ML19305B440
| ML19305B440 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/17/1980 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003190655 | |
| Download: ML19305B440 (4) | |
Text
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NSED NORTHERN STATES POWER COMPANY M IN N E A PO LI S. MIN N E S OTA 55401 March 17, 1980 Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR CENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Primary Coolant System Pressure Isolation Valves In a letter dated February 23, 1980 from Mr Darrell Eisenhut, Acting Director, Division of Operating Reactors, USNRC, we were requested to provide information related to primary coolant system pressure isolation valves at Prairie Island.
The following information is provided in response to this request:
1.
Eve nt V isolation valve configurations exist within the Class I boundary of the high pressure piping connecting the Primary Coolant System (PCS) to low pressure piping outside containment in the case of the Low Pressure Safety Injection (LPSI/RHR) system.
This configuration is also used to isolate the Safety Injection (SI system) and accumulators from the PCS.
SI system piping on the dis-charge side of the pumps is rated for full PCS pressure.
The accumulators are located inside containment.
A simplified flow diagram is attached showing these connections.
2.
On a daily basis a leakage test of the PCS is performed.
This "on-line" leak test measures all sources of reactor coolant leakage including leakage past pressure isolation valves into low pressure systems.
Our ASME Code Section XI valve inservice testing program has been modified to require leakage measurements of both the inboard and outboard isolation valves of systems connected to the PCS during the PCS leakage test conducted each re fueling. Leakage rates of isolation valves connect-ing RHR, SI, LPSI, and the accumulators to the PCS will be measured during the leakage test of the PCS.
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NORTHERN CTATE'} POWER COMPANY Director of Nuclear Reactor Regulation March 17, 1980 Page Continaous surveillance of the LPSI/RHR pressure isolation valves is accomplished with pressure indication and alarm in the control room.
Continuous surveillance of the safety injection accumulator pressure isolation valves is accomplished with pressure and level indication and alarm in the control room.
4 3.
No plant procedure revision or equipment modification is required to increase reliability.
Please contact us if you have any questions related to the information we have provided.
cx'b.h L 0 Mayer, E Manager of Nuclear Support Services LOM/DMM/ak cc: J G Keppler G Charnoff l
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.'o UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 50-306 License No. DPR-42 DPR-60 LETTER DATED MARCH 17, 1980 RESPONDING TO NRC REQUEST FOR INFORMATION ON PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES Northern States Power Company, a Minnesota corporation, by this letter dated March 17, 1980 hereby submits information in response to NRC request dated February 23, 1980 for information on primary coolant system pressure isolation valves.
This request contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY By u
L 0 Maypf l
Manager of Nuclear Support Services On this
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day of h
//fd, before me a notary public in and for said County, personally appeared L 0 Mayer, Manager of Nuclear Support Services, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
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JEANNE M. HACKER seOf A#Y PutuC - WW#etSOfA HENNEPIN COUNTY
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