ML17251A452

Responds to 890414 Request for Info Re Implementation Status of TMI Action Plan Items at Facility to Meet NUREG-0737 Requirements.Printout Encl

ML17251A452
Person / Time
Site:	Ginna
Issue date:	04/18/1989
From:	Rich Smith ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8904270351
Download: ML17251A452 (16)

Text

1 DJSABt'TJO;t DEMONSTRATOR SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8904270351 DOC.DATE: 89/04/18 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION SMITH,R.E.

Rochester Gas 6r Electric Corp.

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

SUBJECT:

Responds to TE Murley 890414 request for info re status of implementation of TMI action items to meet NUREG-0737.

DISTRIBUTION CODE:

A046D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal:

TMI Action Plan Rgmt NUREG-0737 6 NUREG-0660 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 8 RECIPIENT ID CODE/NAME PD1-3 LA STAHLE,C INTERNAL: AEOD/DSP/TPAB NRR/DEST/MEB 9H NRR/DREP/RPB 10 OC E(YT E

01 ES/DSR DEPY,'XTERNAL:

LPDR NSIC COPIES LTTR ENCL 1

0 1

1 1

1 1

1 1

1 1

0 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DEST/ADS 7E NRR/DREP/EPB 10 NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB NRC PDR COPIES LTTR'NCL 5

5 1

0 1

1 1

1 1

0 1

1 h

R I

MIX 'IO ALL "RIDS" RECIPIENIS'IZASE HELP US TO REDl:JCE WASTE)

CXNZACI'IHE DOCUMENI'ONGEAL DESK BOOM Pl-37 (EXT. 20079)

IO ELDG2QTE K%JR NME FRY DISTVG33UTIQN LISTS FOR DOCUMENIS YOU DGNiT NEED)

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 21 ENCL

'17

EEiE~II/////ENlrir

/

iurrsP~IE i zz(sieve 8Z.,

70RK ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N. Y. 14649.0001 ROBERT E. SMITH Vice President Production end Engineering April 18, 1989 TELEPHONE AREACOOEtte 546 2700 U.S. Nuclear Regulatory Commission Attn: Document. Control Desk Washington, D.C.

20555

References:

a) License No.

DPR-18 (Docket No. 50-244) b) Letter from Thomas E. Murley (NRC) to Robert C. Mecredy (RG&E), dated April 14, 1989 Licensee's Implementation of Action Items to Meet Requirements of NUREG-0737 and NUREG-0737 Supplement 1

Gentlemen:

By letter from Thomas E.

Murley (NRC) to Robert C.

Mecredy (RG&E), dated April 14, 1989 you requested. information regarding the status of implementation of TMI action items necessary to meet the requirements of NUREG-0737 and NUREG-0737 Supplement 1.

The attachment to the April 14 letter has been marked to show the implementation status as requested and.

is enclosed with this letter.

Within the time allowed, it was our desire to be as responsive as possible while making a best attempt to ensure the accuracy of information at the required level of detail.

Because of the short period given to search our records, unintended reporting inaccuracies may have been introduced.

In doing. our search, we followed your guidelines to show an item as complete when changes have been implemented and no further action is required, to the best of our knowledge, on the part of the licensee.

This response is provided for information. only to give our understanding of the completion of these issues.

It should not be construed as a

commitment to any new action or interpretation.

For specific commitments and schedules, refer to correspondence addressing specific topics or requests.

Very truly yours, obert~E.

Smith,

~~

7 JPO~036 Attachments 8904270351 S90418 PDR ADOCK 05000244 P

PDC

xc:

Richard H. Wessman Project Directorate I-3 Washington, D.C.

20555 Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

NOTES Issue ¹ I.D. 1 Most items completed earlier as described. in RG&E letter dated July 14, 1987.

Last modifications to be completed during the 1989 refueling outage as described in RG&E letter dated December 15, 1987.

II.K.3.5.A RG&E response to Generic Letter 85-12 by letter dated August 19, 1985.

NRC responded by'letter dated April 15, 1986 with preliminary review to be followed up with a telephone conference call.

Conference calls that were scheduled have been cancelled at NRC request.

Awaiting NRC to set up conference call.

