ML17325A393
| ML17325A393 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/27/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-***, TASK-A-36, TASK-OR, TASK-TM AEP:NRC:0994, AEP:NRC:994, NUDOCS 8711020303 | |
| Download: ML17325A393 (14) | |
Text
REGULATOR NFORMATION DISTRIBUTION S TEM (RIDS)
ACCESSION NBR: 8711020303 DOC. DATE: 87/10/27 NOTARIZED:
NO DOCKET 0 FACIL: 50-315 Donald C.
Cook Nuclear Poeer Planti Unit 1>
~u 05000315 50-316 Donald C.
Cook Nuclear Poujer Plant'nit 2i Indiana 8c 05000316 AUTH. NAME
'AUTHOR AFFILIATION ALEX ICHOR M. P.
Indiana h Michigan Electric Co.
RECIP. NAME RECIPIENT AFFILIATlON MURLEYiT. E.
Document Control Branch (Document Control Desk)
SUBJECT:
Forujards updated table of plant action items e/revised implementation dates. Requests correct TAC numbers for each listed item in next safety issues mgt sos transmittal.
DISTRIBUTION CODE:
AOOSD COPIES RECEIVED: LTR I
ENCL l
SIZE:
TITLE: OR/Licensing Submittal:
Supp 1 1 to NUREG-0737(Generic Ltr 82-33)
NOTES:
RECIPIENT ID CODE/NAME PD3-3 LA MIGGINGTONi D INTERNAL:
/LFMB REG FIL 01
/EIB COPIES LTTR ENCL 1
1 1
1 1
0 1
1 1
RECIPIENT ID CODE/NAME PD3-3 PD NRR/DLPG/HFB RES DEPY GI COPIES LTTR ENCL 7
7 1
1 1
EXTERNAL:
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 17 ENCL ih
Indiana Michigan Power Company One Summit Square P.O. Box 60 Fort Wayne, IN 46801 219 425 2111 AEP:NRC:0994 Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 NRC UPDATE ON ACTION ITEMS U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley October 27, 1987
Dear Hr. Murley:
Attached is a list of action items that is based on the NRR's Safety Issues Management
- System, which includes open and closed items for the Cook Nuclear Plant.
As agreed at the August 19, 1987 meeting with our Project Manager, Mr. D. L. Wigginton, we are submitting the attached list with revised implementation dates.
It was also agreed at the meeting that AEPSC would initiate a system that would cross-reference our AEP:NRC numbers with the NRC "tac" numbers.
In order to continue with this system, please provide us with the correct NRC tac numbers for each of the items on the attached list in the next transmittal of the Safety Issues Management System.
We believe this will facilitate communications between AEPSC and the NRC.
The system will begin tracking items that have been closed out in 1986 or later in order to limit the scope of the items covered.
We believe that the transmittal of the enclosed list fulfills our commitments to initiate this system and to revise the implementation dates included in the list.
In our letters AEP:NRC:07730, dated October 15,
- 1985, and AEP:NRC:0773S, dated June 29,
- 1987, we provided a schedule for completing Regulatory Guide (R.G.) 1.97 items.
Due to other activities which we did not anticipate at the time these letters were transmitted (such as the rescheduling of the Unit 2 refueling outage due to the steam generator repair project),
we find it necessary to update our schedule for completion of R.G.
8yi>0P0303 8710>>
PDR ADOCK 05000315 P
gpss
~ i(r
Dr. T.
E. Murley AEP:NRC:0994 1.97 items.
The dates given here for Units 1 and 2 are based on our current schedule for completing the R.G. 1.97 items and supersede other earlier dates we may have transmitted on this subj ect.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M.
. Alexich Vice President Attachment cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
~
~
'~
0 Attachment to AEP:NRC:0994 Table of D.
C.
Cook Nuclear Plant Action Items
Attachment to AEP:NRC:0994 Key to Table AEP File Numbers NRC Numbers AEP letter number to NRC.
NRC method of tracking issues Eventually intended to be all tac numbers.
Applicable Issues IMPO.INIT.
Short description of item.
Imposition Initiated either by NRC request or AEP request for that Action item.
IMPO.COMP.
Imposition Complete and indicates NRC licensing action is done.
