05000306/LER-2019-001, Cancellation: LER 2019-001-00 for Prairie Island Nuclear Generating Plant, Unit 2, Reactor Coolant Isolation Valve Leakage Results in Condition Prohibited by Technical Specifications
| ML19353A417 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/16/2019 |
| From: | Sharp S Northern States Power Company, Minnesota, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-19-045 LER 2019-001-00 | |
| Download: ML19353A417 (2) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3062019001R00 - NRC Website | |
text
1717 Wakonade Drive Welch, MN 55089 December 16, 2019 L-PI-19-045 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Unit 2 Docket No. 50-306 Renewed Facility Operating License No. DPR-60 Notice of Cancellation of LER 2019-001-00, Reactor Coolant Isolation Valve Leakage Results in Condition Prohibited by Technical Specifications
References:
- 1) Letter from Prairie Island Nuclear Generating Plant to NRC, Licensee Event Report 2019-001-00, Reactor Coolant Isolation Valve Leakage Results in Condition Prohibited by Technical Specifications, dated September 27, 2019 On September 27, 2019, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter NSPM), submitted Prairie Island Nuclear Generating Plant (PINGP) Licensee Event Report (LER) 2019-001-00 (letter L-PI-19-39). The LER was submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by the plants Technical Specifications. This letter is being submitted to cancel (formally withdraw)
LER 2019-001-00, consistent with the guidance of NUREG 1022, Revision 3, Sections 2.8 and 5.1.2. This cancellation eliminates the need to supplement the LER.
The LER originally reported that the Unit 2 primary containment isolation valve, MV-32410, 21 Reactor Coolant Loop B Hot Leg Sample Motor Valve, likely had a metallic diaphragm leak that was allowing reactor coolant system (RCS) water to leak into the containment building air space. This resulted in a condition prohibited by technical specifications.
NSPM completed a Unit 2 outage in October 2019 which included leak testing and visual inspection activities of MV-32410. The leak testing was performed and found no detectable leakage. A visual inspection was also performed and found no indication of leakage. Further investigation of the penetration found sample valve 2SM-7-3, 21 Reactor Coolant Loop B Hot Sample SM-203, with an inactive boric acid leak from the valve packing. The packing leak from this sample valve is considered the most likely source of the radiation readings described in the LER. This sample valve is not a primary containment isolation valve and does not have a safety related function. This leaking sample valve is not a condition prohibited by technical specifications and no loss of safety function occurred, therefore, an LER is not required.
(l Xcel Energy*
RESPONSIBLE BY NATURE~
Document Control Desk Page2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.
Scott Sharp Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC State of Minnesota