ML18005A857

Forwards Info Re Implementation Status of Identified TMI Action Plan Items in Response to 890414 Request.Time Provided for Determining Status of Implementation of Items Extremely Short & Burdensome to Personnel

ML18005A857
Person / Time
Site:	Harris
Issue date:	04/18/1989
From:	Eury L CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NLS-89-109, NUDOCS 8904240337
Download: ML18005A857 (18)

Text

SUBJECT:

Forwards info re implementation status of identified TMI action plan items in response to 890414 request.

DISTRIBUTION CODE'003D COFZES RECEIVED'LTR I

ENCL L SIZE'ITLE:

OR/Licensing Submittal:

Suppl 1 to NUREG-0737(Generic Ltr 82-33 )

05000400 8

NOTES:Application for permit renewal filed.

, A.CCKLKWTED Dl BUT10N DKMONSTRa o~

. SYSTEM WEGUL'ATORY FORMATION DISTRIBUTION SY M (RZDS)

I ACCESSION NBR:8904240337 DOC.DATE: 89/04/18 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION EURYFL.W.

Carolina Power

& Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: NRR/DLPQ/HFB 10 OC/LFMB RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

0 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD2-1 PD NUDOCS-ABSTRACT 01 NRC PDR COPIES LTTR ENCL 7

7 1

1 1

1 1

1 NOXE 'IO ALL 'RIDS" RECIPII&IS:

PLEASE HELP US TO REDUCE %RBBEi CORI'ACT IHE DOCUMENI'XÃIPOL DESKF RXN Pl-37 (EXT. 20079) K) ElZMZHRH3 KXIR MNB PKN DXSTIMK7ZZGN ZZSTS KK DOCUtKHIS YOU DONFT NEZDf TOTAL NUMBER OF COPIES REQUIRED:

LTTR 17 ENCL 16

0

SMP Carolina Power & Light Company APRl 8 889 SERIAL:

NLS-89>>109 United States Nuclear Regulatory Commission ATTENTION:

Document Control Desk Nashington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO.

NPF-63 IMPLEMENTATION STATUS OF TMI ACTION PLAN ITEMS Gentlemen:

The information attached responds to your request of April 14, 1989 regarding the status of the identified TMI Action Plan Items.

Please note that the time provided to determine the status of implementation of all TMI items as required by your request has been extremely short and that significant personnel burden has been involved.

Moreover, the attached notations regarding status of individual items are necessarily brief and cannot address all of the details of the more complex issues.

Taking these constraints into account, I certify that to the best of my knowledge the attached information is correct.

Please refer any questions regarding this submittal to Mr. M. R. Oates at (919) 546-6063.

Yours very truly, LME/JHE/crs (306CRS)

Attachments L. W.

EU Executive Vice President Power Supply cc:

Mr. R. A. Becker Mr. M. H. Bradford Mr. S.

D. Ebneter aqo4240337 8'P4gio400 DOCg 05000NU oo>

411 Fayettevilte Street o P. O. Box 1551 e Raleigh, N. C. 27602

I

NOTES TO TMI ITEM STATUS TABLE Note 1'HNPP has fully implemented the requirements for an SPDS with the exception that one Human Engineering Discrepancy (HED No.

31G1-6019) remains outstanding.

A modification to correct this HED is currently in progress and scheduled to be completed by May 19, 1989.

Note 2

SHNPP has completed all required actions for this item, however the NRC has not yet issued a final Safety Evaluation Report (SER). If additional requirements are identified in the final SER, CP&L will address them at that time.

GUIDELINES FOR UPDATING TMI STATUS 1.

The enclosure provides a complete listing of all TMI requirements from NUREG-0737 and NUREG-0737 Supplement 1.

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

This listing consists of a matrix of items applicable to both operating reactors and operating license applicants (NTOLS) as of November,

1980, as shown in NUREG-0737 Enclosure 1 and 2, respectively.

All items which are not listed identically fn Enclosure 1 and 2 are marked with asterisks to indicate differences between operating reactor and NTOL requirements.

Whenever these differences occur, enter data in accordance with the appropriate title, regardless of the TMI Action Plan item number listed.

Your NRG Project Manager has indicated which issues are shown as unimplemented in the NRC tracking system.

Please review the entire listing for each licensed reactor unit.

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

2.

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

3.

Where an item was applicable to your facility and changes are complete mark G in: the implementation status column.

If the date is readily available (month and year) we request you provide it, however, C is sufficient.

4.

