C.2 I.C.3 I.C.4 I,C.5 I.C.G A I. C. 7. I "I. C. l. 2

'I C.B

~, o. I (See I.U.2.1 F001 F002 F002 F003 F004 F004 F005 F005 F006 F007 FOOB t F071)

F009

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

6HIFT TECHHICAL ADVISOR - ON DUTY SHIFT TECfNICAL ADVISOR - TECH SPECS...............................................,......................,..........

SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT B.

SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERN PROGRAH.

SHIFT SUPERVISOR RESPONSIBILITIES......

SHIFT HAHHING'- LIHIT OVERTIHES SHIFT HAHNIHG - HIH SHIFT CREH.........

IWEOIATE UPGRADING OF RO 6 SRO TRAINING ANO gUAL. -

SRO EXPER.

IWEDIATE UPGRADIHG OF RO 6 SRO TRAIHIHG AHD EQUAL. - SRO'S BE RO'S 1YR.

IWEDIATE UPGRADIHG OF RO 6 SRO TRAIHING AND gUAL. - 3 NO.

TRAINING.

IWEDIATE UPGRADIHG OF RO 6 SRO TRAIHING AND EQUAL. - NODIFY TRAINIHG.

IWEOIATE UPGRADIHG OF RO 6 SRO TRAINING AND gUAL. - FACILITY CERTIF.

ADHIHISTRATION OF TRAINIHG PROGRAHS.

REVISE SCOPE 6 CRITERIA FOR LICEHSING EXAHS -

INCREASE SCOPE REVISE SCOPE 6 CRITERIA FOR LICEHSIHG EXAHS -

INCREASE PASSING GRADE REVISE SCOPE 6 CRIT.

FOR LIC.

EXAHS - SIHULATOR PLANTS ARITH SIHULATORS..

REVISE SCOPE 6 CRIT.

FOR LIC. EXAHS - SIHULATOR - OTHER PLANTS.

EVALUATION OF ORGANlZATIOH 6 HANAGEHENT.

SHORT-TERN ACCIDENT 6 PROCEDURES REVIEW - SB LOCA.

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

SHORT-TERN ACCID. 6 PROCEDURES REV. -

INADEPT.

CORE COOL.

REANAL. GUIDELINES....

SHORT-TERN ACCID. 6 PROCEDURES REV. -

INADEPT.

CORE COOL.

REVISE PROCEDURES......

SHORT-TERN ACCIO. 6 PROCEDURES REV - TRANSIENTS 6 ACCOTS.

REANAL GUIDELIHES (PROC.

GEH. PKG.).

SHORT-TERN ACCIO. 6 PROCEDURES REV. - TRANSIENTS 6 ACCDRS.

REVISE PROCEDURES (UPGRADED EOP'5)...""...""""-..-" "

SHIFT 6 RELIEF TURNOVER PROCEDURES..........................

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

SHIFT-SUPERVISOR RESPONSIBILITY.............. -....... -..

~ ~ ~

~

CONTROL-ROOH ACCESS

~..........................

~ ~."..--..

~ ~.- ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~

FEEDBACK OF OPERATING EXPERIEHCE.

.............. "..--...-" ~. ~.-

~ ~ ~

~ ~ ~

~ ~

~ ~

VERIFY CORRECT PERFORHANCE OF OPERATING ACTIVITIES.

HSSS VENDOR REV.

OF PROC - LN PNER TEST PROGRAH.

~

~ ~

~ ~

NSSS VENDOR REV.

OF PROC -

POVER ASCEHSION 6 EHER.

PROCS.

PILOT HOH OF SELECTED ENERGEHCY PROC FOR HTOLS.

~

-.. ~

CONTROL-ROON DESIGN REVIENS (ENTER DATA FOR HPA FOOD 6 HPA F-071).

PLANT-SAFETY PARAHETER DISPLAY CONSOLE - DESCRIPTION.

