ML20154A730
| ML20154A730 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/29/1988 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| Shared Package | |
| ML20154A733 | List: |
| References | |
| TASK-124, TASK-OR NUDOCS 8805160135 | |
| Download: ML20154A730 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
- E WASHING TON, D. C. 20555 April 29, 1988 Docket No. 50-302 Mr. W. S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN
- Manager, Nuclear Licensing P.O. Box 219 Crystal iliver, Florida 32629
Dear Mr. Wilgus:
SUBJECT:
CRYSTAL RIVER, UNIT 3 - RESOLUTION OF GI-124, AUXILIARY FEE 0 WATER (AFW) SYSTEM REllABILITY An AFW system review group was formed to prepare an overall reliability assess-ment for each of the seven plants with a two-train AFW system to resolve Generic issue (GI)-124, Auxiliary Feedwater System Reliability.
This effort included a plant-specific review and an on-site audit of the AFW system, and included calculated estimates of the reliability of the AFW system, given various initi-ating events. The staff selected this approach for resolving GI-124 rather than a strictly analytical approach because the staff believed that a first-hand audit of the AFW system design and operation more directly addressed the root causes of AFW system unavailability and unreliability.
The resolution approa-h adopted by the AFW system review team relied on an audit of several parameters tMt directly or indirectly affect the availability and reliability of the AFW syste'n.
These parameters include design configurations; maintenance, surveillance, 6aJ se: ting procedures and practices; operating procedures; personnel training; system bya-operating experience; instrumen-tation and control; and environment and a%
bility for operator recovery Section 10.4.9, AFW System Numerical Reliabili:v Criterion (10~glan (SRg)per actions following potential malfunctions.
%.tandard Review to 10~
demand) served as the basis for concluding that the AFW system was acceptably reliable in the seven plants of concern.
Because the SRP criterion specifies consideration of compensating factors such as otner reliable decay heat removal methods to justify a larger AFW system unavailaoility, the AFW system review team evaluated compensatory features as part of its effort.
The enclosed report documents the results of the staff review of the AFWS for Crystal River, Unit 3.
Based on that review, the staff concluded that improve-ment in the reliability of the AFW system and secondary side decay heat removal capability was warranted. This conclusion was based on the staff's evalua of ghe AFW system reliability, which indicated a reliability below the to 10~ per demand acceptance criterion, and the staff's determination that the uncertainties and disadvantages associated with the use of the feed-and-bleed decay heat removal method cannot justify it as a suitable compensatory feature.
The staff concludes that credit for feed-and-bleed as a compensatory measure in the evaluation of AFW system reliability is inappropriate.
8805160135 880429 fDR ADOCK 05000302 PDR
e Mr. W. S. Wilgus April 29, 1988 You were informed of these conclusions and responded by letter dated March 25, 1988 after meeting with the staff on March 11, 1988 to discuss staff concerns.
3 In your response, you comitted to install an additional means of secondary side decay heat removal.
In a meeting on March 30, 1988, you described the design bases for an auxiliary feedwater pump to satisfy this comitment. We will review the design of this pump to assure that its installation provides L
adequate reliability enhancement.
Your proposed schedule for submittal of the final design and for implementation should be submitted in May 1988, as discussed at the meeting of March 30.
With implementation of this comitment, the staff concludes that the Crystsl River, Unit 3 AFW system and secondary side decay heat removal capat'ility will meet the SRP criterion.
The report also identifies other oceas where enhancements can be made in AFW system reliability and decay heat removal capability.
Please consider these recomendations and inform us within 60 days of your planned disposition of each of these items.
The reporting and recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required pursuant to P.L.96-511.
Sincerely, Originial Signed By:
Steven A. Varga, Director Division of Reactor Projects-1/11 Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION 1
J D5 H W FTTe-J. Partlow NRC & Local PORs ACRS (10) i PD22 Reading Gray File l
S. Yarga DRP/RF G. Lainas D. Miller H. Silver OGC-WF i
E. Jordan
- See previous concurrence l
- LA:PDil-2
- FM:POII-2
- D:P0ll-2 N / SAD DMiller HSilver:bg HBerkow Cdhnas AThadani I
l 4/Q' )'88 4/f]/88 4/ /88 4/ /88 4/ /88 88 1
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Mr. W. S. Wilgus You were informed of these conclusions and responded by letter dated March 25, 1988 after meeting with the staff on March 11, 1988 to discuss staff concerns, in your response, you committed to install an additional means of secondary side decay heat removal.
The specific design and schedule for this additional source will be developed in the near future.
With implementation of this commitment, the staff cencludes that the Crystal River, Unit 3 AFW system and secondary side decay heat removal capability will meet the SRP criterion.
The report also identifies other areas where enhancements can be made in AFW system reliability and decay heat removal capability.
Please consider these recommendations and inform us within 60 days of your planned disposition of each of these items.
Based on the above, the staff considers GI-124 to be resolved for Crystal River, Unit 3.
The reporting and recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore. 0MB clearance is not required pursuant to P.L.96-511.
Sincerely, Steven A. Varga, Director Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page DISTRIBUTION DoWit7ITT NRC & Local PDRs PD22 Reading S. Varga G. Lainas D. Miller H. Silver 0GC-WF E. Jordan J. Partlow ACRS (10)
Gray File DRP/RF
- See previous concurrence
- LA:PDil-2
- PM:PDII-2 D:PD ADR DRP Chiller HSilver:bg HBer)cw Glainas SVarga 4/ /88 4/ /88 4/q/88 4/ /88 4/ /88 i
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Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant CC:
Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Nr. P. F. McKee Mr. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Board of County Comissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsuo Mr. E. C. Simpson Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Florida Power Corporation Support 1700 Rockville Pike, Suite 525 P.O. Box 219 Rockville, Maryland 20852 Crystal River, Florida 32629 Resident inspector U.S. Nuclear Regulatory Comission 15760 West Powerline Street Crystal River, Florida 32629 Regional Administrator, Region 11 U.S. Nuclear Regulatory Comission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Jacob Daniel Nash Office of Radiation Control Departnent of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Aftairs The Capitol Tallahassee, Florida 32304 1
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