ML17250A535
| ML17250A535 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/04/1980 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17250A536 | List: |
| References | |
| NUDOCS 8009090377 | |
| Download: ML17250A535 (4) | |
Text
REGULATORY ORMATION DISTRIBUTION SYS (RIDS)-
ACCESSION NBR:8009090377 DOC.DATE: 80/09/04 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear PlantE Unit 1P Rochester G
05000244 AUTH BYNAME AUTHOR AFF ILIIATION HHITEE L ~ D ~
Rochester Gas 8 Electric Corp.
REC IP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELDED ~
Ooerating Reactors Branch 5
SUBJECT:
Forwards inservice,pump 8 valve testing program for Jan 1981 - Dec 1990iA'ppI C to QA manual
~
DISTRIBUTION CODE:
AOOIS COPIES, RECEIVED:LTRJ l ENCL'0. SIZE:
TITLE: General Distribution for af ter Issue'nce of Operating L'i c NOTES: 1 copy:SEP Sects Ldr ~
05000244 RECIPIENT ID CODE/NAME ACTION:
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ROCHESTER GAS AND ELECTRIC CORPORATION D
89 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
VICE PRESIDENT TELEPHONE AREA CODE 7IS 546.2700 September 4,
1980 Director of Nuclear Reactor Regulation Attention:
Dennis M. Crutchfield, Chief Operating Reactors Branch 45 U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Inservice Pump and Valve Testing Program R.
E. Ginna Nuclear Power Plant Unit N1 Docket No.
50-244
Dear Mr. Crutchfield:
In accordance with the requirements of 10CFR Part 50, Section 50.55a, paragraph (g),
we have enclosed the Ginna Station Inservice Pump and Valve Testing Program for the January 1,
1981 through December 31, 1990 interval.
This enclosure is entitled "Appendix C to the Ginna Station Quality Assurance Manual".
This revised program is very similar to the current program submitted November 15, 1979.
In accordance with 10CFR 50.55a paragraph (g)(4)(ii) this program is based on the 1977 Edition of Section XI with addenda through the Summer 1978 addenda.
Test Category E
(locked valves) has been deleted from the program consistent with the deletion from the referenced Code edition.
Additional containment isolation valves have also been added to Category A so that this program scope is consistent with that of Technical Specifications.
Since the current program, which has yet to receive NRC
- approval, expires on Decmeber 31, 1980, it is our intention to implement the revised Appendix C on January 1, pending subsequent NRC approval.
Enclosed are forty (40) copies of this letter and the attachments.
8e o/
Very truly yours, 5
L. D. White, Jr.
Enclosures P>oooooo 577
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