ML20215J171
| ML20215J171 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/16/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TASK-2.D.1, TASK-TM NUDOCS 8706240346 | |
| Download: ML20215J171 (2) | |
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BALTIMORE l
GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 '
JOSEPH A.T(ERNAN Vict PassIDENT
- NucttAn ENEnOY i
June 16,1987 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 TMI Action Item II.D.1, Performance Testing of Relief and Safety Valves
REFERENCES:
(a)
Letter from Mr. S. A. McNeil (NRC), to Mr. 3. A. Tiernan (BG&E),
dated April 30,1987, same subject (b)
Letter from Mr. A. E. Lundvall, Jr., to Mr. E. 3. Butcher, Jr., dated October 23,1985, same subject Gentlemen:
On April 30,1987, you asked for additional information regarding our implementation of TM1 Action item II.D.1, Performance Testing of Relief and Safety Valves (Reference a).
You asked us to provide the information by September 1,1987.
Many of your questions are extremely complex and will require detailed analyses by our architect / engineer and Nuclear Steam Supply System vendor. Therefore, we estimate we can respond by January 1,1988, except for Items 5 and 13.
Item 5 requests additional information to demonstrate qualification of the control circuitry. We are asked to provide documentation to show the equipment has been qualified under the environmental qualification (EQ) rule,10 CFR 50.49, or provide documentation that is similar to that required by the EQ rule. As members of the Nuclear Utility Group on Equipment Qualification (NUGEQ), we were informed this issue is being pursued on a generic basis between the NRC staff and NUGEQ. We previously addressed qualification of PORV control circuitry in our response to your first request for additional information (Reference b). Since we do not rely on the PORVs during design basis events, there is no basis for requiring environmental qualification. Since this is the issue being pursued by your staff and NUGEQ, we will maintain the position set forth in our previous response until the generic issue is resolved.
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item 18 suggests feedwater line break should have been considered when assessing relief i
and safety valve performance. This is closely related to an open item: Is feedline break a design basis event at Calvert Cliffs? In a letter concerning our Unit 2 Cycle 8 Reload Request, dated March 17,1987 (and subsequent correction dated March 23,1987), we agreed to respond to the feedline break issue as soon as possible, but no later than March 31,1988. We will expand our response to address the points in item 18.
We agree that it will be beneficial to meet with you to discuss your request further. We would like to work with you to provide a timely response to your request. More detailed discussions with your staff and with the outside organizations assisting us may lead us to respond to part, or all, of your request prior to January 1,1988.
Should you have additional questions regarding TMI Action Item II.D.1 or the schedule for our response, we would be pleased to discuss them with you.
Very truly yours, r(//WP JAT/ WPM / dim cc:
D. A. Brune, Esquire
- 3. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC I
W. T. Russell, NRC T. Foley/D. C. Trimble, NRC