ML080930281
| ML080930281 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/17/2008 |
| From: | Farideh Saba NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Young D Progress Energy Co |
| Saba F, NRR/DORL/LPL4, 301-415-1447 | |
| References | |
| TAC MD6044 | |
| Download: ML080930281 (8) | |
Text
April 17, 2008 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION, LICENSE AMENDMENT REQUEST NO. 299, REVISON 0, TECHNICAL SPECIFICATION CHANGES REGARDING CONTROL ROOM HABITABILITY (TAC. NO. MD6044)
Dear Mr. Young:
By letter dated July 12, 2007, the Florida Power Corporation submitted an application to revise the Crystal River Unit 3, Improved Technical Specifications related to control room envelope habitability in accordance with Technical Specification Task Force (TSTF) standard technical specification change, TSTF-448, Revision 3. The staff determined that additional information is needed from the applicant in order to complete the review. Attached is the staff=s request for additional information.
Please respond to the enclosed questions within 30 days of the date of this letter. Please contact me at 301-415-1447, if you have any questions on this issue.
Sincerely,
/RA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
As stated cc w/enclosures: See next page
April 17, 2008 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION, LICENSE AMENDMENT REQUEST NO. 299, REVISON 0, TECHNICAL SPECIFICATION CHANGES REGARDING CONTROL ROOM HABITABILITY (TAC. NO. MD6044)
Dear Mr. Young:
By letter dated July 12, 2007, the Florida Power Corporation submitted an application to revise the Crystal River Unit 3, Improved Technical Specifications related to control room envelope habitability in accordance with Technical Specification Task Force (TSTF) standard technical specification change, TSTF-448, Revision 3. The staff determined that additional information is needed from the applicant in order to complete the review. Attached is the staff=s request for additional information.
Please respond to the enclosed questions within 30 days of the date of this letter. Please contact me at 301-415-1447, if you have any questions on this issue.
Sincerely,
/RA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosures:
As stated cc w/enclosures: See next page Distribution:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMFSaba RidsOgcRp RidsNrrLACSola (Hard Copy)
RidsAcrsAcnwMailCenter RidsRgn2MailCenter RidsNrrDorlDpr RDennig ADAMS ACCESSION: ML080930281 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA SCVB/BC LPL2-2/BC NAME FSaba CSola RDennig TBoyce DATE 04/16/08 04/16/08 04/17/08 04/17/08 OFFICIAL RECORD
Florida Power Corporation Crystal River Nuclear Plant, Unit 3 cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042 Mr. Michael J. Annacone 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. Stephen J. Cahill Engineering Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Jon A. Franke 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 Ms. Phyllis Dixon 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 Mr. Daniel L. Roderick Vice President, Nuclear Projects &
Construction Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. David Varner Manager, Support Services - Nuclear Crystal River Nuclear Plant (SA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708
Enclosure REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST No. 299, REVISION O CRYSTAL RIVER NUCLEAR PLANT UNIT 3 DOCKET NO. 50-302, LICENSE NO. DPR-72 After reviewing the Florida Power Corporation (FPC) License Amendment Request No. 299, dated July 12, 2007, related to the technical specification change to address control room habitability using Technical Specification Task Force (TSTF) Traveler TSTF-448, Revision 3, the staff has determined that additional information is needed to complete the review.
- 1. TSTF-448, Control Room Habitability, was developed for plants with pressurized control room envelopes (CREs). You stated that your plant has a non-pressurized CRE.
Note that in the programs and manuals section of the standard technical specifications (STS) as modified by TSTF-448, Revision 3, paragraph (d) of Section 5.5.18, Control Room Envelope Habitability Program, specifies a differential pressure (dp) test to be conducted between performances of inleakage testing for the purpose of providing input to a periodic assessment of the CRE boundary. The NRC staff recognizes that non-pressurized CREs may not be able to conduct a dp test; nevertheless, TSTF-448 includes a requirement for a method to collect data that will serve as input to a periodic assessment of the CRE boundary. This position is supported by the technical analysis section of TSTF-448, Revision 3 on page 8 where an explanation of the basis for paragraph (d) is provided. Consequently, the staff is requesting that you provide a method to collect data, and an explanation of how it is used and trended as input to a periodic assessment of your CRE boundary. The method should, to the extent practicable, provide information that can be used in a manner similar to the manner in which the information is to be used that is requested by paragraph (d) of Section 5.5.18 of the STS as modified by Revision 3 of TSTF448.
- 2. TSTF-448 revised REQUIRED ACTION, item B2 of the STS TS 3.7.10, Control Room Emergency Ventilation System (CREVS), to state that Verify mitigating actions ensure CRE occupant exposures to radiological. Chemical and smoke hazards will not exceed limits. During development of Revision 3 to TSTF-448, it was agreed that smoke requirements were qualitative rather than quantitative. In the NRC meeting minutes that agreed to this change (Agencywide Documents Access and Management Systems Accession No. ML061310293), it was noted that this was acceptable, because general qualitative requirements for protecting CRE occupants from smoke challenges are retained in the first paragraph of the proposed STS 5.5.18, along with a licensing basis discussion in the proposed Section of B 3.7.10, "Applicable Safety Analyses," that together adequately address the licensing requirements for protecting CRE occupants from smoke. Also, the TSTF-448 bases for REQUIRED ACTION B.2 state that During the period that the CRE boundary is considered inoperable, action must be initiated to implement mitigating actions to lessen the effect on CRE occupants from the potential hazards of a radiological or chemical event, or a challenge from smoke. Actions must be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to verify that in the event of a DBA [design-basis accident], the mitigating actions will ensure that CRE occupant radiological exposures will not exceed the calculated dose of the licensing basis analyses of DBA consequences, and that CRE occupants are protected from hazardous chemicals and smoke. These mitigating actions (i.e., actions that are taken to offset the consequences of the inoperable CRE boundary) should be preplanned for implementation upon entry into the condition, regardless of whether entry is intentional or unintentional.
The licensee, in its letter dated July 12, 2007, has proposed to remove the words chemical and smoke hazards from the Required Action. Although, licensee addresses chemical hazard analysis and the mitigating actions that will be performed two minutes after initial detection, the licensee does not address the requirements for protecting CRE occupants from smoke challenges or chemical hazards in the proposed TS 5.6.2.21, Control Complex Habitability Envelope Integrity Program. The Crystal River proposed TSs address the radiological protection, but not protection from hazardous chemicals or smoke challenges. Please describe as part of the TSs, how you will verify that the mitigating actions implemented in REQUIRED ACTION, item B.2 protect CRE occupants from chemical hazards and smoke hazards with one or more CREVS trains inoperable due to inoperable CRE boundary.