Where an item was applicable to your facility and fs not fully implemented, provide your projected implementation date (month and year) and a short note identifying the outstanding item (e.g.

hardware, prOCeduree,

tra1n1ng, teCnnSCal SpeCiffCatSOnS). W-Mm~K f ~ Z~a~ple'Fe

0 I

~ f 8 mrr r s C/wit M MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I.A.1. 1. 1

• I.A.l.l. 2 AI.A.1.1.3

• I.A.1. 1. 4 I.A.1.2 I.A.1.3.1 I.A.1. 3. 2 I.A.2. 1. 1 I.A.2.1.2 I.A.2.1.3 I.A.2. 1. 4 I.A.2. 1. 5 I.A.2.3 I ~ A.3.1.1 I.A.3.1.2 I.A.3. 1. 3.A I.A.3.1.3. B

• I.B.1:2 I.C.1.1 I.C. 1. 2. A I. C. 1. 2. B I.C.1.3.A I. C. 1. 3. B I. C.2 I.C.3 I.C ~ 4 I.C.5 I.C.6

• I.C.7.1 "I.C.7;2 "I.C.B I.D. 1 (See I.D.2.1 F001 F002 F002 F003

'004 F004 F005 F005 F006 F007 F008 8 F071)

F009 SHIFT TECHNICAL ADVISOR -

ON DUTY.

SHIFT TECHNICAL ADVISOR - TECH SPECS SHIFT TECHNICAL ADVISOR - TRAINED PER I,L CAT B......

SHIFT TECHNICAL ADVISOR - DESCRIBE LONG TERM PROGRAM.

SHIFT SUPERVISOR RESPONSIBILITIES.

SHIFT MANNING LIMIT OVERTIMES..

SHIFT MANNING - MIN SHIFT CREW.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL. -

SRO EXPER IMMEDIATE UPGRADING OF RO 8 SRO TRAINING AND QUAL.

SRO'S BE RO'S lYR.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL. - 3 MO. TRAINING.

IMMEDIATE UPGRADING OF RO 8( SRO TRAINING AND QUAL. - MODIFY TRAINING.

IMMEDIATE UPGRADING OF RO 8c SRO TRAINING AND QUAL. - FACILITY CERTIF.

ADMINISTRATION OF TRAINING PROGRAMS REVISE SCOPE 8c CRITERIA FOR LICENSING EXAMS -

INCREASE SCOPE.....

REVISE SCOPE 8 CRITERIA FOR LICENSING EXAMS -

INCREASE PASSING GRADE REVISE SCOPE

& CRIT.

FOR LIC.

EXAMS - SIMULATOR PLANTS WITH SIMULATORS REVISE SCOPE 8( CRIT.

FOR LIC.

EXAMS - SIMULATOR - OTHER PLANTS EVALUATION OF ORGANIZATION & MANAGEMENT.

SHORT-TERN ACCIDENT & PROCEDURES REVIEW SB LOCA.

SHORT-TERM ACCID.

8(

PROCEDURES REV. - INADEQ.

CORE COOL.

REANAL. GUIDELINES SHORT-TERM ACCID.

8( PROCEDURES REV. - INADEQ.

CORE COOL.

REVISE PROCEDURES SHORT-TERM ACCID.

8( PROCEDURES REV " TRANSIENTS 8c ACCDTS.

REANAL GUIDELINES (PROC.

GEN.

PKG. )

SHORT-TERM ACCID.

8c PROCEDURES REV. - TRANSIENTS 8( ACCDRS.

REVISE PROCEDURES (UPGRADED EOP'S)

SHIFT 8 RELIEF TURNOVER PROCEDURES SHIFT-SUPERVISOR RESPONSIBILITY.

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CONTROL-ROOM ACCESS..

FEEDBACK OF OPERATING EXPERIENCE..

VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES NSSS VENDOR REV.

OF PROC -

LOW POWER TEST PROGRAM.

NSSS VENDOR REV.

OF PROC -

POWER ASCENSION 8( EMER.

PROCS PILOT MON OF SELECTED EMERGENCY PROC FOR NTOLS CONTROL-ROOM DESIGN REVIEWS (ENTER DATA FOR MPA F008 8c MPA F-071).

PLANT-SAFETY-PARAMETER DISPLAY CONSOLE " DESCRIPTION.

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MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS I. D.2.2 I.D.2.3

• I.G.l. 1 "I.G.1.2

• I.G.1. 3 II.B. 1. 1 II.B. 1. 2 II~ B. 1. 3 II.B.2. 1

• II.B. 2. 2

• II ~ B.2. 3

• II.B.2. 4 "II. B. 3. 1

• II.B. 3. 2 "II.B. 3. 3 AII.B.3. 4 II.B.4. 1

%II.B.4.2.A

• II. B.4.2. B II.D.l. 1

• II. D. l. 2. A

• II.D. 1.2. B II.D.1. 3

• II.D.3. 1

• II.0.3. 2

• II. E. 1. 1. 1 (SEE NOTE

• II. E. 1. 1. 2 (SEE NOTE II.E. 1.1. 3 (SEE NOTE F009 F009 F010 F010 F011 F012 F013 F013 F013 F014 F015 1)

F015 2)

F015 3)

ITEM.

