ML17328A002

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Responds to Request for Review & Status Rept of Implementation of TMI Action Plan Items at Facilities. Marked-up Computer Printout Encl
ML17328A002
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/17/1989
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Murley T
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-TM AEP:NRC:0773AD, AEP:NRC:773AD, NUDOCS 8904260232
Download: ML17328A002 (11)
v • d • e


Text

HURON DEMONSTRA,TIO.'i SYSTEM REGULAT INFORMATION DISTRIBUTIONZSTEM (RIDE)

ACCESSION NBR:8904260232 DOC.DATE: 89/04/17 NOTARIZED: NO DOCKET FACIL":50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana 6

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana S

05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEYFT.E.

Office of Nuclear Reactor Regulation, Director (Post 870411

SUBJECT:

Responds to request for review 6 status rept on NUREG 0737 TMI Action Plan requirements. Annotated NUREG 0737 list encl.

DISTRIBUTION CODE:

A046D COPIES RECEIVED:LTR I

ENCL I

SIZE:

TITLE: OR -Submittal:

TMI Action Plan Rgmt NUREG-0737 6 HUREG-0660 NOTES:

RECIPIENT

~

ID CODE/NAME PD3-1 LA STANGFJ INTERNAL: AEOD/DSP/TPAB NRR/DEST/MEB 9H NRR/DREP/RPB 10 REG FILE 01 D R DEPY COPIES LTTR ENCL

'1 0

1 1

1 1

1 1

1 1

1 0

1 1

1 1

RECIPIENT ID CODE/NAME PD3-1 PD NRR/DEST/ADS 7E NRR/DREP/EPB 10 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB COPIES LTTR ENCL 5

5 1

0 1

1 1

1 1

0 1

1 h

EXTERNAL: LPDR NSIC 1

1 1

1 NRC PDR 1

1 R

NVZE 'lo ALL "RIDS" R!XXPIEPIS:

PLEASE HELP US 'lO REZUCE %ASTE!

CXM'AC1'HE DOGMA'XWZROLDESK, RXN Pl-37 (EXT. 20079)

KO ELBGMGR YOUR NME PBCH DIPI%UBUTION LISTS HK DOCUMERX8 YOU DON'T HEED!

S h

D D

S TOTAL NUMBER OF COPIES REQUIRED:

LTTR 21 ENCL 17

l

Indiana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 8

AEP:NRC:0773AD Donald C.

Cook Nuclear Plant Units 1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 NUREG 0737 TMI ACTION PLAN REQUIREMENTS STATUS U.

S. Nuclear Regulatory Commission Document Control Desk Washington, D.

C.

20555 Attn:

T.

E. Murley April 17, l989

Dear Dr. Murley:

This letter responds to your request for a review and status report on the'UREG 0737 TMI Action Plan Requirements.

The attachment to this letter is the NUREG 0737 list you provided annotated with our implementation status.

In responding to your request we have identified, by "*", several items that were closed by NRR and later reopened by NRC Region III.

For example, we received a Safety Evaluation Report (SER) on Item III.D.3.4.1 Control Room Habitability dated February 11, 1982.

Later, during a Region III inspection, the inspector apparently disagreed with the SER and reopened Item III.D.3.4.1.

We are currently responding to those concerns.

We believe that all TMI training requirements, Items I.A.1.1.3, I.A.1.1.4, I.A.2.1.1 thru I.A.2.1.1.5, I.A.2.3, I.A.3.1.1, I.A.3.1.2., should be considered closed based on our extensive efforts to successfully obtain INPO accreditation on all Cook Plant Nuclear Training Programs.

Items I.A.3.1.3 A and B should also be closed because we have purchased, installed, and are currently training on a Cook Nuclear Plant specific simulator.

Please be advised that the attached responses were prepared on extremely short notice.

The responses are therefore only accurate to the best of our knowledge based on our ability to perform a limited records search in the short time available and are limited to the material provided to us in your letter.

