ML20084C444
| ML20084C444 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/23/1984 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-TM GL-83-10C, GL-83-10D, TAC-49663, TAC-49664, NUDOCS 8404300003 | |
| Download: ML20084C444 (2) | |
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Northem States Power Company 414 Nicollet Mall Minneapohs. Minnesota 55401 Telephone i612) 330-5500 April 23,1984 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to Generic Letter 83-10, Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps In our letter dated April 22, 1983, we submitted our plan for resolution of TMI Action Plan Item II.K.3.5.
NRC Staff requirements were contcined in letters from Mr Darrel G Eisenhut to all Applicants and Licensees with Westinghouse designed Nuclear Steam Supply Systems (Generic Letters 83-10 e and d) dated February 8, 1983. The submittals which fulfill the established requirements have been transmitted to you by Westinghouse Owners Group (WOG) letters 0G-117, dated March 12, 1984 and OG-110, dated December 1,1983. The purpose of this letter is to inform the Staff of our resolution of this item at Prairie Island.
Section I of the attachment to NRC letters 83-10 e and d describes " Pump l
Operation Criteria Which Can Result in RCP Trip During Transients and Accidents".
Subsection 1 of Section I presents guidelines for establishing setpoints for Reactor Coolant Pump (RCP) Trip. The Westinghouse Owners Group response to this section of NRC Letters 83-10 e and d is contained in Revision 1 to the WOG Emergency Response Guidelines, which has been issued to member utilities.
Plant specific procedures based on Revision 1 have been implemented at Prairie Island.
The RCP Trip Criteria adopted in the Prairie Island plant specific procedure not only assures RCP trip for all losses of primary coolant for which trip is considered necessary but also permits RCP operation to continue during most non-LOCA accidents, including steam generator tube rupture events up to the design basis double-ended tube rupture. The generic applicability of the RCP trip criterion selected has been documented by the Westinghouse Owners Group Report entitled, "Evsluation of Alternate RCP Trip Criteria", which has been submitted to the NRC for review in letter OG-110.
The Westinghouse Owners. Group has also submitted to the NRC, via letter OG-117, a report entitled " Justification of Manual RCP Trip for Small Break LOCA Events". As stated above, these submittals completed the WOG documentation responding to NRC Generic Letters 83-10 e and d.
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