~ ~ ~

HULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TTTI.E LICENSEE IHPLEMENTATIOH STATUS 1.0.2.2 I.0.2.3 I.G. 1. 1

<<I.G.1.2

<<I.G.1.3 I I.B. 1. 1 Il.8.1.2 I I.B. 1. 3 I I.B. 2. 1

<<Il.8.2.2

<< I I.8.2. 3

<<II.B.2.4

<< I I.B. 3. 1

<<l1.8.3. 2

" II. B. 3. 3

<<I I. 8.3.4 I1.8.4. I

<<Il.8.4.2.A

<<11.8.4.2.8 I I. 0. 1. 1 "II D.1.2.A,,

<<ll.0.1.2.8 I I.D. 1. 3 "II.O. 3. 1

<<II 0.3.2

<<I I.E. 1. 1. 1 (SEE NOTE 1)

<<I I. E. 1. l. 2 (SEE HOTE 2)

I I. E. 1. 1. 3 (SEE NOTE 3)

F009 F009 F010 F010 F011 F012 F013 F013 F013 F014 F015 F015 F015

'PLANT-SAFETY PARAMETER DISPLAY CONSOLE - INSTALLED.

PUNT-SAFETY PARAMETER DISPLAY COHSOLE - FULLY IHPLEMEHTED.

TRAIHIHG DURING LOW-POWER TESTIHG - PROPOSE TESTS................................

TRAINIHG OURIHG LOW-POWER TESTING - SUBMIT ANAL. 8 PROCS.

TRAIHIHG DURING LOW-POWER TESTING - TRAINING 4 RESULTS.

REACTOR-COOLANT SYSTEH VENTS - OESIGH VEHTS..

REACTOR-COOLANT SYSTEM VENTS - INSTALL VEHTS (LL CAT 8)

REACTOR-COOLANT SYSTEH VENTS - PROCEDURES PLAHT SHIELDIHG - REVIEW DESIGNS.

PLAHT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS.

PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8).

PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A THI ACTIOH ITEH.

POSTACCIOEHT SAMPLING - INTERIM SYSTEH..............................................-...

~ ~ ~ ~..

POSTACCIDEHT SAMPLING - CORRECTIVE ACTIONS................................-.."..

~. ~ ~

POSTACCIDENT SAHPLING - PROCEDURES.

POSTACCIDEHT SAMPLING - PLAHT MODIFICATIONS (LL CAT 8).

.. ~

~ ~

TRAIHIHG FOR HITIGATING CORE DAMAGE - DEVELOP TRAIHING PROGRAM.

TRAIHING FOR MITIGATING CORE DAMAGE - INITIAL.

TRAINING FOR HITIGATING CORE DAMAGE - COMPLETE RELIEF 4 SAFETY VALVE TEST REQUIREMENTS - SUBHIT PROGRAM.

RELIEF 4 SAFETY VALVE TEST REQUIREMENTS - COMPLETE TESTING.

RELIEF 8 SAFETY VALVE TEST REQUIREMEHTS - PLANT SPECIFIC REPORT.

RELIEF 4 SAFETY VAVLE TEST REQUIREMEHTS - BLOCK-VALVE TESTING.

VALVE POSITION INDICATIOH - INSTALL DIRECT INDICATIONS OF VALVE POS................

VALVE POSTION INOICATIOH - TECH SPECS....................

~... ~..........

~ - ~."..-

~ ~ ~ ""--

~

- ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~

AFS EVALUATION-AHALYSIS...............--.-..--.--.. -..... ". ""... ".

.".... "."-. ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~"

AFS EVALUATION-SHORT TERH NODS AFS -LONG TERH NODS...

NOTE 1 -

THE ITEH LISTED IS FROH HUREG-0737, ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'5 ONLY NOTE 2 -

THE ITEH LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)

NOIE 3 - THE ITEM LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)

P HULTI-PLAHT ISSUE NUHBER ACTION HO.