We do not certify to the full and complete accuracy of our responses and we reserve the right to amend our responses if further review merits such action.

sv t

89042h0232 85'04i 7 PDR ADQCK 050003 P

PNU

Dr. T. E. Murley AEP:NRC:0773AD Sincerely, M. P. Alex ch Vice Pres dent MPA/eh Attachment cc:

D. H. Williams, Jr.

W.

G. Smith, Jr.

- Bridgman R.

C. Callen G. Charnoff G. Bruchmann A. B. Davis - Region III NRC Resident Inspector

- Bridgman

Attachment to AEP:NRC:0773AD Page 1

C - Coaplete H - Hard~are installation, procedures and training complete R - AEPSC letter response SER -

NRC Safety Evaluation Report CO -

NRC confirmatory order N/A -

NTOL or BWR plants only

<<Previously closed and reopened MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICEHSEE IMPLEMENTATION STATUS I.A.1.1.1

~I.A.1-1.2

  • I.A.1.1.3

~I.A.1' '

1.'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 1.C.1.2. 8 1.C.1.3.A I.C.1.3. 8 I.C.2 I.C.3 I.C.4 I.C.S I.C.6

~I.C.7.1 4I.C.7.2

  • I.C.B F001 F002 F002 F003 F004 F004 F005 F005 F006 F007 1.0.1 (See F008 8 F071)

I.D.2.1 F009 SHIFT TECHNICAL ADVISOR -

ON DUTY

~

SHIFT TECHNICAL ADVISOR -

TECH SPECS.

SHIFT TECHNICAL ADVISOR - TRAINED PER LL CAT B.

SHIFT TECHNICAL ADVISOR - DESCRIBE LOHG TERM PROGRAM.

SHI FT SUPERVISOR RESPONSIBILITIES.

SHIFT MANNING - LIHIT OVERTIMES.

SHIFT MANNIHG - MIN SHIFT CREN.

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. -

SRO EXPER.

IMHEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - SRO'S BE RO'S 1YR.

IMHEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL. - 3 MO. TRAINIHG.

IMHEDIATE UPGRADING OF RO & SRO TRAINING AHD QUAL. - MODIFY TRAINIHG~

IMMEDIATE UPGRADING OF RO & SRO TRAINING AND QUAL

- FACILITY CERTIF.

ADMINISTRATION OF TRAINING PROGRAMS.

REVISE SCOPE

& CRITERIA FOR LICENSING EXAHS -

INCREASE SCOPE ~

REVISE SCOPE 8 CRITERIA FOR LICENSING EXAMS -

INCREASE PASSING GRADE REVISE SCOPE

& CRIT ~

FOR LIC. EXAMS - SIHULATOR PLANTS MITH SIMULATORS.

REVISE SCOPE

& CRIT.

FOR LIC. EXAHS - SIMULATOR - OTHER PLANTS EVALUATION OF ORGANIZATION & MANAGEMENT.

SHORT-TERM ACCIDENT 8 PROCEDURES REVIEll - SB LOCA.

.SHORT-TERN ACCID. & PROCEDURES REV. -

IHADEQ. CORE COOL. REANAL. GUIDELINES SHORT-TERH ACCID. & PROCEDURES REV. -

INADEQ. CORE COOL ~ REVISE PROCEDURES.

SHORT-TERM ACCID. & PROCEDURES REV - TRANSIENTS 8 ACCDTS.

REANAL GUIDELINES (PROC.

GEN SHORT-TERH ACCID~ 8 PROCEDURES REV. - TRAHSIEHTS 8 ACCDRS.

REVISE PROCEDURES (UPGRADED SHIFT 8 RELIEF TURNOVER PROCEDURES.

SHIFT-SUPERVISOR RESPONSIBILITY.

CONTROL-ROOM ACCESS.

FEEDBACK OF OPERATING EXPERIENCE.

VERIFY CORRECT PERFORMANCE OF OPERATING ACTIVITIES NSSS VENDOR REV.

OF PROC -

LOW POMER TEST PROGRAM.

HSSS VENDOR REV.

OF PROC - PONER ASCENSIOH 8 EMER.

PROCS.

PILOT MOH OF SELECTED EMERGENCY PROC FOR HTOLS.