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AFS EVALUATION-SHORT TERM NODS AFS -LONG TERN MODS

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PLANT-SAFETY PARAMETER DISPLAY CONSOLE - INSTALLED.

PLANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED..

TRAINING DURING LOW-POWER TESTING -

PROPOSE TESTS TRAINING DURING LOW-POWER TESTING SUBMIT ANAL. & PROCS TRAINING DURING LOW-POWER TESTING - TRAINING & RESULTS REACTOR-COOLANT SYSTEM VENTS " DESIGN VENTS REACTOR-COOLANT SYSTEM VENTS - INSTALL VENTS (LL CAT B).

REACTOR-COOLANT SYSTEM VENTS -

PROCEDURES PLANT SHIELDING - REVIEW DESIGNS PLANT SHIELDING - CORRECTIVE ACTIONS TO ASSURE ACCESS PLANT SHIELDING - PLANT HODIFICATIONS (LL CAT B).

PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A THI ACTION PQSTACCIDENT SAMPLING INTERIH SYSTEM.

POSTACCIDENT SAMPLING " CORRECTIVE ACTIONS POSTACCIOENT SAMPLING -

PROCEDURES PQSTACCIDENT SAMPLING - PLANT MODIFICATIONS (LL CAT B).

TRAINING FOR MITIGATING CORE DAMAGE - DEVELOP TRAINING PROGRAM.

TRAINING FOR MITIGATING CORE DAMAGE INITIAL..

TRAINING FOR MITIGATING CORE DAMAGE - COHPLETE.............

RELIEF & SAFETY VALVE TEST REQUIREMENTS - SUBMIT PROGRAM.....

RELIEF & SAFETY VALVE TEST RE(UIREHENTS - COMPLETE TESTING.

RELIEF & SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT RELIEF & SAFETY VAVLE TEST REQUIREHENTS'- BLOCK-VALVE TESTING.

VALVE POSITION INDICATION INSTALL DIRECT INDICATIONS OF VALVE POS VALVE POSTION INDICATION - TECH SPECS AFS EVALUATION-ANALYSIS

. Awol.

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MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS II.E.1.2.1.A II. E. 1. 2. 1. B II.E.1.2.2.A "II.E.l.2.2.B

• II.E.1.2.2.C

• II.E. 3. l. 1

• II.E. 3 ~ 1. 2 II.E.4.1.1

• II. E.4. 1. 2

• II.E.4. 1. 3 II. E.4.2. 1-4

• II. E. 4 ~ 2.5. A

• II.E.4.2. 5. B II.E.4.2.6 II. E.4. 2. 7

• II.E.4.2.8

• II.F. l. 1

• II. F. l. 2. A "II.F.1.2.B

• II.F.1.2. C

• II. F. 1. 2. D

• II. F. l. 2. E

%II.F.1.2. F

• II.F.2.1

• II.F.2. 2

• II. F. 2. 3

• II.F.2.4

• II.G. 1. 1

%II.G. 1. 2 II.K. 1 (Oper.

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

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ATION.

AFS INITIATION8( FLOW-CONTROL GRADE AFS INITIATION8( FLOW - SAFETY GRADE AFS INITIATION4 FLOW -

FLOW INDICATION CONTROL GRADE AFS INITIATION8( FLOW - LL CAT A TECH SPECS AFS INITIATION 8c FLOW - SAFETY GRADE EMERGENCY POWER FOR PRESSURIZER HEATERS - UPGRADE POWER SUPPLY EMERGENCY POWER FOR PRESSURIZER HEATERS - TECH SPECS DEDICATED HYDROGEN PENETRATIONS - DESIGN.

DEDICATED HYDROGEN PENETRATIONS - REVIEW 8 REVISE H2 CONTROL PROC.

DEDICATED HYDROGEN PENETRATION - INSTALL CONTAINMENT ISOLATION DEPENDABILITY - IMP.

DIVERSE ISOLATION CONTAINMENT ISOLAT. DEPENDABILITY -

CNTMT PRESS.

SETPT.

SEECIFIY PRESS CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PRESSURE SETPT.

