ML19310A210
| ML19310A210 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco  |
| Issue date: | 01/17/1980 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | Benaroya V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8006060283 | |
| Download: ML19310A210 (3) | |
Text
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UNITED STATES 3' '
NUCLEAR REGULATORY COMMISSION 2 yk; s.q i
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JAN 17 E0 i
Cocket ;os.: 50-259, 270, 287 50-302, 50-312, 50-313, 50-3t6 4
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MEMORANDUM FOR:
". Senaroya, Chief Auxiliary Systems Branch, OSS FROM:
R.. A. Capra, Project Manager Standardization Branch, DPM THRU:
pr.W. F. Ka'ne, Acting Chief
- 1. )-
Standardization Branen, DPM
SUBJECT:
AUXILIARY FEE 0 WATER (AFW) RELIA 3ILITY ANALYSIS i
FOR BA3C0K & WILCOX OPERATING PLANTS As part of demonstrating compliance with the long-term portion of the confirmatory snutdown Orders issued to the Bf4 operating plants in May 1979, the Bulletins & Orders Task Force directed each of the B&W licensees to perform an AFW reliability analysis. The purpose of the requirement was to take an overall view of the AFW system on each plant in order to (1) identify, through reliability based insights, dominant contributors to AFW system unreliability and (2) assess the relative reliability of B&W operating plant AFW systems.
From the results of the analysis it would be possible to determine which com-r ponents or portions of the AFW system would need further improvement.
Attached are the following documents:
1 4
1.
" Auxiliary Feedwater System Reliability Analyses: A Generic Report for Babcock & Wilcox Plants" BAW-1554 December 1979 (Note: Contains revised pages #19 + B-4.)
2.
" Emergency Feedwater System Reliability Analysis'for the Oconee Nuclear Generating Station Unit Nos. 1, 2, 3 Revision 1, tiovemoer 1979" 3.
" Emergency Feedwater System Reliability Analysis for the Arkansas Nuclear One Nuclear Generating Station ' hit No.1, Revision 1 December 1979" 4.
" Auxiliary Feedwater System Reliability Analysis for the Rancho Seco Nuclear Generating Station Unit No. 1 December 1979" 5.
" Auxiliary Feedwater System Reliability Analysis for Crystal River Unit No. 3 October 1979" 6.
" Auxiliary Feedwater System Reliability Analysis for the Davis-Sesse Nuclear Generating Station Revision 1 tiovember 1979" It is requested that the Auxiliary Systems Branch take the lead on a tinely review of these documents.
The review will involve a coordinated effor: cn :ne part of ASB, ICS3, FA3 anc 55.
In accition, any formal correspondence,either from the licensees or to :he licensees, will take place through CRE it.
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U V. Senaroya In meetings with the licensees regarding the submission of these reports, I had requested that in addition to forwarding the S&W generic evaluation anc their individual plant-specific analysis, they were to address what actions tney were taking to imorove tne reliacility of tne AFW system. The purpose of this request was to consolidate in one place all of the AFW system modifications and upgrades. As I told the licensees, this cortion of their submittals was to include all proposed system modifications based upon four sources:
1.
Any specific comitments made by the licensee to upgrade the AFW system, based upon the long-tenn requirements of the May 1979 Orders; i
2.
Any necessary system upgrades to comply fully with Sections 2.1.7a and 2.1.7b of fiUREG-0573; 2.
Any system upgrades or modifications as a result of the identification of dominant failure contributors in the AFW reliability analysis; and, 4.
Any applicable staff recomendations icentified in Appendix III to the W and C-E generic reports (TCREG-0611 and tiUREG-0635, respectively;.
However, most of the licensees' submittals do not contain this consolidated list ofsystemmodificationsandupirades. Therefore. I recommend that durino the review of the reliability analyses, we take into account the acti.ons reovired by the.0rders, i;UREG-0573, and the W and C-E Goneric Reoorts.
Based on this recommendation, it is requested that the end product of this re.iew include:
1.
A staff evaluation of the S&W Generic AFW Reliability Analyses; 2.
A plant-specific evaluation for each licensees' AFW Reliability Analysis;
- and, 3.
A ccmplete list of required system upgrades for each licensee based upon items 1 through 4 identified above. This list should also include a reco= ended implementation schedule.
My recomended priority for perfoming the individual plant reviews is as follows:
1.
Rancho Seco 2.
Oconee 1, 2 & 3 3.
Crystal River 3 4.
A'iO-1 5.
Davis-Besse 1 Based upon the large number of high priority items presently under review, we will have to negotiate a satisfactory review schedule with all of the branches involved.
It is requested, however, that the Rancho Seco review be completed by January 31, 1930. The hearing on Rancho Seco is scheduled to commence on February 26, 1930 and I would prefer to have all modifications identifiM and scheduled prior to the start of the hearing.
I am forwarding a copy of this memorandum to OR3 #4, 1053 and PAS for their infor-mation; however, I am sending you four copies of eacn enclosure for your control and distribution for the review.
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P12asa nota, uhan uorking on these reports, time is charged to the Soc %at nuc.cor cf the facility, TACS-5194, and Activity Code R-31.
If you have ad:itional questions, please contact n2 at extension 2/745.
ca.istrel sicned tr*
R.
- n. Capra, Proj2ct 'anager Standardi:stion Sranch Division of Project Manage:r.ent l'
-s Inclosures:
1.
Ltr from Duke Po.:cr dtd 12/21/79 2.
Ltr from Arkansas Pouer & Light dtd 12/20,;9 3.
Ltc from S:PJD dtd 12,1;/~9 f
4 Ltr frca Florida Po..er atd 12/2/,19
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5.
Ltr fro; IcieJo Rison C;.:pany dtj 01..a.:.
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cc:
C. T.cid, GUT.
- . Taylor, PAS l
- 7.. Satterfi.ald, ICSB i
Distribution:
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