CON'1ROL-ROOH DESIGN REVIENS (ENTER DATA FOR MPA F008 & MPA F-071).

PLANT-SAFETY PARAHETER DISPLAY CONSOLE - DESCRIPTIONS

~

PKG ~ ) ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

EOP'S)

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

C; SER 1/01/82 C;

SER 1/01/82 Cl SER 1/01/82 C;

SER 1/01/82 C;

C; SER 11/12/81 C;

SER 11/12/81 C

C; CI C;

SER 2/11/83 C

C C

C; C;

CO 3/14/83 C;

CO 3/14/83 N/A C;

Cl R

12/21/79 C;

R 12/31/79 C;

R 3/16/86 C;

6/06/86 CI C;

C C;

SER 11/12/81 C;

SER 11/12/81 N/A H/A N/A C;

R 12/30/86 C;

Attachment to AEP:NRC:0773AD Page 2

MULTI-PLANT ISSUE NUMBER ACTION NO.

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

<<I.G.'I ~ 1

<<I.G.1.2

<<I.G.1.3 II.8.1.1 I1.8.1.2 Ij.8.1.3 II~8.2.1

  • II ~8.2.2
  • II~ 8'.3

<<I I.B.2 4

<<II.8.3.1

<<II ~8.3.2

<<I I ~8.3.3

<<II.B.3.4 II.8.4.1

<<II.B.4.2.A

<<II.B 4.2.8 II.D.1.1

<<I 1.0.1.2.A

<<II.D ~ 1.2.8 II.D.1.3

<<I I.D.3.1

<<I I.D.3.2

<<I I.E.1.1.1 (SEE NOTE

<<I I.E.1.1.2 (SEE NOTE II.E.1.1.3 (SEE NOTE FON FON F010 F010 F011 F012 F013 F013 F013 F014 F015 1)

F015 2)

F015 3)

PLANt-SAFETY PARAMETER DISPLAY CONSOLE -

INSTALLED'LANT-SAFETY PARAMETER DISPLAY CONSOLE - FULLY IMPLEMENTED.

TRAINING DURING LOM-POMER TESTING - PROPOSE TESTS.

TRAINING DURING LN POMER TESTING - SUBMIT ANAL. 8 PROCS.

TRAINING DURING LOM-PONER TESTING - TRAINING 8 RESULTS.

REACTOR-COOLANT SYSTEM VEHTS - DESIGN VENTS'EACTOR-COOLANT SYSTEM VENTS - INSTALL VEHTS (LL CAT 8).

REACTOR-COOLANT SYSTEM VENTS - PROCEDURES.

PLANT SHIELDING - REVIEII DESIGNS ~

PLANT SHIELDIHG - CORRECTIVE ACTIONS TO ASSURE ACCESS.

PLANT SHIELDING - PLANT MODIFICATIONS (LL CAT 8).

PLANT SHIELDING - EQUIPMENT QUALIFICATION-NOT TRACKED AS A THI ACTION POSTACCIDENT SAMPLIHG -

INTERIM SYSTEH.

POSTACCIDENT SAMPLING - CORRECTIVE ACTIONS.

POSTACCIDEHT SAHPLING - PROCEDURES.

POSTACCIDENT SAMPLING - PLANT MODIFICATIONS (LL CAT 8).

TRAINING FOR HITIGATING CORE DAMAGE - DEVELOP TRAINIHG PROGRAM.

TRAINIHG FOR MITIGATING CORE DAMAGE - INITIAL TRAINING FOR HITIGATIHG CORE DAHAGE - COMPLETE.

RELIEF 8 SAFETY VALVE TEST REQUIREMENTS - SUBHIT PROGRAM.

RELIEF 8 SAFETY VALVE TEST REQUIREHENTS - COMPLETE TESTIHG.

RELIEF 8 SAFETY VALVE TEST REQUIREMENTS - PLANT SPECIFIC REPORT.

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

VALVE POSITION INDICATION - INSTALL DIRECT INDICATIONS OF VALVE POS.

VALVE POSTIOH INDICATION -

TECH SPECS.

AFS EVALUATION-ANALYSIS

~ ~ ~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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

AFS EVALUATION-SHORT TERM MOOS.