MOOS CONTAINMENT ISOLATION DEPENDABILITY -

CNTMT PURGE VALVES CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES CONTAINMENT ISOLATION DEPENDABLITY - TECH SPECS ACCIDENT MONITORING -

PROCEDURES.

ACCIDE)T - MONITORING -

NOBLE GAS MONITOR.....

ACCIDENT MONITORING - IODINE/PARTICULATE SAMPLING.........

ACCIDENT MONITORING - CONTAINMENT HIGH-RANGE MONITOR.

ACCIDENT MONITORING - CONTAINMENT PRESSURE ACCIDENT MONITORING - CONTAINMENT WATER LEVEL ACCIDENT MONITORING - CONTAINMENT HYDROGEN.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING -

PROCEDURES INSTRUMENTATION FOR DETECT.

OF INADE(UATE CORE COOLING -

SUBCOOL METER-INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING - DESC.

OTHER INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENT POWER SUPP-FOR PRESSURIZER

RELIEF, BLOCK VALVES 8( LEVEL IND. -

UPGRADE POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8( LEVEL IND.

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

I 4

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

• II. K. 1. 5 "II. K. 1. 10

• II. K. 1. 20

• II.K.l.21

• II. K.l. 22 AII. K. 1. 23

• II.K.2. 2 AII. K.2. &

II.K.2.9 II.K.2.10 "II. K. 2. 11 II. K.2. 13 II. K.2. 14 II. K. 2 ~ 15 II.K.2. 16 II. K.2. 17 II.K.2. 19 AII. K.2. 20

+II.K.3. 1. A "II. K. 3. 1. 8 II.K.3.2 II.K.3.3 II.K.3.5.A II.K.3.5.8 II.K.3.7 II.K.3.9 II.K.3.10 II ~ K.3. 11 II. K. 3. 12. A II. K. 3:12. 8 II.K.3.13.A II. K. 3. 13. 8 F027 F02&

F029 F030 F031 F032 F033 F035 F036 F037 F03&

F039 F039

, F040 F041 F042 F043 F043 IE BULLETINS - REVIEM ESF VALVES IE BULLETINS - OPERABILITY STATUS IE BULLETINS -

PROMPT MANUAL REACTOR TRIP IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP.........

IE BULLETINS AUX. HEAT REM SYSTEM, PROC.

IE BULLETINS -

RV LEVEL, PROCEDURES ORDERS ON 88IM PLANTS PROCEDURES TO CONTROL AFW IND OF ICS ORDERS ON 88W PLANTS UPGRADE AFM SYSTEM.

ORDERS ON-8&M PLANTS FEMA ON ICS ORDERS ON 8&W PLANTS - SAFETY-GRADE TRIP ORDERS ON 88W PLANTS - OPERATOR TRAINING.

ORDERS ON 88W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO).

ORDERS ON 88M PLANTS LIFT FREQUENCY OF PORV'S 8 SV's ORDERS ON B&W PLANTS - EFFECTS OF SLUG FLOW.

ORDERS ON 8&W PLANTS -

RCP SEAL DAMAGE ORDERS ON 8&M PLANTS - YOIDING IN RCS (CE & M PLANTS ALSO).

BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO 'ONCE THROUGH STM GENERATOR.

ORDERS ON 88W PLANTS SYSTEM RESPONSE TO SB LOCA.

88IO TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN.

FINAL RECOMMENDATIONS, 880 TASK FORCE - AUTO PORV ISO TEST/INSTALL B&0 TASK FORCE -

REPORT ON PORV FAILURES 880 TASK FORCE REPORTING SY 8 RY FAILURES AND CHALLENGES 88IO TASK FORCE - AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS 880 TASK FORCE - AUTO TRIP OF RCP'S MODIFICATIONS.

B&0 TASK FORCE EVALUATION OF PORY OPENING PROBABILITIES 880 TASK FORCE - PID CONTROLLER MODIFICATION.

880 TASK FORCE -

PROPOSED ANTICIPATORY TRIP MODIFICATIONS 880 TASK FORCE - JUSTIFY USE OF CERTAIN PORY.

880 TASK FORCE ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MOOS 880 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS............

B&0 TASK FORCE - HPCI 8

RCIC SYSTEM INITIATION LEVELS ANALYSIS..