III.A.1.2 III.A.2.'2 RG&E proposed program and implementation schedule by letters dated July 1, 1981 and June 11, 1982.

Program was implemented and described in RG&E letter dated November 23, 1988.

NJLTI-PLANT ISSuz NUMBER ACTION im.

ISSUE TITLE LICkHSEE IHPLElIENTATIGNSThTUS I - A. 1. l. 1 "I.A. l. 1. 2 "I. A. 1. l. 3 "I.A.1. 1.4 l.A.l.2 I.A.1.3.1 I.A. 1.3.2 I. A. 2. l.l I.A 2 ~ 1.2 I. A. 2. l. 3 I. A. 2. l. 4 I. A. 2. l. 5 I. A.2. 3 I.A.3.1.1 I.A.3.1.2 I. A. 3. 1.3.A l. A. 3. l. 3. B "l.B. 1.2 I.C. l. l

l. C. 1.2.A

l. C.1.2oB

l. C. 1.3.A I.C. l. 3.8 I. C.2 I. C.3 I.C.4 I.Co5 I. C.6 "1.C. J. 1 "I.C.7.2 "I.C.a I.O. 1 (See

f. I). 2. 1 F001 F002 f002 F603 F004 F004

.F005 F005 F006 F007 FOOS 5 F071)

F009 SHIFT TECHNIChL ADVISOR " ON DUTY......,.

SHIFT TECHHIChL ADVISOR " TECH SPECS.....

SHIFT TECHNICAL ADVISOR " TRAINED PN LL CAT B.

SHIFT TECHNICAL ADVISOR DESCRISE UWG TERM PROGRAM..................

'sl-,'....

SHIFl SUPERVISQR RESPONSIBILITIES.....

SHIFl HANNIHG - LNIT OVERTINES..........

SHIFl HANHIHG " HIH SHiFT CRN.........

IHKPIATE UPGRADING OF RO 8 SRO TRhilliHG AND EQUAL. - SRO EXPER.....

INSlIATE IjPGRAOING OF RO 4, SRO TRAINIHG AND EQUAL. - SRO'S BE RO'S lYR......

INKljlIATEUPGRADIHG OF RD 4 SRO TRhllilHG AHD EQUAL. - 3 MD. TRAINIHG E~IIATE UPGRADNG DF RQ 4 SRO TRAIHIHG AHD EQUAL. - HODIFY TRAINING..............

INKflIATEUPGRADIHG OF RO 4 SRO TRAIHIHG AND EQUAL. - FACILITY CERTIF.......

NNIfIISTRATIOIlIOF TRhINIHG PRGGRAHS REVI-'iE SCOPE 4 CRITERIA FOR LICEHSIHG EXAHS - 'INCREASE SCOPE.........

+<C..

REVI~iE SCOPE 4 CRITERIA FOR LICENSIHG EXAHS NCREASE PASSING GRADE..........HJ.~..

REVE,'E SCOPE 4 CRIT.

FOR LIC.

EXAHS - SIMULATOR PLANTS 'ARITH SNULATORS................<J<...........................:..

=

REVPiE SCOPE 4 CRIT.

FOR LIC.

EXAHS - SIMULATOR - OTHER PLANTS.......

N<

EVALUATIONOF ORGANIZATION 4 NAHAGNEHT.

SHORT-TERH ACCIDENT 8 PROCEDURES REVIEW -

SB LOCA.

SHO

-TERN ACCID. 8 PROCEDURES REV.

INADEPT.

CORE CODL.

REANAL. GUIDELINES.........;.~.......-...-..........-........

SHOR =TERH ACCID. 4 PROCElNRES REV. INADEq.

CQRE CQOL.

REVISE PIWCEDURES.................

SHOR =TERH ACCID. 4 PROCEINRES REV - TRANSIENTS 8 ACCOTS.

RENAL GUIOELINES (PROC.

GEH. PKG.).

SNN "TEHH ACCIO. 5 PROCElNRES REV.

TRANSIENTS L ACCDRS.

REVISE PROCEDURES (IlPGRADED EOP'S}...<.

