ML022130531

Crystal River Unit 3 - Request for Additional Information Proposed License Amendment Request No. 270, Revision 0, Power Uprate to 2568 Mwt

ML022130531
Person / Time
Site:	Crystal River
Issue date:	08/01/2002
From:	Goshen J NRC/NRR/DLPM/LPD2
To:	Young D Florida Power Corp
References
TAC MB5289
Download: ML022130531 (5)

Text

August 1, 2002 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing and Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 REQUEST FOR ADDITIONAL INFORMATION RE: PROPOSED LICENSE AMENDMENT REQUEST NO. 270, REVISION 0, POWER UPRATE TO 2568 MWT (TAC NO. MB5289)

Dear Mr. Young:

By letter dated June 5, 2002 (3F0602-05), you submitted an amendment application to revise the Crystal River Unit 3 (CR-3) Improved Technical Specifications Section 1.1 and License Condition 2.C.(1) to allow operation up to 2568 MWt. The enclosed Request for Additional Information (RAI) was previously discussed with your staff in a July 24, 2002, telephone conference call.

For the staff to complete its review on schedule, your response to this RAI is requested no later than August 13, 2002. This date was mutually agreed upon in a telephone conversation with CR-3 personnel on July 24, 2002. If circumstances result in the need to revise the target date, please call me at the earliest opportunity at 301-415-1437.

Sincerely,

/RA/

John M. Goshen, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

Request for Additional Information cc w/encl: See next page

REQUEST FOR ADDITIONAL INFORMATION POWER UPRATE TO 2568 MWT CRYSTAL RIVER UNIT 3

1. As seen in Section 4.12.1 of its submittal dated June 5, 2002, Florida Power Corporation (FPC, the licensee) did not perform containment integrity analyses for Crystal River, Unit 3 . FPC stated in the submittal that the original calculations that provided the mass and energy release data for the reactor building pressure analysis was performed, but were not located. However, FPC did not explain in the submittal whether they have performed a long-term Loss of Coolant Accident (LOCA) analysis for the uprated power to determine the acceptability of the containment safeguards systems to mitigate the consequences of a hypothetical large break LOCA. The staff needs this information to perform its review. Please provide information for the reactor building integrity analysis.

Discuss the assumptions, computer code used, and calculation results for the containment accident pressure responses at the stretch rated power level.

2. Section 4.8.1 of FPCs June 5, 2002, submittal states that the main steam system is not impacted by the uprate. FPC should explain whether the main steam system and its components to operate at 2568 Mwt were enveloped by the original design. Please provide information on maximum flow rate and steam pressure corresponding to the thermal power rate originally designed. Explain whether the safety relief valves are capable to support the operation at the stretch power conditions with increased flow rate.

3. Section 4.8.18 of FPCs June 5, 2002, submittal states that the nuclear services and decay heat seawater (RW) system provides cooling water to the nuclear services closed cycle cooling (SW) system and decay heat closed cycle cooling (DC) system for heat removal during accidents and normal operation. FPC indicated in the submittal that the power uprate has no impact on this system based on its accident analyses. However, at uprated power level, the plant heat discharges to the RW system during normal operation and after accidents increase. The RW system draws seawater from the Gulf of Mexico to cool these safety-related cooling systems. The seawater temperature in the summer for the heat sink is normally higher in the Gulf area. Therefore, at the stretch rated power level, the service water temperature in SW and DC systems will increase from current level. Please explain whether the temperature variation of heat sinks resulting from weather changes was considered in the accident analysis.

4. FPC did not evaluate the effects of the proposed stretch rated power on equipment qualification to meet 10 CFR 50.49 requirements. Since this is a license amendment for power uprate, the licensee is required to confirm that the temperature profile previously approved for equipment qualification bounds the environmental conditions resulting from LOCA or Main Steam Line Break at the higher power level.

5. In its June 5, 2002, submittal FPC stated that it used the following references in its evaluaton:

5. FRA-ANP 86-1266133-01, CR-3 PT Fluence Analysis Report - Cycles 7-10

6. FRA-ANP 32-5013936-00, Adjusted Reference Temperature for 32 EFPY for CR-3 Power Uprate The staff requests these documents in order to complete the evaluation on the changes on pressure vessel fluence.

ENCLOSURE

August 1, 2002 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing and Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3 REQUEST FOR ADDITIONAL INFORMATION RE: PROPOSED LICENSE AMENDMENT REQUEST NO. 270, REVISION 0, POWER UPRATE TO 2568 MWT (TAC NO. MB5289)

Dear Mr. Young:

By letter dated June 5, 2002 (3F0602-05), you submitted an amendment application to revise the Crystal River Unit 3 (CR-3) Improved Technical Specifications Section 1.1 and License Condition 2.C.(1) to allow operation up to 2568 MWt. The enclosed Request for Additional Information (RAI) was previously discussed with your staff in a July 24, 2002, telephone conference call.

For the staff to complete its review on schedule, your response to this RAI is requested no later than August 13, 2002. This date was mutually agreed upon in a telephone conversation with CR-3 personnel on July 24, 2002. If circumstances result in the need to revise the target date, please call me at the earliest opportunity at 301-415-1437.

Sincerely,

/RA/

John M. Goshen, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

Request for Additional Information cc w/encl: See next page DISTRIBUTION: PDII-2 Reading RidsNrrPmJGoshen JGuo (e-mail) RidsRgn2MailCenter(LWert) RidsOgcRp PUBLIC RidsNrrDlpmLpdii2(KJabbour) RidsAcrsAcnwMailCenter FAkstulewics (email) BClayton (Hardcopy) SWeerakkody (e-mail)

ADAMS ACCESSION NO. ML022130531 OFFICE PDII-2/PM PDII-2/LA PDII-2/Acting SC NAME JGoshen BClayton KJabbour DATE 7/24/02 7/27/02 7/25/02 OFFICIAL RECORD COPY

Mr. Dale E. Young CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation cc:

Mr. R. Alexander Glenn Chairman Associate General Counsel (MAC-BT15A) Board of County Commissioners Florida Power Corporation Citrus County P.O. Box 14042 110 North Apopka Avenue St. Petersburg, Florida 33733-4042 Inverness, Florida 34450-4245 Mr. Jon A. Franke Ms. Sherry L. Bernhoft Plant General Manager Manager Regulatory Affairs Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2H) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Michael A. Schoppman Mr. Daniel L. Roderick Framatome ANP Director Site Operations 1911 North Ft. Myer Drive, Suite 705 Crystal River Nuclear Plant (NA2C)

Rosslyn, Virginia 22209 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. William A. Passetti, Chief Department of Health Senior Resident Inspector Bureau of Radiation Control Crystal River Unit 3 2020 Capital Circle, SE, Bin #C21 U.S. Nuclear Regulatory Commission Tallahassee, Florida 32399-1741 6745 N. Tallahassee Road Crystal River, Florida 34428 Attorney General Department of Legal Affairs Mr. Richard L. Warden The Capitol Manager Nuclear Assessment Tallahassee, Florida 32304 Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Mr. Craig Fugate, Director Crystal River, Florida 34428-6708 Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100