ML17304B132

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Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facility
ML17304B132
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/14/1989
From: Murley T
Office of Nuclear Reactor Regulation
To: Karner D
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
TASK-***, TASK-TM NUDOCS 8905010186
Download: ML17304B132 (22)
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Text

~gg RfaI P0 Pa) t+g UNITE0 STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 April 14, 1989 Docket Hos.:

50-528, 50-529 and 50-530 Nr. Donald B. Karner Executive Ace President Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034 Mr. Karner:

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

As an ericlosure we are providiIIg a printout of all TNI items annotated where our Tracking system indicates that,implementation is not complete.

For the purpose of this request, implementation shoula be considered complete when, to the best of your knowledge, all actions necessary to satisfactorily meet the requireIIents of IIUPEG-0737 ano NUREG-0737 SupplemerIt 1 have been completed.

Mhere you have not fully completed an item as described

above, we request that you fllark-up the enclosure to reflect your projected implementav'Ion date.

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

hardware, procedures,
training, technical specifications).

Nore explicit instructions are provided as part of the enclosure.

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

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

In view of the importance of the informatson we request your personal attentior and certification that the iIformatior 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, l989.

The estimated average burden hours is 40 person hours per owner response, including searching data

sources, gathering and analyzing the data, and preparing the required letter.

Send coIIeents regarding this burden estimate or any other aspect uf this collection aeoaoaoaaS 890414 0 PDR ADOCK 05000528 P

PNUJ

~I If April 14, 1989 of snformation, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regu1atory Commiss>on washington, D.C.

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

20503.

Your prompt attention to this matter within the requested time frame is appreciated.

S incere ly,

Enclosure:

As stated Thomas E. Mur 1 ey, rector Office of Nuclear Reac ulation cc w/enclosure:

See next page

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0 April 14, 1989 of information, including suggestions for reducing this burden, to the.Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources tianagement, U.S. Nuclear Regulatory Commission Mashington, D.C.

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

20503.

Your prompt attention to this matter within the requested time frame is appreciated.

Sincerely, 51'4inal s1gaed by Thomas Z. llturley Encl osur e:

As stated cc w/enclosure:

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.Mr. Donald B. Karner Arizona Nuclear Power Project Executive Vice President Post Office Box 52034 Phoenix',. Arizona 85072-2034 Palo Verde CC:

Arthur C. Gehr, Esq.

Snell

& Milmer 3100 Valley Center.

Phoenix, Arizona 85073.

-Charles R. Kocher, Esq. Assistant Council James A. Boeletto, Esq.

Southern California.Edison Company P. 0.

Box 800

Rosemead, California 91770 Mr. Tim Polich U.S. Nuclear Regulatory Commission HC-03 Box 293-NR Buckeye, Arizona 85326 1

Regional Administrator, Region V

U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Malnut Creek, California 94596 Mr. Charles B.

Br inkman Rashington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852=

Mr. Charles Tedford, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, Arizona 85040 Chairman Maricopa County Board of Supervisors 111 South Third Avenue Phoenix, Arizona 85003

II

GUIDELINES FOR UPDATING THI STATUS 1.

The enclosure provides a complete list1ng of all THI requirements from NUPEG-0737 and NUREG-0737 Supplement I.

Regulatory Guide 1.97 requirements, although addressed in Supplement 1 to NUREG-0737, are excluded since they did not orig1nate frow the THI Action Plan.

This listing consists of a aatrix of 1tems applicable to both operating reactors and operating license applicants (NTOLS) as of November, 5980, as shown in'NUREG-0737 Enclosure 1 and 2, respect1vely.

All items wh1ch are not listed 1dentically in Enclosure 1 and 2 are marked with asterisks to indicate differences between operat1ng reactor and NTOL requirements.

1Ihenever these differences occur, enter data in accordance with the appropr1ate t1tle, regardless of the THI Action Plan item nurser listed.

Your. NRC Pro'ect Hanager has indicated which issues are shown as unimplemented in the NRC track1ng system.

Please review the entire listing for each licensed reactor unit.

Nhere an item was not applicable for your facility, mark N/A in the implementation status column.

2.

Mhere an iten was applicable to your facility but no changes were necessary, mark NC in the implementation status column.

3.

'Nhere an item was applicable to your facility and changes are complete mark C in the implementation status column. If the date is readily available (month and year) we request you provide it, however, C is sufficient.