880 TASK FORCE - HPCI & RCIC INITIATION LEVELS MODIFICATION.

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P ISSUE NUMBER MULTI-PLANT ACTION N0.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS

• II. K.3. 14 II.K. 3. 15 II. K. 3. 16A II. K. 3. 16. B II.K. 3. 17 II.K.3.18.A II.K.3.18.B II.K.3.18.C AII. K.3. 19

• II. K. 3. 20 II. K. 3. 21. A II. K. 3. 21. B II.K.3.22.A II. K. 3. 22. B II. K.3. 24 II. K.3. 25. A II.K. 3. 25. B II.K.3.27 II. K.3. 28

• II. K.3. 29 II.K.3. 30. A II.K.3. 30. B II.K.3. 30. C II.K.3. 31 "II.K.3.40

%II.K.3.43 II. K.3. 44 II. K.3.45 II.K.3.46 AII. K.,3. 57 III.A.1. 1 F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054

'055 F056 F057 F058 F059 F060 F061 F062 B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B80 TASK B&0 TASK B80 TASK B80 TASK B80 TASK B80, TASK B80 TASK B80 TASK B80 TRASK B80 TASK B80 TASK B80 TASK B&0 TASK B&0 TASK B80 TASK 880 TASK B&0 TASK B80 TASK B80 TASK

RESPONSE

IDENTIFY EMERGENCY FORCE - ISO CONDENSER ISOLATION ON HIGH RAD..

FORCE MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY..

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY..

FORCE -

CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.

FORCE -

ECC SYSTEM OUTAGES FORCE - ADS ACTUATION STUDY.

FORCE - ADS ACTUATION PROPOSED MODIFICATIONS FORCE - ADS ACTUATION MODIFICATIONS FORCE - INTERLOCK RECIRCULATORY PUMP MODIFICATIONS FORCE -

LOSS OF SVC WATER AT BRP FORCE RESTART OF CSS 8E LPCI LOGIC DESIGN.

FORCE RESTART OF CSS & LPCI LOGIC DESIGN MODIFICATIONS FORCE - RCIC SUCTION VERIFICATION PROCEDURES FORCE " RCIC SUCTION MODIFICATION.

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

FORCE -

POWER ON PUMP SEALS PROPOSED MODIFICATIONS FORCE -

POWER ON PUMP SEALS MODIFICATIONS FORCE -

COMMON REFERENCE LEVEL FOR BWRS FQRCE - QUALIFICATION OF ADS ACCUMULATORS FORCE -

PERFORMANCE OF ISOLATION CONDENSERS FORCE - SCHEDULE FOR OUTLINE OF SB LOCA MODEL FORCE -

SB LOCA MODEL, JUSTIFICATION.

FORCE -

SB LOCA METHODS NEW ANALYSES FORCE - COMPLIANCE WITH CFR 50.46...

FORCE -

RCP SEAL DAMAGE - 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 FROM ACRS CONSULTANT.

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

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s MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEMENTATION STATUS III.A.1.2. 1 III ~ A.1.2. 2 (SEE F063, III.A.1. 2. 3 (SEE F063, III.A.2. 1 III.A.2. 2 "III. D. l.l. 1

• III.D. l.l. 2 III.D. 3.3. 1 III.D.3.3. 2 III. D.3.4. 1

• III. D.3.4. 2

• III.D. 3.4. 3 HPA-F008 HPA-F063 MPA"F064 HPA-F065 HPA-F071 HPA-B072 MPA-B083 67.4.1

F064, F065)

F064, F065)

F067 F068 F069 F070 F070 F008

'F063 F064 F065

'F071 B072 B083 G001 UPGRADE EMERGENCY SUPPORT FACILITIES INTERIM TSC OSC 8

EOF UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP. INTO F063/F064/F065.

UPGRADE EHER SUPPORT FACILITIES - HODS INCORPOR.

INTO F063, F064 8c F065.

UPGRADE PREPAREDNESS -

UPGRADE EMERGENCY PLANS TO APP.

E.

10 CFR 50.

UPGRADE PREPAREDNESS - METEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE CONTAINMENT - LEAK REDUCTION.

PRIMARY COOLANT OUTSIDE CONTAINMENT - TECH SPECS INPLANT RAD. MONIT.

PROVIDE MEANS TO DETER.

PRESENCE OF RADIOIODINE INPLANT RADIATION MONIT. - HODIFICATIONS TO ACCURATELY MEAS.

IODINE CONTROL ROOM HABITABILITY-REVIEW.

CONTROL ROOM HABITABILITY-SCHEDULE MODIFICATIONS CONTROL ROOM HABITABILITY-IMPLEMENT MODIFICATIONS I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN.

III.A,1.2 TECHNICAL SUPPORT CENTER.

III.A.1.2 OPERATIONAL SUPPORT CENTER..............................-.

~...

III ~ A..l. 2 EMERGENCY OPERATIONS FACILITY I.D.1.2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8)

NUREG-0737 TECH SPECS (GENERIC LETTERS 82-16 8( 83-02).

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

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)

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