ML17329A747
| ML17329A747 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/06/1993 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9301110266 | |
| Download: ML17329A747 (8) | |
Text
SUBJECT:
Informs TE Murley that licensees completed commitments in response to Generic Ltr 90-06, "Power-Operated Relief Valve
& Block Valve Reliability," & Generic Issue 94, "Addi Low-Tem Overpressure Protection for LWRs," per 10CFR50.54(f).
S DZSTRZBUTZON CODE:
A019D COPIES RECEZVED:LTR
( ENCL IP SZSE'ITLE:
Generic Ltr 90-06 Resolution of GE 70N94 PORVs
& Block Valve Relxabil D
ACCEI ERAT DOCUMENT DIST UTION SYS'fEM REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:9301110266 DOC.DATE: 93/01/06 NOTARIZED: YES DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
Indiana Michigan Power Co. (formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA DEANgW COPIES LTTR ENCL RECIPIENT 1D CODE/NAME PD3-1 PD COPIES LTTR ENCL A
D D
INTERNAL: KIRKWOODiR.NLS3 NRR ARZB NRR/EMEB PICKETT,D 13H15 RES/DSIR/EIB EXTERNAL: NRC PDR NUDOCS-ABSTRACT R
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P1-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
G'OTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL D
S
indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 AEP: NRC: 1131B Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 RESOLUTION OF GENERIC ISSUE 70, "POWER-OPERATED RELIEF VALVE AND BLOCK VALVE RELIABILITY AND GENERI C IS SUE 9 4 >
ADDITIONAL LOW TEMPERATURE OVERPRESSURE PROTECTION FOR LIGHT-WATER REACTORS,"
PURSUANT TO 10 CFR 50.54(f)
(GENERIC LETTER 90-06)
U.S, Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T ~
E. Murley January 6,
1993
Dear Dr. Murley:
This letter is written to inform you that we have completed certain commitments that we made in response to Generic Letter (GL) 90-06 (reference our letters AEP:NRC;1131 and
- 1131A, dated December 21, 1990 and April 16, 1991, respectively).
Generic Letter 90-06 requires, in part, that the valves in the control air system that operates the power-operated relief valves (PORVs) be included in the in-service testing (IST) program.
We took exception to this requirement and stated that "Plant procedures will be enhanced to provide further assurance that the control air system valves perform their required functions when the PORVs are stroked off both the normal and backup air supplies every 18 months during cold shutdown."
Hardware required to effectively perform this testing on the two PORVs that have backup air supplies (NRV-152 and -153) has now been installed, tested and released for unrestricted operation in both units.
Specifically, in addition to the PORV positive shutoff racks, test vents were added upstream of t'e normal control air supply check valves for the two LTOP pressurizer PORVs on each unit, to provide the capability to ensure that these valves seat effectively during stroking of the PORVs off their back-up air supplies.
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Dr. T. E. Murley AEP:NRC:1131B The Cook Nuclear Plant Operations Department has revised its procedures (Procedures 1-and 2-OHP 4021.002.001, ) to perform this enhanced testing of the two LTOP pressurizer PORVs to stroke both off the normal and back-up air supplies independently during filling and venting of the RCS.
Our request for amendment to the Technical Specifications (reference our letter AEP:NRC:1131A) contains more stringent requirements than presently exist.
For example, the new technical specifications willrequire us to perform PORV operability testing in Mode 3, rather than during RCS filling and venting, as is currently the practice.
Also, the allowable outage time for a single LTOP channel will be decreased from 7 days to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Once we receive the approved amendment, we will implement these more stringent requirements.
This letter is submitted pursuant to 10 CFR 50.54(f) and, as such, an oath statement is enclosed.
Sincerely, Pg~pmf)
E.
E. Fitzpatrick Vice President JMN/die CC:
D. H. Williams,Jr.
A. A. Blind - Bridgman J.
R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector
- Bridgman
STATE OF OHIO)
COUNTY OF FRANKLIN)
E.
E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing Resolution of Generic Issue 70, "Power-Operated Relief Valve and Block Valve Reliability,"
and Generic Issue 94, "Additional Low-Temperature Overpressure Protection for Light-Water Reactors,"
and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to before me this ~g day of
, 19~~
NOTARY) PUBLIC BlTA D. HILL NOTARY PUBLlC. STATE OP OI uY COMMISSIOII EXPIRE
I 4 ~
Ql g
Dr. T. E. Murley AEP:NRC:1131B bc:
D. H. Malin/K. J. Toth S. J.
Brewer M. L. Horvath - Bridgman J.
B. Shinnock W.
G. Smith, Jr, W. M. Dean NRC - Washington D.C.
J.
B. Kingseed/T.
R. Satyan-Sharma/J.
M. Nieto S.
K. Farlow/B. J. Bastien R. L. Shoberg ED AD Abshagen/M.
A. Ferguson
- Bridgman J.
R.
Sampson
- Bridgman P.
G
~ Schoepf
- Bridgman AEP:NRC:1131B DC-N-6015.1