}fhere an item was applicable to your facility and is not fully 1mplemented, provide your prospected implementation data (month and year) and a short note identifying the outstand1ng 1tem (e.g. hardware, procedures, training, technical specifications).

MULTI-PLANT I'AUL NUMBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEMEHTATION STATUS FOOl F002 F002 F003 F004 F004 F005 F005 F006 F007 F008 & F071)

F009 I.h. l. l. 1

" I.h. l. 1. 2

'.h. I. l. 3

" I. h. l. 1. 4 I.A.1.2 I.h. 1.3. 1 l.h. l. 3. 2 l.h. 2. 1. 1 I.h.2. 1.2 I. h. 2. l. 3 I.h.2.1.4 l.h.2.1.5 I.'h. 2. 3 l, h. 3. l. I I.h. 3. l. 2 I. h. 3. 1. 3. A l.h. 3. l.3.8

'I U. 1.2 l

C l.l i <:.1.2.A I.C. l.2.0 I. C. l. 3. A l.C. l.3.8 I.C.2 I,C.3 i.C.n I.C.U

},C.O "l C/ I

'. C. /. 2

'I C.U l U. l

{See l 0.2.1 6HIFT TECHNICAL ADVISOR - ON DUTY.......

SHIFT TECHNICAL ADVISOR - TECH SPECS..

SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT 8.

SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAH.

SHIFT SUPERVISOR RESPONSIBILITIES.

SHIFT MANNING - LIHIT OVERTIMES..

SHIFT MANHING - HIN SHIFT CREW.

ISIEDIATE UPGRADING Of RO & SRO TRAINING AND QUAL. -

SRO EXPER 184EDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - SRO'S BE RO'5 lYR....

IWEOIATE UPGRADING OF RO & SRO TRAINING AND QUAL. " 3 MO. TRAIHING.

IWEDIATE UPGRADING OF RO & SRO TRAIHING AND QUAL. - HODIFY TRAIHING.

IfSEDIATE UPGRADING OF RO & SRO TRAINING ANO QUAL. - FAClLITY CERTIF.

ADMINISTRATIONOF TRAINING PROGRAHS.

REVISE SCOPE & CRITERIA FOR LICEN5ING EXAHS -

INCREASE SCOPE REVISE SCOPE & CRITERIA FOR LICENSING EXAHS -

INCREASE PASSING GRADE REVISE SCOPE & CRIT.

FOR LIC.

EXAHS - SIMULATOR PLANTS WITH 51MULATORS..

REVISE SCOPE

& CRIT.

FOR LIC.

EXAHS - SIMULATOR - OTHER PLANTS EVALUATION OF ORGANIZATION & HANAGEMENT.

SHORT-TERH ACCIDENT & PROCEDURES REVIEW - 58 LOCA.

SHORT-TERM ACCIO. & PROCEDURES REV. -

INAOEQ.

CORE COOL.

REANAL. GUIDELINES SHORT-TERH ACCID. & PROCEDURES REV. -

INADEQ.

CORE COOL.

REVISE PROCEDURES SHORT-TERH ACCIO. & PROCEDURES REV - TRANSIENTS & ACCOTS.

REANAL GUIDELINES (PROC.

GEH. PKG.).

SHORT-TERM ACCID. & PROCEDURES REV. - TRANSIENTS & ACCORS.

REVISE PROCEDURES (UPGRADED EOP'5)

SHIFT & RELIEF TURNOVER PROCEDURES SHIFT-SUPERVISOR RESPONSIBILITY...............

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CONTROL-ROOH ACCESS.

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FEEDBACK OF OPERATING EXPERIENCE.

VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES.

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NSSS VENDOR REV.

OF PROC " LOW POWER TEST PROGRAH.

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NSSS VENDOR REV.

OF PROC -

POWER ASCENSION & EHER.

PROCS.

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PILOT HON OF SELECTEO EMERGENCY PROC FOR NTOLS.

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CONTROL-RDDH DESIGN REVIEWS

{ENTER DATA FOR MPA FOOB & HPA F-071)............

PUNT-SAFETY PARAMETER DISPLAY CONSOLE - DESCRIPTION.

