ML082820056
| ML082820056 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/21/2008 |
| From: | Nadiyah Morgan Plant Licensing Branch 1 |
| To: | Sena P FirstEnergy Nuclear Operating Co |
| References | |
| TAC MD7795, TAC MD7796 | |
| Download: ML082820056 (3) | |
Text
October 21, 2008 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 - RE:
CORRECTION LETTER TO THE GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS, PROPOSED ALTERNATIVE COURSE OF ACTION LETTER (TAC NOS. MD7795 AND MD7796)
Dear Mr. Sena:
By letter dated September 15, 2008, the Nuclear Regulatory Commission (NRC) staff issued an assessment of the 3-month response to Generic Letter 2008-01 submitted by FirstEnergy Nuclear Operating Company (licensee) for Beaver Valley Power Station, Unit Nos. 1 and 2. The NRC staff concluded that the licensees proposed alternative course of action and the associated basis for acceptance, with the exception of some clarifications and associated requests, were acceptable.
For clarification purposes, the NRC staff would like to make a correction to page 2 of the assessment. Enclosed is the corrected assessment page 2. If you have any questions, please contact me at (301) 415-1016.
Sincerely,
/RA/
Nadiyah S. Morgan, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
As stated cc w/encl: Distribution via ListServe
October 21, 2008 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 - RE:
CORRECTION LETTER TO THE GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS, PROPOSED ALTERNATIVE COURSE OF ACTION LETTER (TAC NOS. MD7795 AND MD7796)
Dear Mr. Sena:
By letter dated September 15, 2008, the Nuclear Regulatory Commission (NRC) staff issued an assessment of the 3-month response to Generic Letter 2008-01 submitted by FirstEnergy Nuclear Operating Company (licensee) for Beaver Valley Power Station, Unit Nos. 1 and 2. The NRC staff concluded that the licensees proposed alternative course of action and the associated basis for acceptance, with the exception of some clarifications and associated requests, were acceptable.
For clarification purposes, the NRC staff would like to make a correction to page 2 of the assessment. Enclosed is the corrected assessment page 2. If you have any questions, please contact me at (301) 415-1016.
Sincerely,
/RA/
Nadiyah S. Morgan, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
As stated cc w/encl: Distribution via ListServe Distribution:
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For BVPS-2, the licensee stated that necessary in-field verifications on both the suction side piping and the discharge side piping would be completed during the April 2008 refueling outage except where issues such as those discussed in the first paragraph of Section 2.0 of this assessment prevent completion. Any piping segments that require in-field verification, but have not received it prior to the 9-month GL response, will be in-field verified no later than restart from the next refueling outage that is planned for the fall of 2009. The licensee provided the following commitments for completion of its GL response:
For BVPS-1: Any piping segments that require in-field verification, but have not received it prior to the 9-month GL response, will be in-field verified no later than restart from the next refueling outage that is planned for the spring of 2009.
For BVPS-2: Any piping segments that require in-field verification, but have not received it prior to the 9-month GL response, will be in-field verified no later than restart from the next refueling outage that is planned for the fall of 2009.
NRC Staff Assessment The NRC staff finds that, with the exception of the clarifications and associated requests discussed below, that the licensees proposed alternative course of action is acceptable at BVPS-1 and 2.
The NRC staff notes examples where the licensees 3-month submittal dated April 11, 2008, does not clearly describe the content and/or schedule for the 9-month submittals. Specifically, the licensee does not explicitly state that its walkdowns and evaluations of accessible piping within the GL scope will be included in the response to be submitted by October 13, 2008.
Although the licensee committed to completing in-field piping verifications by no later than restart from the next refueling outage for BVPS-1 in the spring of 2009 and for BVPS-2 in the fall of 2009, it is not clear if that is the date the information will be submitted to the NRC.
The NRC staff requests the licensee to submit the information requested in GL 2008-01 as follows:
(1) 9-Month Initial Submittal - For the portions of the subject systems that are accessible prior to the BVPS-1 and 2 refueling outages planned for the spring 2009 and fall 2009, respectively, provide all GL requested information to the NRC by October 11, 2008.
(2) 9-Month Supplemental (Post-Outage) Submittal - Except for the long-term items described below, provide all remaining GL requested information for the subject systems to the NRC within 90 days following restart from the next refueling outages at BVPS-1 and 2, that are planned for the spring 2009 and fall 2009, respectively.
For each of the 2 submittals (9-month initial and supplemental submittals), and consistent with the information requested in the GL, the licensee should provide the following: (1) a description of the results of evaluations that were performed in response to the GL, (2) a description of all corrective actions that the licensee determined were necessary, and (3) a statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.