IMPL.COMP.
Implementation Complete indicates the item is complete and implemented at the plant, i.e.,
we are prepared for an inspection on this item.
oo/yr.
Indicates sometime in that year.
Specific date currently not possible to define.
Complete NRC internal date which may require updating.
Open Action dependent upon NRC action which has not yet been completed.
NRC's best guess as to when implementation will be completed.
L or no symbol in IMPL column AEP established the date
- Requires AEP to advise NRC of change.
ATTACHHENT -
SAFETY ISSUES HANAGEHENT SYSTEM STARTING IN 1986 FOR COOK NUCLEAR PLANT Page 1
~
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IHPO.
INIT.
IHPO.
COMP.
IMPL.
COMP.
NUREG-0737 0773S MPA-F-99 67.3 3
ALL TMI ITEMS COMPLETE REG.
GUIDE 1.97 IMPROVED ACCIDENT MONITORING UNIT 1 REG.
GUIDE 1.97 IMPROVED ACCIDENT MONITORING UNIT 2 07/86C 04/83C 05/87C 12/87 00/90 00/89 00/90 0785C 0838U 67.4.1 75 (B-77)
RCP TRIP ITEM 2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE 02/83C 11/83C 09/87>>
04/87C 11/87 05/87C 0838M 0838S 75 (B-81) 75 (B-85)
ITEMS 4.2.1 AND 4.2.2 SALEM ATWS 1.2 POST TRIP REVIEW DATA CAPABILITY 11/83C 11/84C 05/85C 08/87*
10/86C OPEN 0838AB 0838K 0838X 0838A 0895D 75 (B-86) 75 (B-87) 75 (B-89) 75 (B-90)
SALEM ATWS 2.2 SAFETY-RELATED COMPONENTS SALEM ATWS 3.2.1 AND 3.2.2 SAFETY RELATED COMPONENTS SALEM ATWS 4.2.3 AND 4.2.4 LIFE COMPONENTS SALEM ATWS 4.3 W AND B&W T.S.
11/84C 11/84C 11/84C 07/84C OPEN 04/87C OPEN 12/86C OPEN+2 12/87L OPEN+2 02/87C NRC DATE
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IMPL.
COMP.
Page 2
0838Y 0514U 0678 OR 0856 0678 OR 0856 75 (B-93)
A-36 (C-10)
I.A.2.2 INPO I.A.2.7 INFO I;C.1.2.A F-04 SALEM ATWS 4.5.2 AND 4.5.3 TEST ALTERNATIVE CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL TRAINING AND QUALIFICATIONS OF OPERATING PERSONNEL ACCREDITATION OF TRAINING INSTITUTIONS SHORT-TERM ACCIDENT AND PROCEDURES REVIEW:
INADEQUATE CORE COOLING, REANALYZE AND PROPOSE GUIDELINES 11/84C 08/77C 03/85C 03/85C 04/81C OPEN 09/83C NA NA 06/84C OPEN 05/88 11/87R 11/87R 05/86C I.C.1.2.B F-05 I.C.1.3.A F-04 SHORT-TERM ACCIDENT AND
,PROCEDURES REVIEW: INADEQUATE CORE COOLING, REVISE PROCEDURES (FOR UNIT 2:)
SHORT-TERM ACCIDENT AND PROCEDURES REVIEW: TRANSIENTS AND ACCIDENTS, REANALYZE AND PROPOSE GUIDELINES 04/81C 04/81C 05/87C 06/84C 03/86C (06/86C) 05/86C 0678Y 0585J
~NRC DATE I.C.1.3.B F-05 II.B.3.4 F-12 II.D.1.2.B F-14 SHORT-TERM ACCIDENT AND PROCEDURES REVIEW: TRANSIENTS
& ACCIDENTS, REVIEW PROCEDURES (FOR UNIT 2:)
POST ACCIDENT SAMPLING-PLANT MODIFICATIONS RELIEF AND SAFETY VALVE TEST REQUIREMENTS 04/81C 04/81C 12/83C 05/87C 04/85C 09/87*
03/86C (06/86C) 01/88
- 11/87
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IMPL.
COMP.
Page 3
0856G 0856G 0856G 0856T 0761F 0999B 0398C 0398M 0916Z 0500S 0433K 0692AP II.F.1.2.A F-20 II.F.1.2.B II.F.1.2.C F-22 II.F.1.2.E F-24 II.F.2.4 F-26 III.A.2.2 F-68 III.D.3.4.1 F-70 III.D.3.4.2 F-70 II.K.3.31 M49520 M49519 M51602 M51603 M55809 M55810 ACCIDENT-MONITORING-NOBLE GAS MONITOR ACCIDENT-MONITORING-IODINE/
PARTICUIATE ACCIDENT-MONITORING-CONTAINMENT HIGH-RANGE ACCIDENT-MONITORING-CONTAINMENT WATER INSTRUMENTATION FOR DETECTION OF INADEQUATE CORE COOLING UPGRADE PREPAREDNESS METEOROLOGICAL CONTROL ROOM HABITABILITY-REVIEW CONTROL ROOM HABITABILITY-SCHEDULE MOD FINAL RECOMMENDATIONS, B&0 TASK FORCE - COMPLIANCE WITH CFR 50.46 (UNIT 1)
HYDROGEN CONTROL FINAL RESOLUTION SURVEILLANCE REFERENCE TO 4.0.5 FIRE EXEMPTIONS PART 2 CARPETS 04/81C 04/81C 04/81C 01/82C 04/81C 09/83C 04/81C 04/81C 04/82C 01/83C 05/83C 05/86C 05/83C 05/83C 02/82C 06/83C 04/87C 08/87*
02/82C 02/82C 12/86C 12/89 07/86C OPEN 01/88 09/87C 00/90R 00/89L 00/89+
06/88L 06/88L 00/91L 12/86C 00/90R 10/86C OPEN+2
'NRC DATE
+COMPLETION DATE DEPENDENT ON THE STEAM GENERATOR REPAIR PROJECT
AEP FILE NUHBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IHPL.
COMP.
Page 4.
0692AN 0137G M55809 M55810 M55819 FIRE EXEMPTIONS PART 2 HATCH EXEMPTION FOR ASYMMETRIC LOADS 03/84C 09/84C OPEN 11/85C OPEN+2 11/85C 0433J 0895H 0856 0514N H56242 M56243 M56440 M56441 M57680 M57681 M59676 M59675 VALVE TESTING MODS TO TECH SPEC RCP IN MODE 3 AUXILIARYFEEDWATER PUMPS 83-37 HEAVY LOAD MOD FOR CRANE LOAD (15 FEET ISSUE) 10/84C 12/84C 04/85C 09/85C 04/86C 02/87C 12/85C 02/86C 06/86C 02/87C 02/86C 5/88L 0969H M60029 M60029 2ND 10 YEAR ISI/IST 10/85C OPEN OPEN 0895D 0956B 0960D 0960E 0975C H60574 M60575 M60576 M60577 M60835 M60836 M61004 M61005 M61474 M61475 BYPASS BREAKERS AND P8 RADIATION MONITORS HOURLY FIRE WATCH PATROLS MANUAL OPERATION SPRAY ON FILTER OUTSIDE TANKS 01/86C 12/86C 01/86C 04/86C 03/86C 06/86C 04/86C 11/86C 02/86C 07/86C 02/87C 06/86C 10/86C 09/86C 01/87C A'NRC DATE
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IMPL.
COMP.
Page 5
0960F 0931C 0678Z 0969B 0967E 0936H 1015A 1016A 0514S 0896F 0940E 0967K 1018C M61688 M61689 M62242 M62243 M62816 M62817 M63440 M63441 M63452 M63947 M63948 M64161 M64335 M64336 M64384 M64385 M64515 M64516 M64575 M64658 M64773 CONTINUOUS FIRE WATCH BASES CHANGE SNUBBER CORRECTIONS MAIN STEAM NOBLE GAS EXEMPTION RHR VALVE TEST RELIEF 2ND SURVEILLANCE EXTENSION INTEGRITY VS.
OPERABLE FOR STEAM QUADRANT POWER RATIO LIMITS (UNIT 1)
FUEL WEIGHT CRANE LOAD REVIEW (LOAD BLOCK ANALYSIS)
D.
G. RELIABILITY K(Z) FOR EXXON FUEL (UNIT 1)
ICE CONDENSER TEST EXTENSION (UNIT 1)
INCREASED PEAK PELLET EXPOSURE (UNIT 1) 05/86C 08/86C 09/86C 10/86C 10/86C 11/86C 12/86C 12/86C 01/87C 01/87C 01/87C 02/87C 02/87C 07/86C 04/87C 09/87*
12/86C 12/86C 04/87C 04/87C 03/87C 11/87 10/87*
06/87C 05/87C 05/87C 10/86C 05/87C 11/87 01/87C 02/87C 04/87C 05/87C 04/87C 05/88 01/88 09/87C 06/87C 06/87C
%NRC DATE
4
~
(
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IMPL.
COMP.
Page 6
0900G 0692AY 1024 0916W 0916W 0678D 0514T 0838AA 0561 0773K 0773K M64795 M64796 M64946 M64947 M64962 M64963 M65039 M65040 M65041 M65042 M65058 M65113 M65114 MPA-A-20 MPA-A-21 MPA-F-63 MPA-F-64 LOWER INLET DOORS OUTDOOR LIGHTING EXEMPTION TWO-LOOP SI BASIS CYCLE 10 AND RELATED UNIT 2 FOR UNIT 2 FUELS UPDATE TO UNIT 2 AND SPING 3/4 FLOW AND CALIBRATION (UNIT 1)
AUXILIARYBUILDING CRANE REVIEW OF ANALYSIS A-20 10 CFR 50.62 OPERATING REACTOR REVIEWS - AMSAC A-21 10 CFR 50.61 PRESSURIZED THERMAL SHOCK III.A.1.2 TECHNICAL SUPPORT CENTER III.A.1.2 OPERATING SUPPORT CENTER 02/87C 03/87C 03/87C 03/87C 03/87C 03/87C 04/87C 06/84C 10/85C 04/81C 04/81C 05/87C 05/87C 10/87*
06/87C 01/88 09/87*
08/87*
10/87*
03/87C 09/86C 09/86C 07/87C 07/87C 10/87 08/87C 02/89R 04/88 11/87 05/88L 00/89R 01/86C 09/86C 09/86C 0773K MPA-F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 04/81C 09/86C 09/86C xNRC DATE
AEP FILE NUMBER S NRC NUMBERS APPLICABLE ISSUES IMPO.
INIT.
IMPO.
COMP.
IMPL.
COMP.
Page 7
'773V 0846W 07730 0916Z 0916P 0967C 0070V MPA-F-71 NMSS-3 NRR-3 II.F.1.6 F-25 II.F.3.31 F-58 M60099 M60347 M60675 I.D.1.2 DETAILED CONTROL ROOM REVIEW MISC.
AMEND. CONCERN PHYSICAL PROTECTION 0 SEVERE-ACCIDENT POLICY IMPLEMENTATION ON ACCIDENT-MONITORING-CONTAINMENT HYDROGEN (UNIT 2)
FINAL RECOMMENDATIONS, B&0 TASK FORCE -
COMPLIANCE WITH CFR 50.46 (UNIT 2)
COOK 2 -
CYCLE 6 RELOAD COOK 2 - 18 MONTH SURVEILLANCE EXTENSION COOK 2-PIPE HYDRO TEST RELIEF 10/84C 12/86C 09/87 01/82C 04/82C 10/85C 12/85C 02/86C 06/87C 06/88 00/89 09/83C 12/87 06/86C 01/86C 03/86C 00/91 00/88 00/91 12/86C OPEN+2 06/86C 02/86C 00/86C 0916N 0980E 0900F M61481 M63997 M64995 MPA-B-23 COOK 2 REDUCED TEMPERATURE AND POWER COOK 2 STEAM GENERATOR REPLACEMENT PROGRAM COOK 2 - ICE CONDENSER WEIGHT EMERGENCY DEGRADED GRID VOLTAGE (UNIT 2) 05/86C 11/86C 03/87C 08/76C 07/86C 11/87 04/87C 07/80C 04/89L 04/87C 06/86C
- NRC DATE NEVER IMPLEMENTED