3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

ML053550365
Person / Time
Site:	Crystal River
Issue date:	12/12/2005
From:	Annacone M Progress Energy Florida
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F1205-04
Download: ML053550365 (4)

Text

a, Progress Enfergy Crystal River Nuclear Plant Docket No. 50-302 Operating Ucense No. DPR-72 Ref: 10 CFR 50.46 December 12, 2005 3F1205-04 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report

Reference:

Letter from PEF to NRC, dated November 17, 2004 - Crystal River Unit 3 -

10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Clad Temperature Change Report

Dear Sir:

Florida Power Corporation, doing business as Progress Energy Florida, Inc. (PEF), is providing the attached information pursuant to 10 CFR 50.46(a)(3)(ii). There have been no changes to the peak cladding temperature (PCT) for Crystal River Unit 3 (CR-3) since the last report was submitted in the above referenced letter. Tables stating the PCT for large break and small break loss-of-coolant accidents (LBLOCA and SBLOCA, respectively) are included in the attachment.

If you have any questions regarding this submittal, please contact Mr. Paul Infanger, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.

Sincerely, Mi 1J. Annacone Manager Engineering MJA/pei

Attachment:

Summary of Changes to Evaluation Models and PCT for LBLOCA and SBLOCA xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.

Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428

PROGRESS ENERGY FLORIDA CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/LICENSE NUMBER DPR-72 ATTACHMENT Summary of Changes to Evaluation Models and PCT for LBLOCA and SBLOCA

U. S. Nuclear Regulatory Commission Attachment 3F1205-04 Page 1 of 2 Table 1 - Large Break LOCA Date and Description CR/NCR APCT (0 F') PCT (0 F)

Reference _ _ _ _ _ _ _ _ _ _ _ __ _ _ _

02/15/05 2004 Draft Annual BWOG 50.46 Letter. N/A Mark Mark Mark Mark FANP 47- (This letter is compiled by the BWOG for member utility use.) B10 B-HTP BIO B-HTP 5058337-00 .

0 0 1937 2023 8/2/05, FAB05-715 10 CFR 50.46 LOCA EM Change and PCT Reporting Change - No impact to LBLOCA FANP CR Mark Mark Mark Mark B-HTP fuel analyses. The LBLOCA analyses were applied to break sizes as small as 0.5 2005-2302 B10 B-HTP B10 B-HTP square feet, reduced from 0.75 square feet, due to DNB being predicted at a smaller break size AR 164425164425 0 0 1937 2023 for B-HTP fuel.

fultive ahftur-and sti m= ofibt iagn-fiidfh iRpor4) Annual e t

---

IaAsoi____i

=

Mark BIO0 Mark B-HTP 0

M B131 11937 B-HTPI 2023

U. S. Nuclear Regulatory Commission Attachment 3F1205-04 Page 2 of 2 Table 2 - Small Break LOCA Date and Description CR/NCR APCT (OF) PCT (0F)

Reference 02/15/05 2004 Draft Annual BWOG 50.46 Letter. N/A Mark Mark Mark Mark FANP 47- (This letter is compiled by the BWOG for member utility use.) BlO B-HTP BIO B-HTP 5058337-00 0 0 1400 1248 8/2/05, FAB05-715 10 CFR 50.46 LOCA EM Change and PCT Reporting Change - This evaluation concluded FANP CR Mark Mark Mark Mark that SBLOCA break sizes greater than 0.3 square feet would predict initial DNB for Mark 2005-2302 B 10 B-HTP B 10 B-HTP B-HTP fuel. The SBLOCA EM method was modified to include consideration of the two AR 164425164425flow-direction dependent terms via an overall multiplier on the B-HTP SBLOCA CHF correlation. After inclusion of the flow-direction terms, early DNB is predicted for break sizes greater than 0.5 square feet, therefore, the transition break size between LBLOCA and SBLOCA analyses was changed from 0.75 square feet to 0.5 square feet.

There is a 0 degree F change in the SBLOCA PCT for the Mark B-HTP fuel because the limiting break size did not experience initial clad DNB. The Mark B-10 fuel analysis is unaffected by this change.

0 0 1400 1248

_V___ 1q/04}Annual eo - - =X Mark Mark, Mark Mark,

_____ _-__ CB _, - . I . 3-HT RIO B-IIT_

I=-- ____________Ad=_______ - - -A- -;- - _OIf - 1400 1248