ML071090262
| ML071090262 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 06/07/2007 |
| From: | James Kim NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Kansler M Entergy Nuclear Operations |
| kim J, NRR/ADRO/DORL, 415-4125 | |
| References | |
| GL-03-001, TAC MB9840 | |
| Download: ML071090262 (5) | |
Text
June 7, 2007 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
NRC RECEIPT OF PILGRIM NUCLEAR POWER STATION, RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NO. MB9840)
Dear Mr. Kansler:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your responses to Generic Letter (GL) 2003-01 Control Room Habitability dated August 6, 2003 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML032260036);
September 30, 2004 (ADAMS Accession No. ML042880297); March 20, 2006 (ADAMS Accession No. ML060890468); March 22, 2007 (ADAMS Accession No. ML070890406); and May 22, 2007 (ADAMS Accession No. ML071510191). This letter provides a status of your response and describes any actions that may be necessary to consider your response to GL 2003-01 complete.
The GL requested that you confirm that your control room meets the design bases (e.g.
General Design Criterion (GDC) 1, 3, 4, 5, & 19, draft GDC, or principal design criteria), with special attention to: (1) Determination of the most limiting unfiltered and/or filtered inleakage into the control room and comparison to values used in your design bases for meeting control room operator dose limits from accidents (GL 2003-01, Item 1a); (2) Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments (GL 2003-01, Item 1b); and, (3) Determination that reactor control capability is maintained in the control room 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, and plans to retire them (GL 2003-01, Item 2).
Entergy reported the results of American Society for Testing Materials (ASTM E741, Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution) tracer gas tests for the Pilgrim Nuclear Power Station control room which is pressurized for accident mitigation. You determined that the maximum tested value for inleakage into the Control Room Envelope (CRE), was 121 (+/- 26) standard cubic feet per minute (scfm), which was more than the value of 10 scfm assumed in your current design basis radiological analyses for Control Room Habitability (CRH). You stated that an operability evaluation of the radiological consequences to control room occupants following a postulated loss-of-coolant accident (LOCA) was developed using alternate source term (AST) methodology and that the evaluation concluded that the dose limits prescribed in GDC-19 are satisfied under worst-case post accident conditions with unfiltered inleakage rates up to 1500 scfm and, therefore, the CRE remains operable and no compensatory actions are required. In your March 20, 2006, letter you stated that you expect to submit a license amendment request (LAR) in the 1st quarter of 2007 to revise your CRH licensing basis using AST methodology.
M. Kansler In your May 22, 2007 letter you stated that the inputs to the original dose consequence calculation were reassessed and that the dose consequence calculation was revised to update inputs with a control room inleakage value of 400 scfm which is greater than the measured inleakage value of 121 +/- 26 scfm. You further stated that the revised calculation demonstrates that the GDC-19 dose limits are met when the Control Room is placed in the isolated mode and that based on the results from the revised dose consequence analysis, you are no longer planning to submit a request to adopt AST methodology.
In response to Item 1(b) of the GL, Entergy indicated that its analysis for hazardous chemicals assumes that the system is operating at full capacity in the purge mode with 100% outside fresh air drawn into the CRE. This analysis is very conservative and in-leakage does not apply.
Therefore, no further analysis is needed. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested that you assess your Technical Specifications (TS) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL 2003-01, Item 1c). In your September 30, 2004, letter you indicated that you plan to use the guidance developed by the Nuclear Energy Institute Technical Specification Task Force (TSTF) and inleakage test results to determine changes to TS if required. In your March 22, 2007, letter you committed to submit a LAR to adopt TSTF-448, Revision 3, by November 30, 2007.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH, and also supported the conclusion that your are committed to meet the intent of the GDC regarding CRH which is documented in your Updated Final Safety Evaluation Report.
The information as discussed above, and your commitment to submit an LAR based on TSTF-448 is acceptable for purposes of closing out your response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me at 301-415-4125.
