ML20050C150
| ML20050C150 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/01/1982 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204080210 | |
| Download: ML20050C150 (2) | |
Text
a Northern States Power Company 414 Nicollet Mall Minneapolis. Mi j th, A g
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Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 NUREG-0737, Item II.D.1, PWR Safety and Relief Valve Test Program In ac u dance with the initial recommendations of NUREG-0578, Section 2.1. 2 as later clarified by NUREG-0737. Item II.D.1, and an NRC letter dated Septembe 29, 1981, each I ressurized Water Reactor (PWR) licensee on or before April 1, 1982 is required to submit a preliminary evalua-tion supported by test results which demonstrates the capability of relief and safety valves to operate under expected operating and accident conditions.
This letter is the Northern States Power Company response to the April 1, 1982 NRC reporting requirement and is applicable to Prairie Island Units I and 2.
Northern States Power is a participant ta the Generic PWR Safety and Relief Valve Test Program implemented by the tilectric Power Research Institute at the request of participating PWR Utilities in response to the USNRC recommendations for safety and relief valve testing. The primary objective of the Test Program is to provide full scale test data confirming the functionability of primary system power operated relief valves and safety valves for expected operating and accident conditions. The secondary objective of the program is to obtain suf ficient piping thermal hydraulic load data to permit confirmation of models which may be utilized for plant unique analysis of safety and relief valve discharge piping systems.
Relief valve tests were completed in August, 1981 and safety valve tests were completed in December, 1981. The reports prepared by EPRI document-ing the Test Program results are as follows:
" Valve Selection / Justification Report" This report documents that the selected test valves represent all participating PWR plant safety and relief valves.
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" Test Condition Justification Report" and the
"(Applicable NSSS Vendor) Plant Condition Justification Report" These reports document the basis and justification of the valve test conditions for all participating PWR plants.
" Safety and Relief Valve Test Report" This report provides evidence demonstrating the functionability of the selected test valves under the selected test conditions for all participating PWR plants.
" Discharge Piping Load Model Reports" This report presents an analytical model benchmarked against test data that may be used for plant unique analysis of safety and relief valve discharge piping systems...
All of these reports have been transmitted to the NRC by David Hoffman of Consumers Power Company on behalf of the participating PWR Ut111 ties to meet the April 1,1982 preliminary submittal requirement. Northern States Power has performed a preliminary review of the Test Prgram results.
Based on the review, we have concluded that valves tested reprer.ent the safety and relief valve designs and that the conditions tested represent the range of unexpected operating and accident conditions for Prairie Island Unit I and 2.
Also, the above mentioned Reports provide the information required by NUREG-0737, Item II.D.I. A which will be used to perform the final plant specific evaluations.
The September 29, 1981 USNRC Ictter requested that plant specific final evaluations be submitted by July 1,1982.
In order to meet that date, evaluations have been initiated. Depending on the outcome of the evaluations, it may be necessary to continue the evaluation beyond July 1, 1982.
If a longer evaluation period is required, we will request schedule relief before July 1, 1982.
Please contact us if you have any questions concerning the information we have provided related to this TMI Action Plan requirement.
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- L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/bd Attachment cc: Regional Admin-III, NRC NRR Proj Mgr, NRC-NRC Resident Inspector G-Charnof f m.
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