ML072690612
| ML072690612 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/29/2007 |
| From: | John Hughey NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Pardee C Exelon Generation Co |
| Hughey J, NRR/DORL, 301-415-3204 | |
| References | |
| GL-03-001, TAC MB9837, TAC MB9838 | |
| Download: ML072690612 (4) | |
Text
October 29, 2007 Mr. Charles G. Pardee Chief Nuclear Officer & Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NRC RECEIPT OF PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3, RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NO. MB9837 AND MB9838)
Dear Mr. Pardee:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of the responses for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, to Generic Letter (GL) 2003-01 Control Room Habitability dated August 11, 2003 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML032310390); December 9, 2003 (ADAMS Accession No. ML033560302); March 19, 2004 (ADAMS Accession No. ML040890545);
September 30, 2004 (ADAMS Accession No. ML042740704); November 29, 2004 (ADAMS Accession No. ML043420211); January 21, 2005 (ADAMS Accession No. ML050330124);
July 11, 2005 (ADAMS Accession No. ML051920406); and January 9, 2007 (non-publicly available). This letter provides a status of the PBAPS response to GL 2003-01.
The GL requested confirmation that the PBAPS control rooms (CR) meet their design bases with special attention to: (1) Determination of the most limiting unfiltered and/or filtered inleakage into the CR and comparison to values used in the PBAPS design bases for meeting CR operator dose limits from accidents (GL 2003-01, Item 1a); (2) Determination that the most limiting unfiltered inleakage is incorporated into the PBAPS hazardous chemical assessments (GL 2003-01, Item 1b); and, (3) Determination that reactor control capability is maintained in the CR or at the alternate shutdown location in the event of smoke (GL 2003-01, Item 1b). The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH), and plans to retire them (GL 2003-01, Item 2).
PBAPS reported the results of ASTM E741 (American Society for Testing Materials, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) tracer gas tests for the Unit 2 and 3 CR, which is a common CR pressurized for accident mitigation. PBAPS determined that the tested value for inleakage into the control room envelope (CRE), was 369 standard cubic feet per minute (scfm) for Train A and 21 scfm for Train B. Both values are above the value of 10 scfm assumed in the design basis radiological analyses for CRH. In your January 21, 2005, letter, PBAPS stated that a license amendment request (LAR) was submitted on July 14, 2003, to revise the licensing basis to use Alternative Source Term (AST) methodology.
C. Pardee PBAPS stated that AST methodology would increase the assumed inleakage from 10 scfm to 500 scfm and would result in doses that are less than the general design criteria (GDC) 19 limits for whole body and thyroid. In the letter dated May 10, 2005, PBAPS subsequently withdrew the LAR, but in the response dated January 9, 2007, PBAPS committed to re-submit an LAR to adopt AST methodology by November 30, 2007. An LAR to adopt AST methodology was re-submitted to the NRC for PBAPS Units 2 and 3 on July 13, 2007 (ADAMS Accession No. ML072570151).
PBAPS also provided information that adequately supported a conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments, and that reactor control capability is maintained from either the CR or the alternate shutdown panel in the event of smoke.
The GL further requested that PBAPS assess your technical specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL 2003-01, Item 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your July 11, 2005, response, you indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force (TSTF)-448 and resubmit a proposed license amendment request based on the evaluation. An LAR to adopt TSTF-448 was re-submitted to the NRC for PBAPS Units 2 and 3 on April 12, 2007 (ADAMS Accession No. ML071090282).
The information PBAPS provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH. This information also supported the conclusion that the units meet the intent of the draft GDC regarding CRH.
The information provided above and the LARs submitted for PBAPS to adopt AST methodology and TSTF-448 are acceptable for the purposes of closing out the PBAPS response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me at 301-415-3204.
Sincerely,
/RA/
John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278 cc:
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C. Pardee PBAPS stated that AST methodology would increase the assumed inleakage from 10 scfm to 500 scfm and would result in doses that are less than the general design criteria (GDC) 19 limits for whole body and thyroid. In the letter dated May 10, 2005, PBAPS subsequently withdrew the LAR, but in the response dated January 9, 2007, PBAPS committed to re-submit an LAR to adopt AST methodology by November 30, 2007. An LAR to adopt AST methodology was re-submitted to the NRC for PBAPS Units 2 and 3 on July 13, 2007 (ADAMS Accession No. ML072570151).
PBAPS also provided information that adequately supported a conclusion that the most limiting unfiltered inleakage into the CRE is incorporated into the hazardous chemical assessments, and that reactor control capability is maintained from either the CR or the alternate shutdown panel in the event of smoke.
The GL further requested that PBAPS assess your technical specifications (TSs) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL 2003-01, Item 1c). As permitted by the GL, you provided a schedule for revising the surveillance requirement in the TS to reference an acceptable surveillance methodology. In your July 11, 2005, response, you indicated that you would evaluate your submittal with respect to the elements contained in Technical Specification Task Force (TSTF)-448 and resubmit a proposed license amendment request based on the evaluation. An LAR to adopt TSTF-448 was re-submitted to the NRC for PBAPS Units 2 and 3 on April 12, 2007 (ADAMS Accession No. ML071090282).
The information PBAPS provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH. This information also supported the conclusion that the units meet the intent of the draft GDC regarding CRH.
The information provided above and the LARs submitted for PBAPS to adopt AST methodology and TSTF-448 are acceptable for the purposes of closing out the PBAPS response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me at 301-415-3204.
Sincerely,
/RA/
John D. Hughey, Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-277 and 50-278 cc:
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Accession Number: ML072690612 OFFICE LPLI-2/PM LPLI-2/LA SCVB/BC PGCB/BC LPLI-2/BC NAME JHughey ABaxter RDennig MMurphy HChernoff DATE 10/04/07 10/04/07 10/18/07 10/16/07 10/29/07 Official Record Copy
Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 cc:
Site Vice President Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Plant Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Regulatory Assurance Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P.O. Box 399 Delta, PA 17314 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Roland Fletcher Department of Environment Radiological Health Program 2400 Broening Highway Baltimore, MD 21224 Correspondence Control Desk Exelon Generation Company, LLC P. O. Box 160 Kennett Square, PA 19348 Director, Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Director-Licensing and Regulatory Affairs Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Board of Supervisors Peach Bottom Township 545 Broad Street Ext.
Delta, PA 17314-9203 Mr. Richard McLean Power Plant and Environmental Review Division Department of Natural Resources B-3, Tawes State Office Building Annapolis, MD 21401 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Manager-Financial Control & Co-Owner Affairs Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038-0236 Manager Licensing-Peach Bottom Atomic Power Station Exelon Generation Company, LLC 200 Exelon Way, KSA -3E Kennett Square, PA 19348 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President-Operations Mid-Atlantic Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555