ML070470027
| ML070470027 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/23/2007 |
| From: | Stewart Bailey NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Young D Florida Power Corp |
| Bailey S N,NRR/DLPM,415-1321 | |
| References | |
| TAC MD2054 | |
| Download: ML070470027 (5) | |
Text
February 23, 2007 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:
REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST TO IMPLEMENT TSTF-449, CRYSTAL RIVER NUCLEAR PLANT, UNIT 3 (TAC NO. MD2054)
Dear Mr. Young:
By letter dated December 21, 2006, Florida Power Corporation (FPC, the licensee) submitted Revision 1 to License Amendment Request No. 264 for the Crystal River Nuclear Plant, Unit 3.
The amendment would replace the existing steam generator tube surveillance program to one that is consistent with the program proposed by the Technical Specification Task Force (TSTF)
Traveler TSTF-449. The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the staff to complete its review. These questions were sent via e-mail to FPC on January 17, 2007, and discussed with Mr. Paul Infanger, et al., of your staff on January 31, 2007. As discussed with your staff, please provide a response to the enclosed questions within 30 days of the date of this letter in order to allow the NRC staff to complete a timely review of the amendment.
If you have questions about this request, please contact me at (301) 415-1321.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML070470027 OFFICE LPL2-2/PM LPL2-2/LA SCGB/BC LPL2-1/BC NAME SBailey BClayton AHiser LOlshan for AMarinos DATE 2/21/07 2/21/07 2/22/07 2/23/0
REQUEST FOR ADDITIONAL INFORMATION CRYSTAL RIVER NUCLEAR PLANT UNIT 3 LICENSE AMENDMENT REQUEST NO. 264, REVISION 1 STEAM GENERATOR TUBE INTEGRITY TECHNICAL SPECIFICATIONS DOCKET NO. 50-302 By letter dated December 21, 2006, Florida Power Corporation submitted Revision 1 to License Amendment Request No. 264 for the Crystal River Unit 3 Nuclear Generating Plant. The amendment would revise the Technical Specifications (TSs) related to steam generator tube integrity to adopt Technical Specification Task Force (TSTF) Traveler TSTF-449, Steam Generator Tube Integrity.
The Nuclear Regulatory Commission staff has reviewed the December 21, 2006, submittal and determined that clarifications are needed in the following areas:
1.
In your response to Question 8, you indicated that the second sentence of TS 5.6.2.10.4.a.11.b was deleted since it refers to inspection categories that were deleted. Although the inspection categories were deleted, this sentence contained expansion criteria for your inspection that were not captured in your proposal. Please discuss your plans to incorporate this expansion criteria into your proposed TSs (without reference to the inspection categories). In addition, with respect to proposed TS 5.6.2.10.d.8, please discuss your plans to replace degradation of a repair roll with flaw or flaws in a repair roll since TSTF replaced the term degradation with the term flaws.
2.
In your response to Question 1, you indicated that you would remove the exception to the accident-induced-leakage performance criterion. Please discuss your plans to remove similar text from your Bases (refer to page B 3.4-78).
3.
In your response to Question 8, you indicated that an additional sentence was added to clarify the repair criteria for intergranular attack (IGA). In reviewing the proposed text, it does not appear to address the repair criteria for all IGA indications in the first span of Steam Generator B. For example, it only addresses the acceptance criteria for those indications in the Inservice Inspection Surveillance Procedure (and there is no requirement to record the indications in this document). In addition, it does not specify the actions to take when these indications satisfy the repair criteria (i.e., the tubes must be plugged or repaired). Please discuss your plans to clarify the repair criteria for all first span IGA indications. The staff notes that the proposed repair criteria appear identical to the standard 40-percent depth based tube repair criteria and could possibly be deleted.
Enclosure 4.
The proposed structure for TS 5.6.2.10.c could result in misinterpreting the requirements since the first sentence indicates that alternate repair criteria are discussed below and the next sentence is not an alternate tube repair criteria. Please discuss your plans to clarify the requirements. Clarity could be achieved by:
(1) numbering the first sentence (as number 1) and replacing below with in Technical Specification 5.6.2.10.c.3; (2) number the second sentence (as number 2);
(3) numbering the third clause (as number 3) and adding in Technical Specification 5.6.2.10.c.a at the end of the clause; and (4) renumbering 1 and 2 as a and b.
5.
In the second sentence of proposed TS 5.6.2.10.c.2, it would appear that the sentence should read, provided the combined projected leakage from all sources of primary to secondary leakage. Please discuss your plans to clarify this requirement.
6.
In the first sentence of the second paragraph of proposed TS 5.6.2.10.c.2, you indicate that tubes identified with tube end cracking that meet the alternate repair criteria will be added to the existing list of tubes in the surveillance procedure. In TSTF-449, the phrase satisfy the tube repair criteria is used to indicate that an indication exceeds the tube repair criteria (i.e., the tube must be plugged or repaired). However, in the sentence in TS 5.6.2.10.c.2, the phrase meet the alternate repair criteria is used to indicate that if a tube is allowed to remain in service (i.e., it does not exceed the alternate repair criteria), then it should be added to the list of tubes in the surveillance procedure. To ensure consistent terminology throughout this specification, discuss your plans to clarify TS 5.6.2.10.c.2 by indicating that tubes identified with tube end cracking that are allowed to remain in service under the alternate repair criteria will be added to the list.
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.
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