3F1102-06, Response to Request for Additional Information Proposed License Amendment Request 270, Revision 0, Power Uprate to 2568 Mwt.

Response to Request for Additional Information Proposed License Amendment Request #270, Revision 0, Power Uprate to 2568 Mwt.

ML023250278
Person / Time
Site:	Crystal River
Issue date:	11/13/2002
From:	Young D Florida Power Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1102-06, TAC MB5289
Download: ML023250278 (4)

Text

SFlorida Power AProgress Energy Company Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.90 November 13, 2002 3F17102-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - Response to Request for Additional Information Re: Proposed License Amendment Request #270, Revision 0, "Power Uprate to 2568 MWt" (TAC No. MB5289)

References:

1. FPC letter to NRC, dated June 5, 2002, Crystal River Unit 3 - License Amendment Request #270, Revision 0, "Power Uprate to 2568 MWt"

2. FPC letter to NRC, dated September 30, 2002, Crystal River Unit 3 - Response to Request for Additional Information Re: Proposed License Amendment Request

1. 270, Revision 0, "Power Uprate to 2568 MWt" (TAC No. MB5289)

Dear Sir:

During a conference call on November 7, 2002, the NRC staff made a request for additional information (RAI) regarding Florida Power Corporation's (FPC) proposed License Amendment Request #270, "Power Uprate to 2568 MWt" (Reference 1), and the previous RAI response (Reference 2). The Attachment to this letter provides the response to this request.

This letter makes no new regulatory commitments.

If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.

Sincerely, Dale E. Young Vice President Crystal River Nuclear Plant DEY/pei

Attachment:

Response to Request for Additional Information xc: Regional Administrator, Region II Senior Resident Inspector NRR Project Manager 15760 West Power Line Street

• Crystal River, Florida 34428-6708 * (352) 795-6486

U.S. Nuclear Regulatory Commission 3F1 102-06 Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS Dale E. Young states that he is the Vice President, Crystal River Nuclear Plant for Progress Energy; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

Dale E. Young Vice President Crystal River Nuclear Plant The foregoing document was acknowledged before me this _____ day of ,A___, ____

2002, by Dale E. Young.

of Notary Public JANET"sCHRO.DER my COMMISSION # DO 12806

~ EXPIRES June 20, 2006 (Print, type, or stamp Commissioned Name of Notary Public)

Personally 7 Produced Known / -OR- Identification

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ATTACHMENT Response To Request For Additional Information Re: Proposed License Amendment Request #270, Revision 0, Power Uprate to 2568 MWt Response to Request for Additional Information

U.S. Nuclear Regulatory Commission Attachment 3F17102-06 Page 1 of 1 Response to Request for Additional Information NRC Request (per conference call November 7, 2002)

In a previous response to an NRC request for additional information (RAI), dated September 30, 2002, FPC stated in Question 2.b that there had been no significant design changes in the fuel assembly spacer grid since the critical heat flux tests were performed. What modifications have been made and why were they determined not to be significant?

FPC Response The Mark-B series fuel assemblies have used the same spacer grid design (BZ grid) since the 1980's. Only one modification has been made to this design since the critical heat flux (CHF) tests. This change involved replacing the then existing wrap-around weld joint at the comer of the spacer grid with a precision laser butt-weld joint. The comer weld was changed to reduce the chance of catching on other assemblies during fuel moves. This modification does not impact the geometry of the inner portions of the spacer grid and, therefore, does not impact the flow or heat transfer properties of the assembly. This modification was considered to have an insignificant impact on the CHF test results. Therefore, the BWC correlation remains valid for the Crystal River Unit 3 Cycle 13 core design.