AFS -LONG TERM MOOS.

ITEM.

~*

C; C;

12+1/85 H/A i N/A

'/A C;

SER 8/31/83 CI SER 8/31/83 CI SER 8/31/83 CI SER 3/23/83 C;

SER 3/23/83 C;

SER 3/23/83 N/A C;

SER 4/11/85 C;

SER 4/11/85 C;

SER 4/11/85 C;

SER 4/11/85 C;

SER 2/11/83 C;

CO 3/14/83 C;

CO 3/14/83 CI SER 11/'l7/87 C;

SER 'll/17/87 CI SER 11/17/87 C;

CO 3/14/83 C;

SER 3/20/80 O'ER 3/20/80 N/A CI SER 10/06/80 C;

SER 10/06/80 NOTE 1 - THE ITEM LISTED IS FROM NUREG-0737(

ENCLOSURE 2 AND IS APPLICABLE TO NTOLS'S OHLY NOTE 2 - THE ITEH LISTED IS FOR ALL PLANTS (OPERATING REACTORS AND NTOL'S)

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

Attachment to AEP:NRCt0773AD Page 3

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.1.2.2.B

<<II.E.1.2.2.C

  • II.E.3.1.1
  • II.E.3.1.2 11.E.4.1.1

<<11.E.4.1. 2

  • 11.E.4 ~ 1.3 II.E.4.2.1-4

<<ICE.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

<<11.F.1.1

  • II.F.1.2.A

<<I I.F.1.2.B

  • II.F.1.2.C

<<II.F.1.2.D

<<11.F.1.2.E

  • II.F.1.2. F
  • II.F.2.1

<<II.F.2.2

<<II.F.2.3

  • II.F.2.4

<<I I.G.1.1

  • 11.0.1.2 II.K.1 (Oper.

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

AFS INITIATIOH& FLOW-CONTROL GRADE.

AFS INITIATION& FLOM - SAFETY GRADE. ~.

AFS INITIATION& FLOW -

FLOM INDICATION CONTROL GRADE.

AFS INITIATION & FLOW - LL CAT A TECH SPECS

~

AFS INITIATIOH & FLOW - SAFETY GRADE.

EHERGENCY POMER FOR PRESSURIZER HEATERS UPGRADE POWER SUPPLY.

EHERGENCY POWER FOR PRESSURIZER HEATERS -

TECH SPECS.

DEDICATED HYDROGEN PENETRATIONS - DESIGN.

DEDICATED HYDROGEN PENETRATIOHS - REVIEW & REVISE H2 CONTROL PROC DEDICATED HYDROGEN PEHETRATIOH - INSTALL COHTAINMEHT ISOLATION DEPENDABILITY - IMP. DIVERSE ISOLATION.

CONTAINMEHT ISOLAT. DEPENDABILITY -

CHTMT PRESS.

SETPT.

SEECIFIY PRESS.

COHTAINMEHT ISOLATION DEPENDABILITY - CHTMT PRESSURE SETPT ~

MOOS.

COHTAINMEHT ISOLATION DEPENDABILITY - CHTMT PURGE VALVES.

CONTAINHEHT ISOLATION DEPENDABILITY - RADIATIOH SIGNAL ON PURGE VALVES.

COHTAINMEHT ISOLATION DEPENDABLITY - TECH SPECS.

ACCIDENT - MONITORING - PROCEDURES.

ACCIDENT - MONITORING -

NOBLE GAS MONITOR.

ACCIDENT - MOHITORING - IODINE/PARTICULATE SAMPLIHG~ ~

ACCIDENT - MONITORING - CONTAINMEHT HIGH-RANGE MONITOR~

ACCIDENT - MONITORING - COHTAINHENT PRESSURE.

ACCIDENT - MONITORING - CONTAINMENT WATER LEVEL.

ACCIDENT - MONITORING - COHTAIHMENT HYDROGEN.

IHSTRUMEHTATION FOR DETECT.

OF INADEQUATE CORE COOLING - PROCEDURES ~

IHSTRUMEHTATIOH FOR DETECT.