Sincerely,
/RA/
James Kim, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293 cc: See next page
M. Kansler In your May 22, 2007 letter you stated that the inputs to the original dose consequence calculation were reassessed and that the dose consequence calculation was revised to update inputs with a control room inleakage value of 400 scfm which is greater than the measured inleakage value of 121 +/- 26 scfm. You further stated that the revised calculation demonstrates that the GDC-19 dose limits are met when the Control Room is placed in the isolated mode and that based on the results from the revised dose consequence analysis, you are no longer planning to submit a request to adopt AST methodology.
In response to Item 1(b) of the GL, Entergy indicated that its analysis for hazardous chemicals assumes that the system is operating at full capacity in the purge mode with 100% outside fresh air drawn into the CRE. This analysis is very conservative and in-leakage does not apply.
Therefore, no further analysis is needed. You also indicated that reactor control capability is maintained from either the control room or the alternate shutdown panel in the event of smoke.
The GL further requested that you assess your Technical Specifications (TS) to determine if they verify the integrity of the CRE, including ongoing verification of the inleakage assumed in the design basis analysis for CRH, in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL 2003-01, Item 1c). In your September 30, 2004, letter you indicated that you plan to use the guidance developed by the Nuclear Energy Institute Technical Specification Task Force (TSTF) and inleakage test results to determine changes to TS if required. In your March 22, 2007, letter you committed to submit a LAR to adopt TSTF-448, Revision 3, by November 30, 2007.
The information you provided supported the fact that there are no compensatory measures needed to be in place to demonstrate CRH, and also supported the conclusion that your are committed to meet the intent of the GDC regarding CRH which is documented in your Updated Final Safety Evaluation Report.
The information as discussed above, and your commitment to submit an LAR based on TSTF-448 is acceptable for purposes of closing out your response to GL 2003-01.
If you have any questions regarding this correspondence, please contact me at 301-415-4125.
Sincerely,
/RA/
James Kim, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-293 cc: See next page DISTRIBUTION:
PUBLIC LPLI-1 R/F RidsNrrDorlLplb1-2 RidsNrrPMJKim RidsOgcRp RidsAcrsAcnwMailCenter RDennig CJackson RidsRgn1MailCenter JRobinson RidsNrrLASLittle Accession Number: ML071090262 OFFICE LPLI-2/PM LPLI-1/LA SCVB/BC PGCN/BC LPLI-1/BC NAME JKim SLittle RDennig CJackson MKowal DATE 6/01/07 4/23/07 6/07/07 6/04/07 6/05/07 Official Record Copy
Pilgrim Nuclear Power Station cc:
Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Senior Resident Inspector U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Post Office Box 867 Plymouth, MA 02360 Chairman, Board of Selectmen 11 Lincoln Street Plymouth, MA 02360 Chairman Nuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360 Chairman, Duxbury Board of Selectmen Town Hall 878 Tremont Street Duxbury, MA 02332 Office of the Commissioner Massachusetts Department of Environmental Protection One Winter Street Boston, MA 02108 Office of the Attorney General One Ashburton Place 20th Floor Boston, MA 02108 MA Department of Public Health Radiation Control Program Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129 Secretary of Public Safety Executive Office of Public Safety One Ashburton Place Boston, MA 02108 Director, Massachusetts Emergency Management Agency Attn: James Muckerheide 400 Worcester Road Framingham, MA 01702-5399 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056-0426 Mr. Kevin H. Bronson General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. Michael A. Balduzzi Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. Stephen J. Bethay Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. Bryan S. Ford Manager, Licensing Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508
Pilgrim Nuclear Power Station cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Oscar Limpias Vice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwarz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue New Orleans, LA 70113 Mr. James Sniezek 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster 5931 Barclay Lane Naples, FL 34110-7306 Mr. Garrett D. Edwards 814 Waverly Road Kennett Square, PA 19348