ML073370907
| ML073370907 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/30/2007 |
| From: | Mccarthy J Florida Power & Light Energy Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-06-002, NRC 2007-0074 | |
| Download: ML073370907 (3) | |
Text
FPL Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 FPL Energy Point Beacl~ Nuclear Pilaill November 30,2007 NRC 2007-0074 10 CFR 50.54(f)
U. S. Nuclear Regulatory Commission AlTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Clarification of Response to Request for lnformation Renardinn Generic Letter 2006-02, "Grid Reliabilitv and the lmpact on Plant Risk and the Operabilitv of Offsite Power"
References:
I ) Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2006-02, "Grid Reliability and the lmpact on Plant Risk and the Operability of Offsite Power",
dated February 1,2006 (ML060180352)
- 2) Nuclear Management Company, LLC (NMC) letter L-HU-06-030, Response to Generic Letter 2006-02, dated July 21,2006 (ML062050349)
- 3) NRC letter, "Request for Additional lnformation Regarding Resolution of Generic Letter (GL) 2006-02, Grid Reliability and the lmpact on Plant Risk and the Operability of Offsite Power (TAC Nos. MD0947-MD1050), dated December 5,2006 (ML063380300)
- 4) NRC letter, Revised Response Date for Request for Additional lnformation Regarding Resolution of Generic Letter (GL) 2006-02, (TAC Nos. MD0947 through MD1050), dated December 13,2006 (ML063460440)
- 5) NMC Letter, "Response to Request for Additional lnformation Regarding Resolution of Generic Letter 2006-02 dated January 31, 2007 (ML070310576)
- 6) NRC letter, Monticello Nuclear Generating Plant, Point Beach Nuclear Plant, Units 1 and 2, and Prairie Island Nuclear Generating Plant, Units 1 and 2 (TAC Nos. MD1001, MD1018, MD1019, MD1020, and MD1021), dated April 24,2007 (ML071070027)
In Reference 1, the NRC requested that specific information be provided for each nuclear plant.
Reference 2 provided the NMC response to the requested information for the Point Beach Nuclear Plant (PBNP). In Reference 3, the NRC transmitted six requests for additional information (RAls) for resolution of GL 2006-02 and a matrix listing the applicable RAI questions for each specific plant. Reference 4 requested that the RAI responses be provided to the NRC by January 31, 2007. Reference 5 provided the response to the request for additional information, and Reference 6 stated that the NRC considered the response to GL 2006-02 complete for the subject nuclear plants.
An FPL Group company
Document Control Desk Page 2 During the course of the FSAR reconciliation project at PBNP, it was discovered that the NMC response to Question 3(a) of Reference 1 was inconsistent with the plant's license basis as directed in the Technical Specifications. Accordingly, the enclosure to this letter clarifies the response to Question 3(a). The issue was documented in the Point Beach Nuclear Plant (PBNP) corrective action program.
If there are questions associated with this clarification, please contact Mr. Mike Millen, Work Control Center Manager at 9201755-6001.
Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on November 30, 2007.
Very truly yours, FPL Energy Point Beach, LLC
~7
/ James H. ~ b ~ a r t h ~
Site Vice President Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach, USNRC Resident Inspector, Point Beach, USNRC
ENCLOSURE Clarification of Response to Request for Information Regarding Generic Letter 2006-02, "Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power" Point Beach Nuclear Plant, Units 1 and 2 NRC Question 3 Use of criteria and methodologies to assess whether the NPP's offsite power system and safety-related components will remain operable when switchyard voltages are inadequate.
(a) If the TSO notifies the NPP operator that a trip of the NPP, or the loss of the most critical transmission line or the largest supply to the grid would result in switchyard voltages (immediate and/or long-term) below TS nominal trip setpoint value requirements (including NPP licensees using allowable value in its TSs) and would actuate plant degraded voltage protection, is the NPP offsite power system declared inoperable under the plant TSs? If not, why not?
FPL Enernv Point Beach (FPLE-PB) formerly Nuclear Mana~ement Company (NMC)
Clarified Response If the Transmission System Operator (TSO) notifies Point Beach Nuclear Plant (PBNP) that a trip of either PBNP unit would result in 345 kV system voltages to drop below the specified minimum voltage, PBNP will enter the associated Technical Specification Action Condition (TSAC) for inoperable offsite power.
Declaring offsite power inoperable due to the contingent loss of a single element is limited to the loss of a PBNP generating unit, not any transmission system event. Entering TSACs as a result of postulated failures elsewhere on the grid is not part of the PBNP licensing basis. Entry into a shutdown TSAC for both units would likely exacerbate the 345 kV grid conditions.
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