OF INADEQUATE CORE COOLING -

SUBCOOL METER INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING - DESC.

OTHER ~

INSTRUHEHTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD'L IHSTRUMEN POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES & LEVEL IND. - UPGRADE.

POMER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES & LEVEL IND. -

TECH SP.

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

TATION.

CI SER 6/16/81 C;

SER 6/16/81 O'ER 6 '16/Bl O'ER 6/16/81 C;

SER 6/16/81 Cl SER 8/25/81 C;

SER-8/25/81 C;

SER 9/09/81 C;

SER 9/09/81 C;

SER 9/09/81 C;

SER 10/30/81 C;

SER 10/30/81 C;

SER 10/30/81 C;

SER 10/30/81 C;

SER 7/27/82 CI SER 8/25/81 H; 1983 T/S R

7/31/87 H; 1983 T/S R

7/31/87 H; 1983 T/S R

7/31/87 CO 3/14/83 T/S R 7/31/87 C;

SER 12/13/85 C;

SER 6/08/83 Cl SER 6/08/83 C;

SER 4/10/87 C;

SER 4/10/87 C;

SER 4/10/87 C;

SER 4/10/87 C;

SER 7/02/80 C;

SER 7/02/80 R

5/01/79

& 6/06/79 Attachment to AEP:NRC:0773AD Page 4

HULTI-PLANT ISSUE NUNBER ACTION NO.

ISSUE TITLE LICEHSEE IHPLEHEHTATION STATUS

  • II.K-1.5
  • II.K.1.10
  • II.K-1.20

<<I I.K.1.21

<<11.K.1.22

  • II.K.1.23
  • II.K.2.2

<<11-K.2.8 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
  • II.K.2.20

<<I I.K.3.1.A

  • 11.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 11.K.3.11 II.K.3.12.A II.K.3.12.8 II.K.3.13.A II.K.3.13.8 F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 F041 F042 F043 F043 IE BULLETINS - REVIEM ESF VALVES.

IE BULLETINS - OPERABII.ITY STATUS.

IE BULLETIHS -

PROHPT HANUAL REACTOR TRIP IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP.

IE BULLETINS - AUX. HEAT REN SYSTEH, PROC.

IE BULLETINS - RV LEVEL, PROCEDURES.

ORDERS ON B&M PLANTS - PROCEDURES TO CONTROL AFM IHD OF ICS...

. ~.....

~

ORDERS OH B&W PLANTS - UPGRADE AFW SYSTEH.

ORDERS ON 8&'M PLANTS - FEHA ON ICS.

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

ORDERS ON B&W PLANTS - THERNAL HECHANICAL REPORT (CE E W PLANTS ALSO).

ORDERS OH B&W PLANTS - LIFT FREQUENCY OF PORV'S

& SV's.

ORDERS ON B&M PLANTS - EFFECTS OF SLUG FLOW.

ORDERS OH B&M PLANTS -

RCP SEAL DAHAGE~

ORDERS ON B&W PLANTS - VOIDING IN RCS (CE E W PLANTS ALSO) ~

BEHCHHARK ANALYSIS OF SEQUENTIAL AFM FLOW TO ONCE THROUGH STH GENERATORS ORDERS OH BEll PLANTS - SYSTEH RESPONSE TO SB LOCA.

BEO TASK FORCE - AUTOHATIC PORV ISOLATIOH DESIGN FINAL RECOHHEHDATIONS, BEO TASK FORCE - AUTO PORV ISO TEST/INSTALL.

B&0 TASK FORCE - REPORT ON PORV FAILURES.

BEO TASK FORCE - REPORTING SV E RV FAILURES AND CHALLENGES.

B&O TASK FORCE - AUTO TRIP OF RCP'S PROPOSED HODIFICATIONS..

BEO TASK FORCE - AUTO TRIP OF RCP'S H(OIFICATIONS.

B&O TASK FORCE - EVAI.UATION OF PORV OPENING PROBABILITIES..

BEO TASK FORCE - PID COHTROLLER HODIFICATION.

~

BEO TASK FORCE - PROPOSED ANTICIPATORY TRIP HOOIFICATIOHS.