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HULTI-P LANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEHENTATION STATUS I.0.2.2 I.D.2.3 "I G 1

1 "I.G.l. 2 "I.G.1.3 I I.B. 1. 1 I I.B. 1. 2 II.B.1.3 I I.B. 2. 1

" I I.8.2. 2 "II.8.2.3 "I1.8.2. 4 "II.8.3. 1 "II.B. 3. 2 AII 8.3.3 "II.8.3. 4 I I. 8.4. 1

" I I. 8.4. 2. A "II. 8.4. 2. 8 I I.D. I. I "II 0.1.2.A

  • II.0.1.2.8 I I. 0. 1. 3 "II.0.3.1 A I I.0.3. 2

" I I. E. l. l. 1 (SEE NOTE 1)

"II.E.1.1.2 (SEE NOTE 2)

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

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

'PLANT-SAFETY PARAHETER DISPLAY CONSOLE - INSTALLED.

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IHPLEHENTEO.

TRAINING DURING LOW-POWER TESTING - PROPOSE TESTS TRAINING DURING LOW-POWER TESTING - SUBHIT ANAL. 8 PROCS.

TRAINING DURING LOW-POWER TESTING - TRAINING 8 RESULTS REACTOR-COOLANT SYSTEH VENTS - DESIGN VENTS REACTOR-COOLANT SYSTEH VENTS - INSTALL VENTS (LL CAT 8)

REACTOR-COOLANT SYSTEH VENTS - PROCEDURES.

PLANT SHIELDING - REVIEW DESIGNS.

PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS PLANT SHIELDING - PLANT HODIFICATIONS (LL CAT 8).

PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A THI ACTION ITEM.

POSTACCIOENT SAMPLING - INTERIM SYSTEH.

POSTACCIOENT SAMPLING - CORRECTIVE ACTIONS.

POSTACCIOENT SAHPLING - PROCEDURES.

POSTACCIOENT SAHPLING - PLANT MODIFICATIONS (LL CAT 8).

TRAINING FOR HITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAH.

TRAINING FOR HITIGATING CORE OAHAGE - INITIAL TRAINING FOR HITIGATING CORE DAMAGE - COMPLETE.

RELIEF 8 SAFETY VALVE 7EST REQUIREMENTS - SUBMIT PROGRAM.

RELIEF 8 SAFFTY VALVE 7EST REQUIREMENTS - COHPLE7E TESTING.

RELIEF 8 SAFETY VALVE TEST REQUIREHENTS - PLANT SPECIFIC REPORT.

RELIEF 8 SAFETY VAVLE TEST REQUIREHENTS - BLOCK-VALVE TESTING.

VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS OF VALVE POS VALVE POSTION INDICATION - TECH SPECS.

AFS EVALUATION-ANALYSIS.

AFS EVALUATION-SHORT TERH MOOS.

AFS -LONG TERH MOOS.

NO IE I THE ITEM LISTED IS FROH NUREG 0737

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ENCLOSURE 2 ANO IS APPLICABLE TO NTOLS 5 ONLY NOTE 2 - THE ITEH LIS7EO IS FOR ALL PLANTS (OPERATING REACTORS AND NIOL'S)

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

HULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS s

~

I I.E.1.2.1.A I I. E.1.2.1.8 I I. E.1.2.2.A A I I. E. 1. 2. 2. 8

" I I. f. l. 2. 2. C "lI. E.3. 1. I "ll.f.3.1.2 l I. E.4. 1. 1

" l I. E. 4. 1. 2

" I l. E.4. l. 3 I I. C. 4. 2. 1-4 "l l. E.4. 2. 5. A

  • ll.E.4.2.5.8 l 1.E.4.2.6 l l. E.4.2.7 "lI. E.4.2. 8 "Il. f. l. 1 "ll.F.1.2.A Al l F.1.2.8

' l. F. 1. 2. C

" I I F. l. 2. 0 "ll. F. 1.2. E "II. F. 1.2. F "II. F. 2. 1 "lI.F.2.2

" Il. F. 2. 3 "lI. F.2. 4

" I I.G. 1. 1 A l I. G, 1. 2 l I.K. I (Oper.

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

'0 AFS INITIATION& FLOW-CONTROL GRADE AFS INITIATION& FLOW - SAFETY GRADE..

AFS INITIATION& FLOW - FLOW INDICATION CONTROL GRADE.

