ML20029A516
| ML20029A516 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/20/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 9102250155 | |
| Download: ML20029A516 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o-(
W ASHINGTON D. C. 20555 f
February 20, 1991 i
Docket No. 50-245 Mr. Edward J. Mroczka Senior Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company i
Post Office Box 270 Hartford, Connecticut- 06141-0270
Dear Mr. Mroczka:
SUBJECT:
MILLSTONE UNIT 1 - POST ACCIDENT TORUS TEMPERATURE i
Recent conversations'with members of-your staff indicate that post accident torus temperatures, for Millstone Unit 1, may exceed previous design basis values resulting in the need to reevaluate the impact on attached piping, supports, heat exchanges and pumps. Until such time as your evaluations are complete, we understand that you are procedurally restricting operating limits on torus temperature and service water temp (TS) as documented in erature to values below those in the Millstone Unit 1 Technical Specifications Inspection Report 50-245/90-17 dated October 5, 1990. Specifically, the torus temperature is restricted to 85'F versus a TS value of 90*F and the service water temperature is restricted to 72'F versus a TS value of 75 F.
While we concur with the need for the above described administrative measures, for the long term, the Technical Specifications should be changed to reflect the revised operating limits. Accordingly, we request that you submit an application for license amendment in order to incorporate the more limiting values for torus and service water temperatures in the TS.
As indicated in our February 12, 1991 telephone conversation with Mr. R. Kacich of your staff, we request that you make your submittal prior to the Spring 1991 Refueling Outage.
In the event that subsequent analysis indicate that the present Technical Specification operating limits are acceptable, you may withdraw this application.
During our telephone conversations with your staff, we noted that you have not, as yet, received an evaluation of the effects of the elevated, post-accident, 9102250155 910220 DR ADOCK 050 5
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Mr. Edward-J. Mroczka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. I cc:
Gerald Garfield, Esquire R. M. Kacich, Manager Day, Berry and Hnward Generation Facilities Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Rorberg, Vice President D. O. Nordquist Nuclear Operations Director of Quality Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region 1 Department of Environmental Protection U. S. Nuclear Regulatory Comission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 3radford S. Chase, Under Secretary First Selectmen Energy Division Town of Waterford Office of Policy and Management Hall cf Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Nuclear Station Director W. J. Raymond, Resident Inspector Millstone Nuclear Power Station Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U. S. Nucinar Regulatory Comission Post Office Box 128 Post Office Box 811 Waterford, Connecticut 06385 Niantic, Connecticut 06357 H. F. Haynes, Luclear Unit Director Millstone Unit No. 1 Northeast Huciear Energy Company Post Office Eax 128 Waterford, Connecticut 06385-1 1
1
Mr. Edward J. Hroczka February 20, 1991 torus temperatures en the low pressure coolant injection (LPCI) heat exchangers.
Until such time as the LPCI heat exchangers are qualified at the elevated torus temperature, we request that you propo.>e interim TS to further restrict service water tenperature such that the operability of the LPCI heet exchangers are l
assured.
Sincerely, S
John F. Stolz, Director Project Directorate I-4 Divis. ion of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation cc: See next page Distribution:
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POST-ACCIDENT TORUS TEMP