B&O TASK FORCE - JUSTIFY USE OF CERTAIN PORV.

BEO TASK FORCE - AHTICIPATORY TRIP ON TURBINE TRIP PROPOSED H(6S.

BEO TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP IHSTALL NODS ~ ~

BEO TASK FORCE - HPCI E RCIC SYSTEH INITIATION LEVELS ANALYSIS B&0 TASK FORCE - HPCI E RCIC INITIATION LEVELS HODIFICATIOH.

~ ~

~ ~

R 6/20/80 N/A N/A H/A C;

SER '12/22/83 N/A N/A N/A N/A N/A C;

SER 6/18/84 H/A H/A N/A C;

SER '12/16/83 C;

SER 6/29/81 H/A C;

SER 9/12/83 O'ER 9/12/83 C;

SER 9/12/83 C;

SER 9/08/82 CI SER 7/13/88 C;

SER 7/13/88 H/A C;

SER 9/08/81 C;. SER 9/08/81 H/A Cl SER 9/08/81 C;

SER 9/08/81 N/A H/A Attachment to AEP:NRC:0773AD Page 5

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IMPLEHENTATION STATUS

<<I I.K.3.14 II.K.3.15 II.K;3.16A II.K.3.16.8 I I.K.3.17 II.K.3.18.A 11.K.3. 18. 8 II.K.3.18.C

  • II.K.3.19
  • II.K.3.20 II.K.3.21.A II.K.3.21.8 II.K.3.22.A II.K.3.22.8 II.K.3.24 II.K.3.25.A II.K.3.25' II.K.3.27 II.K.3.28

<<II.K.3.29 II.K.3.30.A II.K.3.30.8 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 11.K.3.46
  • II.K.3.57 III.A.I.I F044 F045 F046 F046 F047 F048 F048 F048 F049 F050 F050 F051 F051 F052 F053 F054 F055 F056 F057 F058 F059 F060 F061 F062 B&0 TASK B&0 TASK BEO TASK BEO TASK BEO TASK 8&0 TASK B&0 TASK 8&0 TASK B&0 TASK 8&0 TASK BEO TASK B&0 TASK 8&0 TASK BEO TASK 8&0 TASK B&0 TASK 8&0 TASK BEO TASK 8&0 TASK 8&0 TASK 8&O TASK B&0 TASK B&0 TASK 8&0 TASK 8&0 TASK 8&0 TASK B&0 TASK B&0 TASK RESPOHSE IDENTIFY EHERGEHCY FORCE - ISO CONDENSER ISOLATION OH HIGH RAD ~.

FORCE - HODIFY HPCI

& RCIC BRK DETECTIOH CIRCUITRY~

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES STUDY.

FORCE - CHALLENGE & FAILURE OF RELIEF VALVES HODIFICATIONS.

FORCE -

ECC SYSTEH OUI'AGES.

FORCE - ADS ACTUATION STUDY.

FORCE - ADS ACTUATIOH PROPOSED HODIFICATIOHS.

FORCE - ADS ACTUATION HODIFICATIONS.

FORCE -

INTERLOCK RECIRCULATORY PUMP MODIFICATIONS FORCE - LOSS OF SVC MATER AT BRP.

FORCE - RESTART OF CSS & LPCI LOGIC DESIGH.

FORCE - RESTART OF CSS E LPCI LOGIC DESIGN MODIFICATIONS.

FORCE - RCIC SUCTION VERIFICATIOH PROCEDURES'ORCE

- RCIC SUCTION HODIFICATIOH~

FORCE -

SPACE COOLING FOR HPCI/RCI LOSS OF AC POMER FORCE -

PDMER OH PUHP SEALS PROPOSED HODIFICATIOHS.

FORCE -

POMER ON PUMP SEALS MODIFICATIONS.

FORCE -

COMMON REFERENCE LEVEL FOR BMRS.

FORCE - QUALIFICATIOH OF ADS ACCINULATORS.

FORCE -

PERFORHANCE OF ISOLATION COHDEHSERS.

FORCE - SCHEDULE FOR OUTLINE OF SB LOCA HDDEL.

