ML20077R786
| ML20077R786 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/20/1991 |
| From: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-76786, TAC-76787, NUDOCS 9108260096 | |
| Download: ML20077R786 (2) | |
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p B ALTIMORE GAS AND ELECTRIC CHARLES CENTER e P.O. BOX 1475
( JOO 26 0 -4 4 M E U. S. Nuclear Regulatory Commission Washir.;, ton, DC 20555 ATTENTION:
Document Control Dc
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2: Docket Nos. 50-317 & 50-318 Requests for Relief from ash 1E Section XI Requirements (TAC Nos. 76786 & 76787)
REFERENCES:
(a)
Letter to Mr. G. C Creel (BG&E) from Mr. R. A. Capra (NRC),
Second Ten-Year Interval Inservice Testing Program - Calvert Cliffs Nuc! car Power Plant, Urits 1 and 2, dated September 20,1990 (b)
Letter to NRC Document Control Desk from Mr. G. C. Creel (BG&E), dated May 24,191, same subject Gentlemen:
Reference (a) forwarded the Nuclear Regulatory Commission Safety Evaluation related to the inservice testing (IST) program and Baltimore Gas and Electric Company's reauests for relief concerning the second ten-year inspection interval.
Reference (b) further addressed two relief requests from Reference (a). One of those was relief request RC-1, which deals with stroking of Power Operated Relief Valves (PORVs). We wish to provide further clarification concerning our use of PORVs and our intentions for meeting the ASME Section XI requirements.
First, we wish to correct a statement in the Technical Evaluation Report (Enclosure 2) of Reference (a). Section 4.3.1.1.2 of Enclosure 2 states, in part:"These valves are normally isebted by manual block valves during power operation, therefore, they are essentially out of service..."
Actually, Calvert Cliffs Units 1 and.: Technical Specification 3.4.3 requires that both PORVs and their associated block valves be operable in Modes 1,2 and 3. Surveil!ances are required every 31 days and 18 months to demonstrate operability. These valves are therefore normally insenice during operation and would not need to be retested during a cooldown before the plant enters the region requiring overpressure protection.
Second, as reoorted in Reference (b), we have withdrawn relief request RC-1 and we commit to upgrade the status of these valves to ASME Section XI, Category B cold shutdown exercised valves.
We will perform all tests resulting from this categorization, in accordance with ASME Section XI.
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Documcat Control Desk August 20,1991 Page 2 A request for change to Technical Specification 4.4.9.3.1.d will be submitted for your review in the near future to reflect the positions stated above.
Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours,
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D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC L E. Nicholson, NRC R. I. McLean, DNR J.11. Walter, PSC l
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