ML20207L350
| ML20207L350 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/04/1999 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | Cowan J FLORIDA POWER CORP. |
| References | |
| TAC-MA0667, TAC-MA667, NUDOCS 9903180092 | |
| Download: ML20207L350 (4) | |
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Mr. John Pcui Cowan Vipe President, Nuclear Oper tions Florida Power Corporation March 4, 1999 ATTN: Manager, Nuclear Licensing (SA2A)
Crystal River Energy Complex 15760 W. Power Line Street j
Crystal River, Florida 34428-6708 l
SUBJECT:
CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION -
LICENSE AMENDMENT REQUEST 222 RELATED TO CONTROL ROOM EMERGENCY VENTILATION SYSTEM (TAC NO. MA0067)
Dear Mr. Cowan:
in a submittal dated July 30,1998, Florida Power Corporation submitted a license i
amendment request which proposed changes to the Improved Technical Specifications for the Control Room Emergency Ventilation System and to the Ventilation Filter Test Program at Crystal River Unit 3. In order to complete our review of this request, we require additional l
information as specified in the enclosure to this letter. Please provide the requested information within 30 days of receipt of this letter. This Request for Additional Information and requested submittal date were discussed with Mr. Sidney Powell of your staff.
Sincerely, Ori ein=1 Leonam A...s-w ie s, or Project Manager Project Directorate ll-3 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket 50-302
Enclosure:
Request for AdditionalInformation cc w/ encl: See next page l
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OFFICIAL RECORD COPt PDR ADOCK 05000302-a p
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Mr. John Psul Cowan CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation cc:
Mr. R. Alexander Glenn Ms. Sherry L. Bemhoft, Director i
Corporate Counsel Nuclear Regulatory Affairs (SA2A)
Florida Power Corporation Florida Power Corporation MAC-ASA Crystal River Energy Complex P.O. Box 14042 15760 W. Power Line Street St. Petersburg, Florida 33733 4042 Crystal River, Florida 34428-6708 Mr. Charies G. Pardee, Director Senior Resident inspector Nuclear Plant Operations (NA2C)
Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission Crystal River Energy Complex 6745 N. Tallahassee Road 15760 W. Power Line Street Crystal River Florida 34428 Crystal River, Florida 34428-6708 Mr. Gregory H. Halnon Mr. Michael A. Schoppman Director, Quality Programs (SA2C)
Framatome Technologies Inc.
Florida Power Corporation 1700 Rockville Pike, Suite 525 Crystal River Energy Complex Rockville, Maryland 20852 15700 W. Power Line Street Crystal River, Florida 34428-6708 Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circlel, SE, Bin #C21 Tallahassee, Florida 32399-1741 Attomey General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. Joe Myers, Director Divis!on 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 invemess, Fiorida 34450 4245
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i REQUEST FOR ADDITIONAL INFORMATION EQP2 LICENSE AMENDMENT REQUEST NO. 222 1.
In Florida Power Corporation's (FPC's) license amendment request No. 222 dated July 30,1998, FPC proposed a new action statement for Technical Specification 3.7.12, ControlRoom Emergency Ventilation System, that would allow operation to continue for up to seven days with a breach in the Control Complex Habitability 2
Envelop less than or equal to one square foot in excess of the limit, or 179 in. The 2
CR-3 Control Room Habitability Report only supports a breach of 35.5 in. The NRC staff requests the following additionalinformation:
a.
The radiological analyses included in the Control Room Haoitability Report determined 2
that a breach of 35.5 in could be tolerated and not exceed the criteria of General Design Criterion-19. No analyses of control room doses were performed at the proposed breach size. Limiting parameter values in the technical specifications are supposed to be based on the plant design basis analyses. The FPC qualitative analysis does not provide the staff with sufficient information to approve this portion of the amendment request. Please provide an evaluation of the radiological consequences of the design basis accidents occurring while a breach of the size proposed in Limiting Condition for Operation (LCO) action 3.7.12.B exists. This should consider the Design Bases Accidents addressed in FPC's Control Room Habitability Report. Personnel actions to seal the breach may be credited in this analysis, provided that the time to affect these actions is conservatively estimated and formal commitments are made to ensure that necessary personnel and equipment are available at all times when LCO action 3.7.12.8 is in effect.
b On Page 6 of 13 of the submittal, FPC states that "This position is similarto one approved for the Waterford-3 Technical Specifications by Ucense Amendment No.
115, issued October 4,1995." The use of Waterford-3 as a precedent does not appear valid due to differences in the configuration of the control rooms (e.g., Waterford employs a zone filtered pressurization design with two widely separated intakes) and differences between the proposed language of the Crystal River Unit 3 (CR-3) technical specification and that approved for Waterford. Please explain why FPC believes that the Waterford proceeding is a valid precedent for the proposed CR-3 amendment given these differences.
2.
FPC's analysis of the fuel handling accident assumes, as an initial condition, that the control room emergency ventilation system (CREVS) is in the emergency (filtered) recirculation mode prior to moving irradiated fuel assemblies. Propcmd action 3.7.12.D (which applies during movement of irradiated fuel) contains a note requiring the CREVS be placed in the emergency recirculation mode if automatic transfer to emergency recirculation is inoperable. Please explain why this statement is required since the accident analysis assumes that the CREVS is in emergency recirculation before irradiated fuelis moved.
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3.
Item M of Table 1 of the Control Room Habitability report appears to contain an error.
The mixing rate is specified as 46,400 cfm. The mixing rate is usually specified as being equal to two times the volume of the unsprayed region per hour. For CR-3 this is 23,200 cfm. FPC calculation M97-0110 Rev. 2 appears to have used 23,200 cfm as the mixing rate. Please resolve this apparent discrepancy.
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