ML062500076
| ML062500076 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/20/2006 |
| From: | Mozafari B NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Young D Progress Energy Co |
| Mozafari B, NRR/ADRO/DORL, 415-2020 | |
| References | |
| GL-03-001, TAC MB9793 | |
| Download: ML062500076 (3) | |
Text
October 20, 2006 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing and Regulatory Programs 15760 W. Power Line Street Crystal River, FL 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - NRC RECEIPT OF RESPONSE TO GENERIC LETTER 2003-01 CONTROL ROOM HABITABILITY (TAC NO. MB9793)
Dear Mr. Young:
The Nuclear Regulatory Commission (NRC) acknowledges the receipt of your response to Generic Letter (GL) 2003-01, Control Room Habitability, in a letter dated December 9, 2003 (Agencywide Document and Access Management System (ADAMS) Accession No. ML033510599). This letter provides a status of your response and describes any additional information that may be necessary to consider your response to GL 2003-01 complete.
GL 2003-01 requested that you confirm that your control room meet its design bases (e.g.,
General Design Criteria (GDC) 1, 3, 4, 5, and 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 (Item 1(a)), (2) Determination that the most limiting unfiltered inleakage is incorporated into your hazardous chemical assessments, and (3) Determination that reactor control capability is maintained in the control room or at the alternate shutdown location in the event of smoke (Item 1(b)). The GL further requested information on any compensatory measures in use to demonstrate control room habitability (CRH), and plans to retire them (Item 2).
You reported the results of American Soceity for Testing Materials, ASTM E741 tracer gas tests for the Crystal River Unit 3 (CR3) control room. For CR3, you determined that the maximum tested unfiltered inleakage into the control room envelope (CRE) was 513 standard cubic feet per minute (scfm), which is less than the value of 1000 scfm assumed in the design basis radiological analysis for CRH.
You indicated that you have evaluated the potential toxic gas sources at the site and concluded that the CRE ventilation system could remain in normal alignment (no isolation) without exceeding the toxicity limits within 2 minutes of nasal detection. You also indicated that reactor control capability is maintained from either the control room or the alternate remote shutdown room in the event of smoke.
D. E. Young 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, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL Item 1(c)). 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 December 9, 2003, response you indicated that you will submit a license amendment request to revise your TS utilizing Technical Specification Task Force (TSTF) Traveler TSTF-448, within 6 months of the approval of TSTF-448 by the NRC.
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate CRH.
The information you provided also supported the conclusion that you are committed to meet the GDC regarding CRH.
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page
D. E. Young 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, and in light of the demonstrated inadequacy of a delta () P measurement to alone provide such verification (GL Item 1(c)). 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 December 9, 2003, response you indicated that you will submit a license amendment request to revise your TS utilizing Technical Specification Task Force (TSTF) Traveler TSTF-448, within 6 months of the approval of TSTF-448 by the NRC.
The information you provided also supported the fact that there are no compensatory measures in place to demonstrate CRH.
The information you provided also supported the conclusion that you are committed to meet the GDC regarding CRH.
Your commitment to submit a license amendment request based on TSTF-448, following our formal review and approval, is acceptable for purposes of closing out your response to GL 2003-01. The NRC staff will monitor submittal of the license amendment request and interact with you as necessary during the amendment process.
If you have any questions regarding this correspondence, please contact me.
Sincerely,
/RA/
Brenda Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302 cc: See next page DISTRIBUTION:
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Mr. Dale E. Young Crystal River Nuclear Plant, Unit 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042 Mr. Jon A. Franke Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Jim Mallay Framatome ANP 1911 North Ft. Myer Drive, Suite 705 Rosslyn, Virginia 22209 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida 32399-1741 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Commissioners Citrus County 110 North Apopka Avenue Inverness, Florida 34450-4245 Mr. Michael J. Annacone Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Daniel L. Roderick Director Site Operations Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Senior Resident Inspector Crystal River Unit 3 U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River, Florida 34428 Mr. Terry D. Hobbs Manager, Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 David T. Conley Associate General Counsel II - Legal Dept.
Progress Energy Service Company, LLC Post Office Box 1551 Raleigh, North Carolina 27602-1551