NRC 2007-0079, Generic Letter 2003-01, Control Room Habitability Regulatory Commitment Change.
| ML072490030 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/05/2007 |
| From: | Koehl D Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-03-001, NRC 2007-0079 | |
| Download: ML072490030 (2) | |
Text
Point Beach Nuclear Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC September 5, 2007 NRC 2007-0079 GL-2003-01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant Units 1 and 2 Docket Nos. 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Generic Letter 2003-01. Control Room Habitability Regulatory Commitment Chanae
References:
- 1) Letter from NMC to NRC dated August 11,2003 (ML032580984)
- 2) Letter from NMC to NRC dated December 5,2003 (ML033500466)
- 3) Letter from NMC to NRC dated September 29,2004 (ML042820156)
- 4) Letter from NMC to NRC dated August 22,2005 (ML052420480)
- 5) Letter from NMC to NRC dated December 8,2006 (ML063420598)
- 6) Letter from NRC to NMC dated January 5,2007 (ML063480040)
- 7) Letter from NMC to NRC dated May 1,2007 (ML071210471)
- 8) Letter from NMC to NRC dated July 6,2007 (ML071900220)
In Reference 1, Nuclear Management Company, LLC (NMC), provided the 60-day response to Generic Letter (GL) 2003-01 for PBNP. The letter included responses to ltems I(b), 2 and 3 of that letter and commitments to provide schedules for responses to ltems l(a) and I(c). The basis for the commitments was the need to conduct a control room envelope (CRE) baseline integrated unfiltered in-leakage test.
Reference 2 provided the preliminary results for unfiltered in-leakage into the CRE as less than 100 scfm while the control room ventilation system is operating in the emergency mode assumed in the radiological accident analysis. Schedules for providing the final CRE unfiltered in-leakage results and responses to ltems l(a) and l(c) were also provided as new commitments. Reference 3 revised the commitment dates provided in Reference 2. The final measured control room envelope unfiltered in-leakage value was provided to the NRC in Reference 4.
Reference 5 supplemented the response to Questions 1 and l(a) and committed to submitting a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by July 30, 2007. As part of this submittal, the post-accident reliance on KI for control room staff will be addressed.
6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321
Document Control Desk Page 2 In Reference 6, the NRC closed GL 2003-01 referencing NMC1scommitments to submit license amendment requests to revise the current accident analysis for PBNP using the AST methodology and to reference an acceptable surveillance methodology based on TSTF-448, following NRC approval.
In Reference 7, NMC committed to provide Technical Specification changes to reference an acceptable surveillance methodology (and plans for any associated plant modifications to the CRE) to support requested information in GL 2003-01, ltem (c), for PBNP no later than 180 days following NRC approval of TSTF-448.
In Reference 8, NMC committed to submitting a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by August 31, 2007. In addition, the commitment to provide Technical Specification changes to reference an acceptable surveillance methodology (and plans for any associated plant modifications to the CRE) to support requested information in GL 2003-01, ltem (c), for PBNP was changed to no later than 60 days following NRC approval of TSTF-448.
Summary of Commitments The following revises the commitment dates as stated in Reference 8. The proposed commitment change was discussed with the PBNP NRC Project Manager during telephone conference on August 31, 2007:
"NMC will submit a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by October 1, 2007.
As part of this submittal, the post-accident reliance on KI for control room staff will be addressed."
This matter has been entered @tothe corrective action program.
I /
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW
Text
Point Beach Nuclear Plant Committed to Nuclear Excellence Operated by Nuclear Management Company, LLC September 5, 2007 NRC 2007-0079 GL-2003-01 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant Units 1 and 2 Docket Nos. 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Generic Letter 2003-01. Control Room Habitability Regulatory Commitment Chanae
References:
- 1) Letter from NMC to NRC dated August 11,2003 (ML032580984)
- 2) Letter from NMC to NRC dated December 5,2003 (ML033500466)
- 3) Letter from NMC to NRC dated September 29,2004 (ML042820156)
- 4) Letter from NMC to NRC dated August 22,2005 (ML052420480)
- 5) Letter from NMC to NRC dated December 8,2006 (ML063420598)
- 6) Letter from NRC to NMC dated January 5,2007 (ML063480040)
- 7) Letter from NMC to NRC dated May 1,2007 (ML071210471)
- 8) Letter from NMC to NRC dated July 6,2007 (ML071900220)
In Reference 1, Nuclear Management Company, LLC (NMC), provided the 60-day response to Generic Letter (GL) 2003-01 for PBNP. The letter included responses to ltems I(b), 2 and 3 of that letter and commitments to provide schedules for responses to ltems l(a) and I(c). The basis for the commitments was the need to conduct a control room envelope (CRE) baseline integrated unfiltered in-leakage test.
Reference 2 provided the preliminary results for unfiltered in-leakage into the CRE as less than 100 scfm while the control room ventilation system is operating in the emergency mode assumed in the radiological accident analysis. Schedules for providing the final CRE unfiltered in-leakage results and responses to ltems l(a) and l(c) were also provided as new commitments. Reference 3 revised the commitment dates provided in Reference 2. The final measured control room envelope unfiltered in-leakage value was provided to the NRC in Reference 4.
Reference 5 supplemented the response to Questions 1 and l(a) and committed to submitting a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by July 30, 2007. As part of this submittal, the post-accident reliance on KI for control room staff will be addressed.
6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321
Document Control Desk Page 2 In Reference 6, the NRC closed GL 2003-01 referencing NMC1scommitments to submit license amendment requests to revise the current accident analysis for PBNP using the AST methodology and to reference an acceptable surveillance methodology based on TSTF-448, following NRC approval.
In Reference 7, NMC committed to provide Technical Specification changes to reference an acceptable surveillance methodology (and plans for any associated plant modifications to the CRE) to support requested information in GL 2003-01, ltem (c), for PBNP no later than 180 days following NRC approval of TSTF-448.
In Reference 8, NMC committed to submitting a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by August 31, 2007. In addition, the commitment to provide Technical Specification changes to reference an acceptable surveillance methodology (and plans for any associated plant modifications to the CRE) to support requested information in GL 2003-01, ltem (c), for PBNP was changed to no later than 60 days following NRC approval of TSTF-448.
Summary of Commitments The following revises the commitment dates as stated in Reference 8. The proposed commitment change was discussed with the PBNP NRC Project Manager during telephone conference on August 31, 2007:
"NMC will submit a license amendment request to the NRC revising the current accident analysis for PBNP to demonstrate compliance with the dose limits of 10 CFR 50, Appendix A, GDC-19, using the Alternative Source Term by October 1, 2007.
As part of this submittal, the post-accident reliance on KI for control room staff will be addressed."
This matter has been entered @tothe corrective action program.
I /
Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW