ML17328A560
| ML17328A560 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/02/1990 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1121A, NUDOCS 9002120350 | |
| Download: ML17328A560 (8) | |
Text
ACCELERATED DILUTION DEMONS'TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9002120350 DOC.DATE: 90/02/02 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Corrects commitment date contained in 900131 ltr & provides details of program to assess operability of MS V.
DISTRIBUTION CODE A001D COPIES RECEIVED LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:
R D
RECIPIENT ID CODE/NAME PD3-1 LA GIITTER,J.
INTERNAL: NRR/DET/ECMB 9H NRR/DST SE2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
1 5
5 1
1 1
1 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DOEA/OTS B1 1 NRR/DST/SELB SD NRR/DST/SRXB SE
~C~Qg3
~EG FIL 01 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1
~
1 1
D D
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 19 A
D D
Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:1121A Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 MAIN STEAM ISOLATION VALVES CORRECTIVE ACTION U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn: T.
E. Murley February 2, 1990
Dear Dr. Murley:
This letter corrects a commitment date contained in our letter AEP:NRC:1121 dated January 31,
- 1990, and also provides the details of our program 'to assess the operability of the main steam isolation valves (Attachment 1).
Conunitment 1 of the previous submittal was to develop a program to monitor dump valve leakage by February 8,
1990.
This date should have been February 2,
1990.
The attached program satisfies this commitment.
During a conversation with a member of the Region III staff, we were requested to provide a copy of the acoustic data collected on the valves.
These data are included as Attachment 2.
This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M.
P Alex Vice President ldp Attachments
,ol
(
9002120350 900202 PDR ADGCK 05000315 I
Dr. T.
E. Murley AEP:NRC:1121A cc:
D. H. Williams, Jr.
A. A. Blind - Bridgman R.
C. Callen G. Charnoff A. B. Davis
- Region III NRC Resident Inspector
- Bridgman NFEM Section Chief
ATTACHMENT 1 TO AEP:NRC:1121A VALVE MONITORING PROGRAM
VALVE MONITORING PROGRAM Monitoring of dump valve leakage will be accomplished by taking acoustical measurements on or just downstream of the dump valves.
Steam leaking past a
valve produces
- noise, and acoustical data have been taken on all dump valves to obtain baseline data.
Future acoustical measurements on Unit 1 valves will be taken at prescribed locations twice a week (the frequency for Unit 2 has not been decided).
Our preliminary assessment is that the threshold criteria will be set such that doubling of the db level or an absolute reading greater than 90db (the value observed on a benchmarked valve) will indicate increasing dump valve leakage and require that a pressure decay test be conducted on the affected dump line, The pressure decay test will consist of isolating the pressurized portion of the dump line and measuring the rate of pressure change.
These data will then be compared against data from a benchmarked valve.
The benchmarked valve 2-MRV-230 marginally passed its Technical Specification surveillance requirement of five seconds before the Unit 2 MSIVs were modified.
The dump valves associated with 2-MRV-230 are in the identical condition that existed during the pre-modification test as no maintenance was performed on them in the interim.
Pressure decay data have been obtained and normalized to allow comparison with the pressure decay rate from other valves providing a measure of dump valve leakage approaching potentially unacceptable. levels.
If the pressure decay rate of the valve under test approaches the decay rate of the benchmark valve, corrective action will be taken.
This action will entail repairing the dump valve before the acceptance criteria is exceeded.
While the repair is being made, the provisions of the applicable Technical Specifications will be followed.
ATTACHMENT 2 TO AEP:NRC:1121A DATA USED TO DEVELOP THE VALVE MONITORING PROGRAM
SOUND LEVELS AT DUMP VALVES - UNIT 1 1-MRV-211 1-MRV-222 1-MRV-241 Date db 1/25 0
1/26 0
1/29 0
1/30 0
1/31 0
2/1 0
1-MRV-212 Date db 1/25 0
1/26 0
1/29 10 1/30 10 1/31 0
1-MRV-221 Date db 1/25 1/26 1/29 1/30 1/31 1-MRV-231 Date db 1/25 0
1/26 0
1/29 5
1/30 5
1/31 0
1-MRV-232 Date db 1/25 1/26 1/29 1/30 1/31 1-MRV-242 Date db 1/25 0
1/26 0
1/29 0
1/30 0
1/31 0
0 5
2.5 10 10 Date db 1/25 1/26 1/29 1/30 1/31 Date db 1/25 10 1/26 3
1/29 0
1/30 0
1/31 3
SOUND LEVELS AT DUMP VALVES - UNIT 2 2-MRV-211 Date db 2-MRV-222 Date db 2-MRV-241 Date db 1/26 0
1/29 30 1/30 35 1/31 4
1/26 1/29 1/30 1/31 2/1 5
0 0
35 0
1/26 0
1/29 0
1/30 0
1/31 30 2/1 0
2-MRV-212 Date db 1/26 0
1/29 0
1/30 0
1/31 0
2-MRV-221 2-MRV-231 Date 'b 1/26 10 1/29 0
1/30 2
1/31 0
2/1 2
2-MRV-232 2-MRV-242 Date db 1/26 50 1/29 0
1/30 5
1/31 0
2/1 40 Date db 1/26 5
1/29 0
1/30 0
1/31 2
2/1 2
Date db 1/26 80 1/29 80 1/30 90 1/31 80 2/1 85