ISSUE TITLE LICENSEE IHPLEHEHTATION STATUS I I. E. I. 2. 1. A II.E.1.2.1.8 Il. E.1.2.2.A

<<I I.E.1.2.2.8

  • II.E.1.2.2.C "ll.E.3.1.1 "II.E.3.1.2 I I.E.4.1.1 "l I. E. 4. l. 2

<<I I E.4.1.3 I I. E.4.2. 1-4

<<II E 4.2.5.A "Il. E.4.2.5.8 II.E.4.2.6 II.E.4.2.7

<<II E 4 2 8

<< I I. F. 1. I

<<II.F.1.2.A

<<I I.F.1.2.8 "II.F.1.2.C "ll.F.1.2.D

  • II F.1.2.E

<<II F.I.2.F

<< II.F.2. I "II.F. 2. 2

<< I I. F. 2. 3 "Il. F.2.4

<<ll G 1

1

<<II.G. 1.2 I I.K.I (Oper.

F016 F017 F018 F019 F019 F020 F020 F021 F022 F023 F024 F025 F026 F026 Reactors Only)

AFS IHITIATIOH6 FLOW-CONTROL GRADE.

AFS INITIATIOH4 FLOW - SAFETY GRADE.

AFS IHITIATIOH4 FLOW - FLOW INDICATION COHTROL GRADE.

AFS IHITIATIOH4 FLOW - LL CAT A TECH SPECS AFS IHITIATIOH4 FLOW - SAFETY GRADE.

EHERGEHCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY.

EHERGEHCY POWER FOR PRESSURIZER HEATERS - TECH SPECS.

DEDICATED HYDROGEN PEHETRATIOHS - DESIGN.

DEDICATED HYDROGEN PEHETRATIOHS - REVIEW 4 REVISE H2 COHTROL PROC.

DEDICATED HYDROGEN PENETRATION - INSTALL CONTAINHEHT ISOLATION DEPENDABILITY-IHP.

DIVERSE ISOLATION.

CONTAIHHENT ISOLAT. DEPENDABILITY-CNTHT PRESS.

SETPT.

SEECIFIY PRESS..

CONTAINHENT ISOLATION DEPENDABILITY-CNTHT PRESSURE SETPT.

NODS.

CONTAINHENT ISOLATION DEPENDABILITY-CNTHT PURGE VALVES CONTAINHENT ISOLATION DEPENDABILITY-RADIATION SIGNAL ON PURGE VALVES.......

CONTAINHENT ISOLATION OEPEHDABLITY - TECH SPECS.

ACCIDEHT - HOHITORING - PROCEDURES ACCIDEHT - HOHITORIHG - NOBLE GAS HOHITOR.

ACCIDENT - HOHITORING - IODINE/PARTICULATE SAHPLING.

ACCIOEHT - HONITORING - COHTAIHHENT NIGH-RANGE HONITOR.

ACCIDEHT - HONITORING - COHTAINHENT PRESSURE ACCIDENT - HOHITORING - COHTAINHENT WATER LEVEL.

ACCIDEHT - HOHITORING - CONTAIHHEHT HYDROGEN.

IHSTRUHEHTATIOH FOR DETECT.

OF INADEQUATE CORE COOLING - PROCEDURES...

IHSTRUHENTATIOH FOR DETECT.

OF INADEQUATE CORE COOLING -

SUBCOOL HETER.

INSTRUHEHTATION FOR DETECT.

OF INADEQUATE CORE COOLIHG - OESC.

OTHER.

INSTRUHENTATION fOR DETECT.

OF INADEQUATE CORE CLIHG INSTLL ADD'L INSTRINENTATION.

POWER SUPP.

FOR PRESSURIZER RELIEF, BLOCK VALVES 8 LEVEL IND. - UPGRADE POWER SUPP.

FOR PRESSURIZER RELIEF, BLOCK VALVES 8 I.EVEL IND. - TECH SP IE BULLETINS 05, 79-06, 79-08.

~ ~

~

~

~

~

~

~ ~

~ ~ ~ ~ ~ ~

~ ~

~

~

~ ~ ~

~

~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ t4 ~ ~ ~ ~

HULTI-PLAHT ISSUE NUHBER ACTION HO.