SHI 4 RELIEF TURNOVER PROCEOURES

~

o o ~ \\ o ~ ~ o o

~ o

~

~ o

~ ~ ~

~

~ o

~ ~

o

~

~ ~

~ o

~

~ ~ ~ ~ ~

G QB

=StlPERVISOR RESPONSIBILITY...

~

~

~ ~

o ~ ~ ~ o ~

~

~

~

~ ~ ~ ~

~ ~ ~ o ~

~

o o ~

~ o ~

~

o C

CONT QL-ROOH ACCESS

~ O ~ ~ o o o

~ o ~

o o o o o o o

~

o FEED/ACK OF OPERATING EXPERIENCE........

~ ~ o

~ oo ~ oo ~

~ ~ ooooo

~ ooG0

~ o

~

~

~

~

~

VERlrY CORRECT PERFORHANCE OF OPERATENG ACTIVITIES........,....................................

NSSS.'VEiaOR REV.

OF PROC " LS NMER TEST PROGRAH.

.......................... J...

Rim HSSS'VENDOR REV.

OF PROC " OER ASCENSION 8 BIER. PROCS................................I...

pe PILol NN OF SELECTFO EHERGNCY PROC FOR NTOLS

~ ~ ~ o o o ~ ~

O

~ i ~

o ~ o (o ~ o

~

~

~

CONT>SL-RN DESIGN REVINS (ENTER DATA FOR MPA F008 5 NPA F-071}......-....-

~ -- ~ ----~

~

CeE eoz-x-l.1 PLAHt-SAFETY PhRAHETER DISPLAY CONSOLE DESCRIPTION.

C, I

I g II C,

4 c

I IP

~ ~

y le r

l eO.

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE LICENSEE IHPLEHENTATION STATUS I I. E. l. 2. l. A I I. E. 1. 2. 1. B I I. E. l. 2. 2. A "II. E. l. 2. 2. B "tI. E. 1. 2. 2. C "II. E.3.1. 1 "II..E. 3. l. 2 I l.E.4.1.1

• II. E.4.1.2 A I I. E. 4. l. 3 I I. E. 4. 2. 1-4 A I I. E. 4. 2. 5. A

• I I. E. 4. 2. 5. B I I. E. 4. 2. 6 I I. E. 4. 2. 7 "II. E. 4. 2. 8 "II. F. 1'. 1

• II. F. l. 2. A "II. f. l. P. B

• II. F. l. 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

'" l I. F. 2. 3 "t I. F.2.4

• I1.G. l. 1 "II. G. l. 2 I I. K. I (Oper.

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

AFS INITIATION8 FLOW-CONTROL GRADE AFS INITIATION 8s FLOW - SAFETY GRADE AFS INITIATION8I FLOW -

FLOW INDICATION CONTROL GRADE.......................'=.......

AFS INITIATION8I FLOW - LL CAT A TECH SPECS..

AFS INITIATION8 FLOW - SAFETY GRADE EMERGENCY POWER FOR PRESSURIZER HEATERS -

UPGRADE POWER SUPPLY..................

C.

EMERGENCY POWER FOR PRESSURIZER HEATERS -

TECH SPECS.

DEDICATED HYDROGEN PENETRATIONS DESIGN.

DEDICATED HYDROGEN PENETRATIONS -

REVIEW 8 REVISE H2 CONTROL PROC DEDICATE0 HYDROGEN PENETRATION INSTALL........................................N(c....

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

.C.

CONTAINMENT ISOLATION DEPENDABILITY - RADIATION SIGNAL ON PURGE VALVES C

CONTAINMENT ISOLATION OEPENDABLITY - TECH SPECS ACCIDENT - MONITORING PROCEDURES C'

ACCIDENT - MONITORING - NOBLE GAS MONITOR.

ACCIDENT - MONITORING - IODINE/PARTICULATE SAMPLING..

ACCIDENT - MONITORING - CONTAINMENT HIGH-RANGE MONITOR.

C ACCIDENT - MONITORING - CONTAINMENT PRESSURE..

ACCIDENT - MONITORING CONTAINMENT WATER LEVEL C

ACCIDENT MONITORING CONTAINMENT HYDROGEN..

C INSTRUMENTATION FOR DETECT.

OF INADE(UATE CORE COOLING " PROCEDURES..

.INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE COOLING - SUBCOOL METER.

