ML20205S012
| ML20205S012 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/29/1986 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.05, TASK-TM TAC-49663, TAC-49664, NUDOCS 8606060106 | |
| Download: ML20205S012 (2) | |
Text
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Northern States Power Company 414 Nicollet Mall Minneapohs. M4nnesota 55401 Telephone (612) 330-5500 May 29, 1986 Director Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAP.'D NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 LICENSE NOS. DPR-42 50-306 DPR-60 Reactor Coolant Pump Trip Criteria In a letter dated May 7, 1986 we were provided with a report prepared by the NRC Staff related to the reactor coolant pump trip criteria i n p'i n ce at the Prairie Island Nuclear Generating Plant in satisfaction of NUREG-0737, Item II.K.3.5.
Northern States Power Company was requested to confirm the information provided in this report and supply additional information related to fluid Jets / pipe whip and reactor coolant system pressure uncerte4nties.
The purpose of this letter is to supply the requested information.
Review of Staff Report The information provided in the May 7, 1986 NRC Staff evaluation has been reviewed.
The information presen-ted as " Prairie Island Responses" was found to be accurate.
Break Dynamic Effects on Pressure Instrumentation Each pressure sensor / transmitter train is located on a separate coolant loop.
Considerable physical separa-tion is provided by concrete shield and vault walls.
Additionally, the transmitters are located outside of their respective vaults.
The transmitters and cabling are " trained" in accordance with IEEE Class IE separa-tion criteria.
Calculation Uncertainty Values The Westinghouse analyses used bounding plant parame-ters.
Justification for the parameters that were used was provided in the owners group reports and was re-viewed and found acceptable to the NRC Staff.
These reports justified the choice of the bounding plant parameters, discussed the difference between plant specific parameters, and justified the choice of the bounding plant.
A specific " uncertainty" value was not (7
computed for each Westinghouse plant.
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t Northem States Power Company Director of NRR May 29, 1986 Page 2 Please contact us if you have any questions related to this information or if additional information is required to complete NRC action on this matter.
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David Musolf Manager Nuclear Support Services c:
NRR Project Manager, NRC Resident Inspector, NRC Regional Administrator, Region III, NRC G Charnoff