ISSUE TITLE LICENSEE IHPLEHEHTATION STATUS

  • II. K. 1. 5

<<I I. K. 1. 10

<<I I. K. 1.20

<<I I. K. 1.21

<<I I. K. 1.22

<<II.K.1.23

<<I I. K. 2. 2

  • II. K.2.8 I I. K.2.9 I I. K.2. 10

<< I I. K.2. 11 I I. K. 2. 13 I I. K.2. 14 I I. K. 2. 15 II. K. 2. 16 II. K.2. 17 I I. K.2. 19

<<I I. K.2. 20 "II.K.3.1.A "II. K.3. 1.8 I I.K.3. 2 I I. K.3.3 II.K.3.5.A II.K.3.5.8 I I.K.3. 7 II.K.3.9 I I. K. 3. 10 II.K.3.11 II. K.3. 12. A I I. K. 3. 12. 8 I I. K. 3. 13. A I I. K. 3. 13. 8 F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 FOll FN2 FOI3 F043

'IE BULLETINS - REVIEW ESF VALVES.

IE BULLETIHS - OPERABILITY STATUS.

IE BULLETINS -

PROMPT HANUAL REACTOR TRIP.

IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP

~......

~.........

~..--.- ~" ~ - ~

IE BULLETINS - AUX. HEAT REH SYSTEH, PROC.

IE BULLETINS -

RV LEVEL, PROCEDURES..

ORDERS ON MW PLANTS - PROCEDURES TO CONTROL AFW IND OF ICS.

ORDERS OH 8&W PLANTS - UPGRADE AFW SYSTEH.

ORDERS ON MW PLANTS - FEHA OH ICS............................................................

ORDERS ON 8&W PLANTS - SAFETY-GRADE TRIP.

ORDERS ON MW PLANTS - OPERATOR TRAIHIHG.

ORDERS ON B&W PLANTS - THERHAL HECHANICAL REPORT (CE & 'W PLAHTS ALSO).

ORDERS ON 8&W PLANTS - LIFT FREQUENCY OF PORV'S & SV's ORDERS ON MW PLAHTS - EFFECTS OF SLUG FLOW.

ORDERS ON 8&W PLANTS - RCP SEAL DAHAGE ORDERS ON 8&W PLANTS VDIDING IN RCS (CE & W PLANTS ALSO).

BENCNHARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STH GEHERATOR.

ORDERS ON 8&W PLANTS - SYSTEH RESPONSE TO SB LOCA..

8&0 TASK FORCE - AUTOHATIC PORV ISOLATION DESIGN.

FINAL RECOISENDATIONS, 8&0 TASK FORCE - AUTO PORV ISO TEST/INSTALL.

8&0 TASK FORCE - REPORT ON PORV FAILURES.

8&0 TASK FORCE - REPORTING SV & RV FAILURES AND CHALLEHGES...

~ ~

~

~ ~

~ ~

~ ~ ~ ~ ~

8&0 TASK FORCE - AUTO TRIP OF RCP'S PROPOSED HODIFICATIONS.

8&0 TASK FORCE - AUTO TRIP OF RCP'S HODIFICATIONS........................

~ ~ ~ -

~ ~...

~ ~

8&O TASK FORCE - EVALUATION OF PORV OPEHIHG PROBABILITIES.................."".

~ ~ -.- ~". ~.

~ ~ ~. ~

8&0 TASK FORCE - PID CONTROLLER HODIFICATION.

~ ~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~

~ ~ ~ ~ ~ ~

~ ~

8&0 TASK FORCE - PROPOSED ANTICIPATORY TRIP NDIFICATIONS.

~ ~ ~ ~ ~

8&0 TASK FORCE - JUSTIFY USE OF CERTAIN PORV.

~ ~ ~ ~ ~ ~

~ ~ ~

~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~

~ ~ ~ ~

~ ~

~

~

~ ~

8&0 TASK FORCE - AHTICIPATORY TRIP ON TURBINE TRIP PROPOSED ISDS.

8&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL HDOS.