INSTRUMENTATION FOR DETECT.

OF INADE(UATE CORE COOLING - DESC.

OTHER.

INSTRUMENTATION FOR DETECT.

OF INADEQUATE CORE CLING INSTLL ADD'L INSTRUMENTATION.

POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8 LEVEL IND. -

UPGRADE.

POWER SUPP.

FOR PRESSURIZER

RELIEF, BLOCK VALVES 8I LEVEL IND. - TECH SP..................

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

~

~

~

~ ~

~

~

~ ~ ~

~

o Jo

~

~ ~

~ ~ ~

~

~ 4

~

~

~

~ ~

~ $ ~ ~ ~ ~

~

~

~ ~

~ ~ ~

~

~

I

~

~

~ ~

~

~

~

~

~

~ 0

~

~

~ ~

~ ~ ~

~

~ \\ ~

~

I

~

J

~

~ ~

~

~

I

~ f~

~

~

~

~

~

~

~

l

~

~

~

~ ~

~

~ ~ ~

~ ~

~

~ ~

~

~

~

"~

g H

A ~

E II

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE L'ICENSEE IMPLEMENTATION STATUS "11. K. l. 5

• II. K. l. 10 "II. K. l. 20 "II. K. l. 21 "II. K. l. 22 "II. K. l. 23

• II. K. 2. 2 "II. K. 2. 8 I I. K. 2.9 I I. K. 2. 10 "II. K. 2. 11 I I. K. 2. 13 I I. K. 2. 14 I I. K. 2. 15

11. K. 2. 16 I I. K. 2. 17

11. K. 2: 19 "11. K. 2. 20 "II. K. 3..l. A "II. K. 3. 1. B

11. K. 3. 2-l 1. K. 3. 3 I I. K. 3. 5. A I I. K. 3. 5. B

11. K. 3. 7 I I. K. 3. 9 I I. K. 3. 10

11. K. 3. 11 t I. K. 3. 12. A I I. K. 3. 12. B I I. K. 3. 13. A I I. K. 3. 13. B F027 F028 F029 F030 F031 F032 F033 F035 F036 F037 F038 F039 F039 F040 F041 F042 F043 F043

'If BULLETINS - RfVIEW ESF VALVES......

IE BULLETINS - OPERABILITY STATUS IE BULLETINS -

PROMPT MANUAL REACTOR TRIP..

IE BULLETINS - AUTO SG ANTICIPATORY REACTOR TRIP If BULLETINS - AUX. HEAT REH SYSTEH, PROC.

IE BULLETINS -

RV LEVEL, PROCEDURES...

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

ORDERS ON B8iW PLANTS -

PROCEDURES TO CONTROL AFW IND OF ICS ORDERS ON B8W PLANTS -

UPGRADE AFW SYSTEM.

ORDERS ON B8W PLANTS -

FEMA ON ICS ORDERS ON B8W PLANTS SAFETY-GRADE TRIP.

ORDERS ON 88W PLANTS OPERATOR TRAINING.

ORDERS ON B8W PLANTS - THERMAL MECHANICAL REPORT (CE & W PLANTS ALSO).

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

ORDERS ON B8W PLANTS - EFFECTS OF SLUG FLOW.

ORDERS ON B&W PLANTS -

RCP SEAL DAHAGf ORDERS ON B&W PLANTS - VOIDING IN RCS (CE 8c W PLANTS ALSO)

BENCHMARK ANALYSIS OF SEQUENTIAL AFW FLOW TO ONCE THROUGH STM GENERATOR ORDERS ON B8W PLANTS SYSTEM RESPONSE TO SB LOCA.

B80 TASK FORCE - AUTOMATIC PORV ISOLATION DESIGN.

FINAL RECOMMENDATIONS, B80 TASK FORCE - AUTO PORV ISO TEST/INSTALL.

B80 TASK FORCE -

REPORT ON PORV FAILURES B80 TASK FORCE REPORTING SV 8

RV FAILURES AND CHALLENGES B80 TASK FORCf AUTO TRIP OF RCP'S PROPOSED MODIFICATIONS B80 TASK FORCf AUTO TRIP OF RCP'S MODIFICATIONS B80 TASK FORCE - EVALUATION OF PORV OPENING PROBABILITIES B80 TASK FORCE - PID CONTROLLER MODIFICATION.

