ML20115G617
| ML20115G617 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/20/1992 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9210260258 | |
| Download: ML20115G617 (2) | |
Text
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W Northem states Power Company 414 Nicollet MJH Minneapoks. Minnesota 55401 1927 Telephone (612) 330 5500 g.
October 20, 1992 U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR GENERATING PIANT Docket Nos. 50-282 Litense Nos. DPR-42 50-306 DPR-60 Reactor Coolant System Samn1!.ng This letter is provided to inform the NRC of sur plans for the suspension of Technical Specification required sampling of the Prairie Island knit 1 reactor coolant systea during portions of the upcoming Unit 1 refueling outage.
These plans were discussad with the NRC Project Manager fer Prairie Island,.Marsha Gamberoni, and it was agreed that we document the plans through this letter.
During the upcoming Unit 1 reiueling outage, the reactor will be defueled and the reactor coolant syrtem will be drained to near the bottom of the hot leg
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to support modifications to the reactor coolant system and steam generator inspections.
Per Technical Specification 4.1.D, whenever the plant condition is such that a system or component is not required to be operable, the surveillance testing associated with that system or component may be discontinued.
Based on this guidance, the majority of the reactor coolant system sampling requirements from Table TS.4.1-2B will not be required during-the time when the reactor is defueled and the reactor coolant system is drained.
However, Technical Specification Section 4.1.D also specifies exceptions to the guidance described above.
It states, through. asterisks in Table TS.4.1.D, that the reactor coolant system sampling for chloride, fluoride and boron concentration are required at all times.
These samples are normally taken from an operating residual heat rimoval loop during cold shutdown and refueling conditions. However, wi:h the reactor coolant system drained to near the bottom of the hot leg, the residual heat removal system will be out of service, and it will not be possible to perform this sampling through.the residual heat removal system. There are no other reactor coolant system sample points available under these conditions which would produce meaningful results.
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M RC Northern States Power Company October 20, 1992 Page 2 1
Therefore, the sampling of the reactor coolant syster. for chloride, fitnride and boron concentration sill be suspended for the period of time the reactor coolant system is drained below mid-loop.
The required sampling will be reswned when the reactor coolant system is returned to a level which allows operation of the residur.1 heat rernoval system.
It is expected that the reactor coolant system will remain in this drained and defueled condition, with no sampling, for a period of several weeks during the Unit 1 outage.
Please contact us if you have any questions releted to the suspension of reactor coolant system sampling described above.
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')H1)l2j Thomas M Parker Manager Nuclear Support Services i
c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg I
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