FORCE - SB LOCA HODEL, JUSTIFICATION FORCE - SB LOCA HETHODS NEll ANALYSES.

FORCE - COHPLIANCE MITH CFR 50.46.

FORCE -

RCP SEAL DAHAGE -

COVERED BY II.K.2.16 AND II.K.3.25 FORCE - EFFECTS OF SLUG FLOM - COVERED BY II.K.2.15

'ORCE

- EVALUATE TRANSIENT MITH SINGLE FAILURE FORCE - ANALYSES TO SUPPORT TO LIST OF CONCERNS FRDH ACRS CONSULTAHT.

MATER SOURCES PRIOR TO HANUAL ACTIVATIOH OF ADS.

PREPAREDNESS, SHORT TERH.

N/A H/A N/A C;

SER 8/05/83 N/A H/A H/A N/A H/A H/A H/A H/A N/A N/A C;

SER 6/23/82 C;

SER 6/23/82 H/A N/A H/A C;

SER 5/24/85 C;

SER 5/24/85 CI SER 5/24/85 C;

SER 5/24/85 H/A N/A N/A H/A H/A N/A Cg SER 9/29/86 Attachment to AEP:NRCJ0773AD Page 6

MULTI-PLANT ISSUE NUHBER ACTION NO.

ISSUE TITLE I

LICENSEE IMPLEMENTATION STATUS I I I.A.1.2.1 III.A.1.2.2 (SEE F063, III-A.1.2.3 (SEE F063, III.A.2.1 111.A.2.2

<<111.0.1.1.1

<<I II.D.1.1.2 111.D.3.3.1 111.D.3.3.2 III.D.3.4.1

<<III.D.3.4.2

  • III.D.3.4.3 MPA-F008 MPA-F063 MPA-F064 MPA-F065 MPA-F071 MPA-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 EMER SUPPORT FACILITIES - MOOS INCORPOR ~

INTO F063, F064 8 F065.

UPGRADE PREPAREDHESS - UPGRADE EMERGENCY PLANS TO APP. E. 10 CFR 50.

UPGRADE PREPAREDNESS - METEOROLOGICAL DATA.

PRIMARY COOLANT OUTSIDE COHTAINMENT - LEAK REDUCTIOH.

PRIMARY COOLANT OUtSIDE CONTAINMENT -

TECH SPECS.

INPLAHT RAD. MONIT. - PROVIDE MEANS TO DETER.

PRESENCE OF RADIOIODINE.

IMPLANT RADIATION MONIT. - MODIFICATIONS TO ACCURATELY MEAS.

IODINE'ONTROL ROOM HABITABILITY-REVIEll.

CONTROL ROOM HABITABILITY-SCHEDULE HCOIFICATIONS.

CONTROL ROOH HABITABILITY-IMPLEMENT MODIFICATIONS.~.

I.D ~ 1.1 DETAILED CONTROL ROOM DESIGN REVIEll PROGRAM PLAN.

~

III.A.1.2 TECHNICAL SUPPORT CENTER.

III.A.1.2 OPERATIONAL SUPPORT CENTER.

I II.A.1.2 EMERGENCY OPERATIOHS FACILITY~

I.D.1.2 DETAILED CONTROL ROOM REVIEll (FOLL(MJP TO F 8).

NUREG-0737 TECH SPECS (GENERIC LET'TERS 82-16 8 83-02)

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

REACTOR COOLANT PUMP TRIP (GEHERIC LETTER 85-12)

C; SER 9/29/86 C;

SER 9/29/86 Cl 10/24/88 C;

SER 5/13/83 C;

SER 10/22/87 C;

SER 8/25/81 C;

SER 8/25/81 C;

SER 2/19/82 C;

SER 2/19/82 C;

SER 2/11/82 C;

H 12/31/82 C;

H 12/31/82 C;

SER 6/01/87 CI SER 9/29/86 CI SER 9/29/86 C;

SER 9/29/86 H

12/31/90 Cl SER 11/23/83 H T/S R 10/26/87 C;

SER 7/13/88 0

l 4

1 c

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