ML17324A619
| ML17324A619 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/07/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0433I, AEP:NRC:433I, NUDOCS 8602140040 | |
| Download: ML17324A619 (6) | |
Text
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SUBJECT:
Responds to questions re 841019 Tech Spec Change Request AEP: NRC: 0433D. Valve ICM-111. previously included in inservice testing programs deleted per 85030b-07 meetings.
DISTRIBUTION CODE:
A001D COPIES RECEIVED: LTR ENCL SIZE:
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OR Submittal:
General Distribution ACCESSION NBR:8b02140040 DOC. DATE: Sb/02/07 NOTARIZED:
NO FACIL: 50-315 Donald C.
Cook Nuclear Power Planti Unit ii Indiana 5
50-31b Donald C.
Cook Nuclear Power Planti Unit 2i Indiana 5
AUTH. NAME AUTHOR AFFILIATION ALEXICH>M. P.
Indiana Zc Michigan Electric Co.
RECIP. NAME RECIPIENT AFFILIATION DENTONi H. R.
Office of Nuclear Reactor Regulationi Director (post 851125 NOTES:
OL: 10/25/74 OL: 12/23/72 05000315 0500031b RECIPIENT ID CODE/NAME PNR-A ADTS PNR-A EB PNR-A FOB PWR-A PSB INTERNAL: ACRB 09 ELD/HDB3 NRR/
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I INDIANA8 MICHIGAN ELECTRIC COMPANY P.O, BOX 16631 COLUMBUS, OHIO 43216 February 7, 1986 AEP:NRC:0433I Donald C.
Cook Nuclear Plant Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ADDITIONAL INFORMATION FOR TECHNICAL SPECIFICATION CHANGE REQUESTS IN LETTER AEP:NRC:0433D ON CONTAINMENT ISOLATION VALVES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter is in response to verbal questions raised by your staff on our Technical Specifications Change Request AEP:NRC:0433D, dated October 19, 1984.
Question I:
Valves ICM-111 and NPX-151 are listed in Table 3.6-1 of the Unit 1 Technical Specifications as containment isolation valves.
These valves are not included in the Inservice Testing (IST) Program.
Why not?
Response
NPX-151 is an instrument valve which performs a
containment isolation function.
The valve is normally closed and is required to remain closed to perform its safety function.
NPX-151 is currently tested per Appendix J.
We have included it in the second 10 year interval IST Program.
Valve ICM-111 had been included as part of our IST Program.
It was deleted as a result of an agreement reached by AEP/NRC during our March 6 and 7, 1985 meeting.
At that meeting, it was agreed that the valve did not perform a safety function.
Question II:
Table 3.6-1 indicates that valves ICM-250 and ICM-251 are testable at power.
AEP requested that these valves be exempt from the IST Program stating that they cannot be tested at power.
Which is correct?
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Response
ICM-250 and ICM-251 are normally closed valves that cannot be operated during normal plant operation without introducing boron into a non-heat traced line.
Boron could crystallize and plug the line.
We have, therefore, requested exemption to permit us to test these valves during cold shutdown.
This discrepancy will be eliminated when the changes to Table 3.6-1 (reviewed as part of AEP:NRC:0433D) are incorporated.
Question III: Service Air Valve PA-145 is listed in Unit 1 Technical Specifications Table 3.6-1, but is not listed in the IST Program.
Why?
Response
f This issue was addressed in our letter AEP:NRC:0659C, dated December 17,'984, and received as Amendment 87 to the Unit 1 Technical Specifications.
In this amendment valve PA-145 was deleted from Table 3.6-1, and'valve PCR-40 (which is included in the IST Program) was added.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M.
. Alexic Vice President el"~
MPA/rjn cc:
John E. Dolan W. G. Smith, Jr.
Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector - Bridgman
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