ML021290207
| ML021290207 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/09/2002 |
| From: | Goshen J NRC/NRR/DLPM/LPD2 |
| To: | Young D Florida Power Corp |
| Goshen, JM, NRR/DLPM, 415-1437 | |
| References | |
| TAC MB2499 | |
| Download: ML021290207 (4) | |
Text
May 9, 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. 263, REVISION 0, RELOCATION OF REACTOR COOLANT SYSTEM PARAMETERS TO THE CORE OPERATING LIMITS REPORT AND 20 PERCENT STEAM GENERATOR TUBE PLUGGING (TAC NO. MB2499)
Dear Mr. Young:
By letter dated July 24, 2001 (3F0701-11), you submitted an amendment application to revise the Crystal River Unit 3 (CR-3) Improved Technical Specifications Tables 3.3.1-1, 3.4.1, and 5.6.2.18 to relocate the reactor coolant system parameters to the Core Operating Limits Report and to increase the steam generator (SG) tube plugging limit to 20 percent. The staff is currently reviewing your request, and the reviewers have determined that additional information is needed. The questions, listed below, were previously discussed with your staff in an April 29, 2002, telephone conference call.
1.
Explain how the originally licensed feedwater flow rate of 5.4E6 lb/hr was determined.
Please include an explanation of the SG tube plugging percentage used in this determination.
2.
The feedwater flow rate to each SG is a safety system setpoint. This number is not specifically stated in the CR-3 Improved Technical Specifications. Explain how this value is controlled on a cycle-specific basis, and how the margin to the original licensed maximum value is determined.
3.
Explain in more detail the derivation of the cross-flow velocity used in the original flow-induced vibration calculations referenced on page 3 of Framatone 51-5000475-01.
4.
Explain in detail the correlation between 20-percent tube plugging and the stated corresponding increased value in cross-flow velocity. Provide a description of the methodology used in this correlation.
5.
Attachment F, page 15, paragraph 4, to your letter of July 24, 2001, is very confusing.
Since there is a specific maximum flow rate per generator previously analyzed, why is the asymmetric condition of 25/10 discussed? The paragraph also states that feedwater flow to the lesser plugged generator may need to be limited. This appears not to be relevant to the flow-induced vibration discussion in this section. Please clarify this. If this information is relevant to this section please explain the statement concerning the feedwater flow limitation to the lesser plugged SG for the worst case asymmetric distribution with 20-percent tube plugging.
D. Young For the staff to complete its review on schedule, your response is requested within 30 days from your receipt of this letter. This date was mutually agreed upon in a telephone conversation with CR-3 personnel on April 29, 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 cc: See next page
D. Young For the staff to complete its review on schedule, your response is requested within 30 days from your receipt of this letter. This date was mutually agreed upon in a telephone conversation with CR-3 personnel on April 29, 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 cc: See next page DISTRIBUTION:
P Chen (e-mail)
PUBLIC KManoly (email)
PDII-2 Reading RidsRgn2MailCenter (RMusser, Acting)
RidsNrrDlpmLpdii2 (TKoshy)
BClayton (Hardcopy)
RidsNrrPmJGoshen RidsOgcRp RidsAcrsAcnwMailCenter ADAMS ACCESSION NO.ML021290207
- see previous concurrence OFFICE PDII-2/PM PDII-2/LA EMEB/SC PDII-2/Acting SC NAME JGoshen BClayton KManoly*
T Koshy DATE 05/06/02 05/06/02 05/03/02 05/06/02 OFFICIAL RECORD COPY
Florida Power Corporation CRYSTAL RIVER UNIT NO. 3 GENERATING PLANT cc:
Mr. R. Alexander Glenn Associate General Counsel (MAC-BT15A)
Florida Power Corporation P.O. Box 14042 St. Petersburg, Florida 33733-4042 Mr. Daniel L. Roderick Plant General Manager Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708 Mr. Michael A. Schoppman 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. Joe Myers, 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 Ms. Sherry L. Bernhoft Manager Regulatory Affairs Crystal River Nuclear Plant (NA2H) 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. Richard L. Warden Manager Nuclear Assessment Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, Florida 34428-6708