B80 TASK FORCE -

PROPOSED ANTICIPATORY TRIP MODIFICATIONS B80 TASK FORCE - JUSTIFY USE OF CERTAIN PORV B80 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP PROPOSED MOOS.

B80 TASK FORCE - ANTICIPATORY TRIP ON TURBINE TRIP INSTALL MODS.

B80 TASK FORCE - HPCI 8i RCIC SYSTEM INITIATION LEVELS ANALYSIS.

B&0 TASK FORCE - HPCI 8

RCIC INITIATION LEVELS MODIFICATION.

~

~

~

~

~

~

~

~

~

~

~

~

~

I jg(jL C

0/A il)A

~

~

~

~

~

~

~

~

Cc C

C S6< N~<<

)

e

~

~

~

~

~

C hl/P NJA C

G p)jp yfp

~

~

~ ~

~

~

1

~ ~ ~ ~ 1 ~ ~ ~ ~ \\ ~

~ 0 ~

t

~

~

~

~ ~

~

~ 0

~ ~

~ ~ ~ ~ ~

~ ~

~

~

~

~

~

N t

~

~

~ ~

~ 1

~

~

~ ~

~

~

~

~

~ '

Pi,%,3 ~ 5

~

~

~

~

~

~

~

~

~ ~

~

~

~

~ ~ ~ t ~ o o ~

~ ~ o ~

~

u'

~'II If f

ISSUE NUMBER MULTI"PLANT ACTION,NO.

ISSUE TITLE l

LICENSEE IMPLEMENTATION STATUS A I I. K. 3. 14 I I. K. 3. 15 I [. K. 3. 16A I I. K. 3. 16. B I I. K. 3. 17 I I. K. 3. 18. A

=- I I. K. 3. 18. B II. K. 3. 18; C

"!I. K.3.19 "II. K. 3. 20 I I. K. 3. 21. A I I. K. 3. 21. B I I. K. 3. 22. A

11. K. 3. 22. B I I. K. 3. 24

11. K. 3. 25. A I I. K. 3: 25. B I I. K. 3. 27 I I. K. 3.'28

• I I. K. 3. 29 I I. K. 3. 30. A

[ [. K. 3. 30. B I I. K. 3. 30. C I I. K. 3. 31 A I I. K. 3. 40 "II. K. 3. 43 I I. K. 3. 44 I I. 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

~B&0 TASK FORCE B80 TASK FORCE B80 TASK FORCE B&0 TASK FORCE B80 TASK FORCE B&0 TASK FORCE B80 TASK FORCE B80 TASK FORCE B&0 TASK FORCE B&0 TASK FORCE B80 TASK FORCE B&0 TASK FORCE B80 TASK FORCE B80 TASK FORCE B8(0 TASK FORCE B8(0 TASK FORCE B&0 TASK FORCE B80 TASK FORCE B&0 TASK FORCE B80,TASK FORCE B8(0 TASK FORCE B80 TASK FORCE B80 TASK FORCE B80 TASK FORCE B80 TASK FORCE B80 TASK FORCE B80 TASK FORCE B&0 TASK FORCE

RESPONSE

TO LIS IDENTIFY WATER EMERGENCY PREPA ISO CONDENSER ISOLATION ON HIGH RAD..

MODIFY HPCI & RCIC BRK DETECTION CIRCUITRY.

CHALLENGE 8 FAILURE OF RELIEF VALVES STUDY.......

CHALLENGE & FAILURE OF RELIEF VALVES MODIFICATIONS.......

ECC SYSTEM OUTAGES.

ADS ACTUATION STUDY.

ADS ACTUATION PROPOSED MODIFICATIONS ADS ACTUATION MODIFICATIONS INTERlOCK RECIRCULATORY PUMP MODIFICATIONS............

LOSS OF SVC WATER AT BRP RESTART OF CSS 8

LPCI LOGIC DESIGN....

RESTART OF CSS

& LPCI LOGIC DESIGN MODIFICATIONS RCIC SUCTION VERIFICATION'ROCEDURES RCIC SUCTION MODIFICATION..