8&0 TASK FORCE - HPCI & RCIC SYSTEH IHITIATIOH LEVELS ANALYSIS..................."...."..-.. ".".-"" ~-

8&0 TASK FORCE - HPCI & RCIC INITIATION LEVELS HODIFICATIOH.....-"".. "

~. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~'

~ ~ ~. ~

HULTI-PLANT ISSUE NINBER ACTION HO.

ISSUE TITLE LICEHSEE INPLENENTATION STATUS "II.K.3.14 II. K. 3. 15 I I. K. 3. 16A II. K. 3. 16. 8 I I. K. 3. 17 I I.K.3.18.A I I. K. 3. 18. 8 II.K.3.18.C

<<II.K.3.19 "II.K.3.20 I I.K.3.21.A I I.K.3. 21. 8 I I. K. 3. 22. A II.K.3.22.8 II.K.3.24 II.K.3.25.A I I.K.3. 25. 8 I I. K.3.27 I I.K.3. 28

' l. K. 3. 29 I I.K.3.30.A I I. K. 3. 30. 8 II.K.3.30.C I I. K. 3. 31

  • II.K.3. 40 "I).K. 3. 43 I I. K. 3. 44 II.K.3.45 I I. K. 3. 46 "II.K.3. 57 I I I.A. 1. 1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 850 TASK BLO TASK 8&0 TASK BM TASK BM TASK BM TASK BM TASK BM TASK BM TASK 8&0 TASK 8$ TASK BM TASK 8&0 TASK 8&0 TASK BLO TASK BM TASK 8$ TASK BM TASK 8&0 TASK 8&0 TASK 8$ TASK 8&0 TASK 8&0 TASK BLO TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK

RESPONSE

IDENTIFY ENERGENCY FORCE - ISO CONDENSER ISOLATION ON HIGH RAD.

FORCE - HODIFY HPCI & RCIC BRK DETECTION CIRCUITRY.

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY.

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES HODIFICATIOHS.

FORCE - ECC SYSTEH OUTAGES............

FORCE - ADS ACTUATIOH STUDY.

FORCE - AOS ACTUATION PROPOSED NODIFICATIOHS.

FORCE - ADS ACTUATION HODIFICATIOHS.

FORCE - INTERLOCK RECIRCULATORY PUNP HODIFICATIONS.

FORCE - LOSS OF SVC WATER AT BRP.

FORCE - RESTART OF CSS & LPCI LOGIC DESIGN.

FORCE - RESTART OF CSS & LPCI LOGIC DESIGN HODIFICATIONS.

FORCE - RCIC SUCTION VERIFICATION PROCEDURES...

FORCE - RCIC SUCTION HODIFICATION.

FORCE - SPACE COOLING FOR HPCI/RCI LOSS OF AC POWER.

FORCE -

POWER ON PUHP SEALS PROPOSEO HODIFICATIONS.

FORCE -

POWER ON PUHP SEALS HODIFICATIOHS.

FORCE - COtSON REFERENCE LEVEL FOR BWRS.

FORCE - qUALIFICATIOHOF ADS ACCUHULATORS.

FORCE - PERFORHANCE OF ISOLATION CONDENSERS.

FORCE - SCHEDULE FOR OUTLINE OF SB LOCA HODEL.

FORCE - SB LOCA HOOEL, JUSTIFICATION.

FORCE - SB LOCA METHODS NEW AHALYSES.

FORCE - CONPLIANCE WITH CFR 50.46.

~ ~

~ ~ ~.. ~. ~ ~ ~ ~ -

~ ~.

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

FORCE -

RCP SEAL OAHAGE - COVEREO BY II.K.2.16 AND II.K.3.25.

FORCE - EFFECTS OF SLUG FLOW - COVEREO BY II.K.2.15.

FORCE - EVALUATE TRANSIENT WITH SINGLE FAILURE.

FORCE - ANALYSES TO SUPPORT.

TO LIST OF CONCERNS FROH ACRS CONSULTANT.

WATER SOURCES PRIOR TO NANUAL ACTIVATION OF ADS.

PREPAREDNESS, SHORT TERN.