AFS INITIATION& FLOW - LL CAT A TECH SPECS.....

AFS INITIATION& FLOW - SAFETY GRADE EHERGENCY POWER FOR PRESSURIZER HEATERS -

UPGRADE POWER SUPPLY EMERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS.

DEDICATED HYDROGEN PENETRATIONS - DESIGN.

DEDICATED HYDROGEN PENETRATIONS - REVIEW & REVISE M2 CONTROL PROC..

DEDICATED HYDROGEN PENETRATION - INSTALL CONTAINHENT ISOLATION DEPENDABILITY - IHP.

DIVERSE ISOLATION.

CONTAINMENT ISOLAT. DEPENDABILITY -

CNTHT PRESS.

SETPT.

SEECIFIY PRESS CONTAINHENT ISOLATION DEPENDABILITY - CNTHT PRESSURE SETPT.

HODS.

CONTAINMENl ISOLATION DEPENDABILITY - CNTHT PURGE VALVES.

CONTAINHENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES.

CONTAINHENT ISOLATION DEPENDABLITY " TECH SPECS.

ACCIDENT - HONITORING - PROCEDURES.

ACCIDENT - HONITORING - NOBLE GAS HONITOR.

ACCIDENT - HONITORING - IODINE/PARTICULATE SAMPLING.

ACCIDENT - HONITORING - CONTAINMENT HIGH-RANGE HONITOR.

ACCIDENT - HONITORING - CONTAINMENT PRESSURE ACCIDENT - HONITORING - CONTAINMENT WA'lER LEVEL.

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ACCIDENT - HONITORING - CONTAINMENT HYDROGEN.

INSTRUHENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

PROCEDURES INSTRUHENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

SUBCOOL HETER.

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INSTRUMENTATION FOR DETECT.

OF INADE(UATE CDRE COOLING - DESC.

OTHER.

INSTRUHENTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL AOD'L INSTRUHENTATION...

POWER SUPP.

FOR PRESSURIZER RELIEF>

BLOCK VALVES & LEVEL INO. -

UPGRADE

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FOR PRESSURIZER RELIEF, BLOCK VALVES & LEVEL IND. - TECH SP.

IE BULLETINS 05, 79-06, 79-08.

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C HULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS "II. K. 1. 5 "II. K. 1. 10 "I I. K. 1. 20 "II. K. l. 21 "I I.K. 1. 22 "II.K.l. 23 "II. 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 I I. K. 2. 16 I I. K.2.17 I I. K.2. 19

" I I. K. 2. 20 "II. K. 3. l. A "I I.K. 3. 1. 8 II.K.3.2 I I.K.3. 3 I I. K. 3. 5. A I I. K. 3. 5. 8 II.K.3.7 I I. K. 3. 9 I I. K. 3. 10 I I. K. 3. 11 I I. 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 F041 F042 F043 F043

'IE BULLETINS - REVIEW ESF VALVES.....

IE BULLETINS - 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 8&W PLANTS -

PROCEDURES TO CONTROL AFM IND OF ICS ORDERS ON 8&W PLANTS -

UPGRADE AFW SYSTEH.

ORDERS ON 8&M PLANTS - FEHA ON ICS.

ORDERS ON 8&W PLANTS -

SAFETY-GRADE TRIP.

ORDERS ON 8&W PLANTS - OPERATOR TRAINING.

ORDERS ON 8&W PLANTS - THERHAL MECHANICAL REPORT (CE & W PLANTS ALSO).

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

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

ORDERS ON 8&W PLANTS -

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

BENCNHARK 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 RECOHHENDATIONS, 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 ANO CHALLENGES 8&0 TASK FORCE - AUTO TRIP OF RCP'S PROPOSEO HODIFICATIONS.

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

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

8&0 TASK FORCE -

PROPOSED ANTICIPATORY TRIP HODIFICATIONS.