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

POWER ON PUMP SEALS PROPOSED MODIFICATIONS POWER ON PUMP SEALS MODIFICATIONS COMMON REFERENCE LEVEL FOR BWRS..

QUALIFICATION OF ADS ACCUMULATORS PERFORMANCE OF ISOLATION CONDENSERS SCHEDULE FOR OUTLINE OF SB LOCA MODEL SB LOCA MODEL, JUSTIFICATION.

SB LOCA METHODS NEW ANALYSES COMPLIANCE WITH CFR 50.46.

RCP SEAL DAMAGE -

COVERED BY II.K. 2. 16 AND II.K.3.25 EFFECTS OF SLUG FLOW -

COVERED BY II.K. 2. 15.

EVALUATE TRANSIENT WITH SINGLE FAILURE ANALYSES TO SUPPORT OF CONCERNS FROM ACRS CONSULTANT.

URCES PRIOR TO MANUAL ACTIVATION OF ADS...............

~..

DNESS, SHORT TERM...

T SO RE

~

~

~

~

~

~

~

g]G Hh NA

~

~

~

~

~

~

~

~

~

~

~

~

~

a a

~N C

~

~

~

. yQ.

~

~

AP

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

pJ(ll

~

~

~

~

~

~

~

~

~ ~ ~ ~ ~ ~ ~ ~ ~

~

~

~

~

~

(

~

~

~

~

~ ~

~ ~ ~ ~

~

~

~

~

~

~ r rr

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

a

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

I~e o-i ~ or(

~

~

~

~

~

~

~

~

~

~

~

~

~

~ r

~

~

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~

~

~E

~

~

~

I E

I I

I ~

4 ~

~ E

~

~

~

~ 4

MULTI-PLANT ISSUE NUMBER ACTION NO.

ISSUE TITLE

, LICENSEE'MPLEMENTATION STATUS I I I. A. l. 2. 1 I II. A. 1. 2. 2 (SEE F063, I I I. A. 1. 2. 3 (SEE F063, III.A.2.1

~~III.A.2.2 "III. D. l. l. 1 "111. D. l.l. 2 I I I. D. 3. 3. 1 I I I. D. 3. 3. 2 III. D. 3. 4. I

• III. D. 3.4. 2 A I II. 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 8072 B083 Gool

'PGRADE EMERGENCY SUPPORT FACILITIES - INTERIM TSC OSC & EOF UPGRADE EMERGENCY SUPPORT FACILITIES-DESIGN-INCORP.

INTO F063/F064/F065.

UPGRADE EMER SUPPORT FACILITIES " MOOS INCORPOR.

INTO F063, F064 & 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. " MODIFICATIONS 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. 1. 2 EMERGENCY OPERATIONS FACILITY.

I. D. 1. 2 DETAILED CONTROL ROOM REVIEW (FOLLOWUP TO F-8).

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

TECH SPEC COVERED BY GENERIC LETTERS 83-26

& 83-37 FOR NUREG-0737.

REACTOR COOLANT PUMP TRIP (GENERIC LETTER 85-12)

C.

(fC'6 goyK ll'I.A.L.L)

(,zm Nige

>i>.P-l. 2)

~

~

~

~

~

~

~

~

~

~ ~ ~ ~ ~ ~

~

~ ~

~

~

~ ~

~

~

~

~

~

~

~ ~

C Z'NG plo~~

1%V +. ~, L)

I

~

~

~

~ t ~

~

~ ~ ~

~ ~ ~ ~

~

~

~

~

~

Se:8, pope

~. b.

1

~

~

~

~

~

~ 4

~ ~

~

~ ~

~

~

~

~

~I

~

~

~

~

~

~

~

~

~

~

~

( <fi'P Te

~ t

~

~

~

~

~

~

~

~

~

~

~

~ T

~

C'l T. b ~ I

~

~

~

~

~

~;

~

~

~

~

~

~

~ ~

~

~

~

~

~

~

~

~ ~ ~ 4

~ ~ ~

~

C-

~

~

~

~

~

~

~

~

~

~

~ ~

~

~

1 ~

~

~

~

~

~

~

I

I

~

~

t H

4 il O

~.