~ ~

~

~

~

~

HULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS III.A.1.2.1 I I I. A. 1.2. 2 (SEE F063, I II.A. 1. 2. 3 (SEE F063, III.A.2.I III.A.2.2 "III.D. I. 1. 1 "III. D. l. 1. 2 I I I.D. 3. 3. I Ill.0.3.3.2 III.0.3.4.1

  • II1.0.3.4.2 "II I. D. 3.4. 3 HPA-F008 HPA-F063 HPA-F064 HPA-F065 HPA-F071 HVA-8072 HPA-8083 67.4. 1 F064, F065)

F064, F065)

F067 F068 F069 F070 F070 F008 F063 F064 F065 FOll B072 8083

'001

'UPGRADE EHERGEKCY SUPPORT FACILITIES - INTERIH TSC OSC 4 EOF.

UPGRADE EHERGENCY SUPPORT FACILITIES-DESIGN-INCQRP.

INTO F063/F064/F065.

UPGRADE EHER SUPPORT FACILITIES " HOOS INCORPOR.

INTO F063, F064 6 F065.

UPGRADE PREPAREDNESS - UPGRADE EHERGENCY PLANS TO APP.

E.

10 CFR 50..

UPGRADE.PREPAREDNESS - HETEOROLOGICAL DATA.

PRIHARY COOLANT OUTSIDE CONTAINHENT - LEAK REDUCTION.

PRIHARY COOLANT OUTSIDE CONTAINHENT - TECH SPECS INPLANT RAD. HONIT. - PROVIDE HEANS TO DETER.

PRESENCE OF RADIOIODINE INPLANT RADIATION HONIT. - HODIFICATIONS TO ACCURATELY HEAS.

IODINE.

CONTROL ROOH HABITABILITY-REVIEW.

CONTROL ROOH HABITABILITY-SCHEDULE HODIFICATIONS.

CONTROL ROOH HABITABILITY-IHPLEHENT HODIFICATIONS.

1.0.1.1 DETAILED CONTROL ROOH DESIGN REVIEW PROGRAH PLAN.

III.A.1.2 TECHNICAL SUPPORT CENTER III.A.1.2 OPERATIONAL SUPPORT CENTER.

Ill.h.l.2 EHERGENCY OPERATIONS FACILITY I.D.1.2 DETAILED CONTROL ROON REVIEW (FOLLOWUP TO F-B).

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 6 83-02)

TECH SPEC COVERED BY GENERIC I.ETTERS 83-26 6 83-37 FOR NUREG-0737.

REACTOR COOLANT PUHP TRIP (GENERIC LETTER 85-12).

~

~

~

~

tMC A? N.Y.t:.t..X4.......

April 14, 1989

'g DOCKET NO(S)

~ 50-335/389 Nr. H.

F.

Conway Senior Vice President-Nuclear~

Nuclear Energy Department Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420

SUBJECT:

ST.

LUCIE HNITS 1

AND 2 DISTRIBUTION

"', Docket Fi1 e PDI I Rdg File J. Norris D.

t'ai 1 1 e r, The following documents concerning our review of the subject facility are transmitted for your information.

Notice of Receipt of Application,= dated Draft/Final Environmental Statement,'ated Q Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.

dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License, dated

[jQ Bi-Weekly Notice; Applications and Amendments to Operatino Licenses Involving No gggggg d

g

'gd g,d d~g ggg Exemption, dated Construction Permit No.

CPPR-

, Amendment No.

dated Facility Operating License No.

, Amehdment No.

dated Order Extending Construction Completion Date, dated monthly Operating Report for transmitted by letter dated

+ Annual/Semi-Annual Report-transmitted by letter dated En cl osures:

As stated See next page Division of Reactor Projects I/II Office of Nuclear Reactor Regulation g

OFFICE/

SURNAME)

OATEN':

MI

~ ~ ~ ~ ~ e

~o

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

D.

%.ER NRC FORM 318 IIOI80INRCM 0240 OFFICIAL RECORD COPY

Retrieved from "https://kanterella.com/w/index.php?title=ML17222A764&oldid=5120235"