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

B&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSEO HODS 8&0 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL HODS 8&0 TASK FORCE - HPCI & RCIC SYSTEH INITIATION LEVELS ANALYSIS 8&0 TASK FORCE - HPCI & RCIC INITIATION LEVELS HODIFICATION. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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HULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS

" I I.K. 3. 14 I I. K. 3. 15 II. 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 I I. K. 3. 18. C "I I. K. 3. 19 AII. K.3.20 I I. K. 3. 21. A ll.K.3.21.8 II.K.3.22.A I I. K. 3. 22. 8 l l. K. 3. 24 I I. K. 3. 25. A I I. K. 3. 25. 8 I I. K. 3. 27 I I. K. 3. 28 A I I. K. 3. 29 l I. K. 3. 30. A I I. K.3.30.8 II.K.3.30.C l I. K. 3. 31 A I I. K. 3. 40 "ll.K 3.43 I I. K.3.44 I l. K. 3.45 I I. K. 3. 46 "Il. 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 SM TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&O TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK B&0 TASK B&0 TASK 8&0 TASK 8&0 TASK B&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK

RESPONSE

IDENTIFY EMERGENCY FORCE - ISO CONDENSER ISOLATION ON HIGH RAD.

FORCE - MODIFY NPCI & RCIC BRK DETECTION CIRCUITRY FORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY.

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.

FORCE -

ECC SYSTEH OUTAGES.

FORCE - ADS ACTUATION STUDY.

FORCE - ADS ACTUATION PROPOSED HODIFICATIONS.

FORCE - ADS ACTUATION HOOIFICATIONS.

FORCE -

INTERLOCK RECIRCULATORY PUHP 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 PROPOSED MODIFICATIONS.

FORCE -

POWER ON PUMP SEALS MODIFICATIONS.

FORCE -

COMMON REFERENCE LEVEL FOR BWRS.

FORCE - QUALIFICATION OF ADS ACCUMULATORS.

FORCE - PERFORHANCE OF ISOLATION CONDENSERS.

FORCE - SCHEDULE FOR OUTLINE OF SB LOCA HODEL FORCE -

SB LOCA HODEL, JUSTIFICATION.

FORCE " SB LOCA METHODS NEW ANALYSES FORCE - COHPLIANCE WITH CFR 50.46.

FORCE " RCP SEAL DAHAGE -

COVEREO 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 FROM ACRS CONSULTANT.

WATER SOURCES PRIOR TO MANUAL ACTIVATION OF ADS PREPAREDNESS, SHORT TERH.

Cl C

E

HULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS I I I.A. 1.2. 1 III.A.1.2.2 (SEE F063, I I I.A. 1. 2. 3 (SEE F063, I I I.A.2. 1 I I I.A.2.2 "II I. D. l.l. 1 "II I.D. l. l. 2, I II. D. 3. 3. 1 111.0.3.3.2 II I. D. 3.4. 1 "I I I.O. 3.4. 2 "II I.O. 3.4. 3 HPA-F008 HPA-F063 HPA-F064 HPA-F065 HPA-F071 HPA-8072 MPA-8083 67.4.1

F064, F065)
F064, F065)

F067 F068 F069 F070 F070 FOOB F063 F064 F065 F071 8072 8083 G001

'UPGRADE EHERGENCY SUPPORT FACILITIES - INTERIH TSC OSC 8

EOF UPGRADE EHERGENCY SUPPORT FACILITIES-DESIGN-INCORP.

INTO F063/F064/F065 UPGRADE EMER SUPPORT FACILITIES - HODS INCORPOR.

INTO F063, F064 5 F065.

UPGRADE PREPAREDNESS - UPGRADE EHERGENCY PLANS TO APP.

E.

10 CFR 50.

UPGRADE PREPAREDNESS - METEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE CONTAINMENT - LEAK REDUCTION.

PRIHARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS.

INPLANT RAO. HONIT. - PROVIDE HEANS TO DETER.

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

IODINE.

CONTROL ROOH HABITABILITY-REVIEW.

CONTROL ROON HABITABILITY-SCHEDULE HODIFICATIONS.

CONTROL ROOH HABITABILITY-IHPLEHENT HODIFICATIONS.

I.D.l. 1 DETAILED CONTROL ROOH DESIGN REVIEW PROGRAM PLAN.

III.A.1.2 TECHNICAL SUPPORT CENTER.

III.A. 1.2 OPERATIONAL SUPPORT CENTER.

III.A.1.2 EMERGENCY OPERATIONS FACILITY.

1.0. 1.2 DETAILED CONTROL ROOH REVIEW (FOLLOWUP TO F-B).

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16

& 83-02)

TECH SPEC COVEREO BY GENERIC LETTERS 83-26 8 83-37 FOR NUREG-0737.

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)

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