ML19256E147
| ML19256E147 | |
| Person / Time | |
|---|---|
| Site: | Crane, Rancho Seco  |
| Issue date: | 09/20/1979 |
| From: | Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| To: | NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| Shared Package | |
| ML19256E145 | List: |
| References | |
| NUDOCS 7910290297 | |
| Download: ML19256E147 (28) | |
Text
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[pm nucoq%g UNITED STATES yj g
NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555
%v /
September 20, 1979 Docket No. 50-312 FACILITY:
Rancho Seco Nuclear Generating Station LICENSEE:
Sacre.iento Municipal Utility District
SUBJECT:
SUMMARY
OF MEETING HELD ON AUGUST 30, 1979 TO DISCUSS THE PRELIMINARY RESULTS OF THE AUXILIARY FEEDWATER SYSTEM RELIABILITY STUDY FOR RANCHO SECO On August 30, 1979, members of the NRC staff met in Bethesda, Maryland with represt;ntatives of the Sacramento Municipal Utility District (SMUD) and the Babcock & Wilcox Company (B&W) to discuss the preliminary results of the auxiliary feedwater (AFW) system reliability study for the Rancho Seco Nuclear Generating Station.
A list of attendees is provided as Enclosure 1.
BACXGROUND As part of the long-tenn requirements of the Commissio.: Orders issued to each B&W operating plant licensee in May 1979, the licensees are ccmmitted to further review and upgrade their AFW/EFW systems.
In order for each licensee to assess which areas of its AFW/EFW system are in need of improvement, the staff directed that each licensee perfonn a reliability study of its AFW/EFW system. The study is to be of a similar scope as that done by the NRC staff for each of the Westinghouse (W) and Combustion Engineering (CE) operating plants. On August 9, 1979, the NRC staff met with the B&W Owners' Group to discuss the scope and schedule for such a The Owners' Group picked Rancho Seco as the lead plant for the study.
program.
It was agreed to at that meeting that the NRC staff would meet with SMUD and B&W on August 30, 1979 to discuss the preliminary results of that study.
DISCUSSION The meeting was divided into two parts:
(1) a review of the Rancho Seco AFW system and (2) a e.'isesssion of the plant specific reliability anclysis.
Part 1
' Rancho Seco AFW system discussion)
B&W presented a detailed sumary of the Rancho Seco AFW system. Basically, the Rancho Seco AFW systeni is comprised of two separate trains. Each train has a separate suction header connected to the seismic Category I condensate storage tank (CST).
Backup water supplies can be obtained from the Fcisum South Canal or the plant reservoir. Neither of these alternate water sources are classified 12')6 316 7910290 $
. as seismic Category I.
One train utilizes a turbine / motor-driven AFW pump (P-318) and the other train uses a straight motor-driven AFW pump (P-319).
Each of the pumps can supply a total of 840 gpm, with 780 gpm fed to the steam generators (S/G) and 60 gpm recirculated to the high pressure and low pressure condensers. The discharge of each pump is cross-connected through a header containing two nomally open, motor-operated valves. Thus, either pump can be used to supply water to either S/G. Flow control to each S/G is controlled through two parallel paths. Th } 9 9%
4.
Proposed Outline for SMUD Report i
cc w/ enclosures:
See attached
BABC0CK & WILCOX OPERATING PLANTS Mr. William O. Parker Jr.
Vice President - Steam Production Duke Power Company P.O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. William Cavanaugh, III Vice President, Generation a.id Construction Arkansas Power & Light Company Little Rock, Arkansas 72203 Mr. J. J. Mattimoe Assistant General
- rer and Chief Engineer Sacramento Muni i ility District 6201 S Street P.O. Box 15830 Sacramento, California 95813 Mr. Lowell E. Roe Vice President, Facilities Development Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Mr. W. P. Stewart Manager, Nuclear Operations Florida Power Corporation P.O. Box 14042, Mail Stop C-4 St. Petersk Jrg, Florida 33733 Mr. R. C. Arnold Senior Vice President Metropolitan Edison Company 260 Cherry Hill Road Parsippany, New Jersey 07054 Mr. James H. Taylor Manager, Licensing Babcock & Wilcox Company Power Generation Group P.O. Box 1260 Lynchburg, Virginia 24505 1?96 320
acramento Municipal Utility Page 1 o f 2 District Christopher Ellison, Esq.
David S. Kaplan, Secretary and Dian Grueuich, Esq General Counsel California Energy Comission 6201 S Street 1111 Howe Avenue P. O. Box 15830 Sacramento, California 95825 Sacramento, California 95813 Ms. Eleanor L.i. artz Sacramento County California State Office 600 Pennsylvania Avenue, S.E., Rm. 201 Board of' Supervisors 227 7th Street, Room 424 Washington, D.C.
20003 Sacramento, California 95814 Docketine, 2:.d Service Section Office 1f the Secretary U. S. Nuclur Regula ory Commission Washington, D.C.
20555 Michael L. Glaser, Esq.
1150 17th Street, N.W.
Director, Technical Assessment Washington, D.C.
20036 Divisien Office of Radiation Programs Dr. Richard F. Cole (AW-459)
Atomic Safety anc Licensing Board U. S. Eavironmental Protection Agency Panel Crystal Mall #2 U. S. Nuclear Regulatory Comission Arlington, Virginia 20460 Washington, D.C.
20555 U. S. Environmental Protection Agency Mr. Frederick J. Shen Atomic Safety and Licensing Board A Il S CO If1ATOR c a gu Co d d on an sco a ifornia 94111 g
9, Mr. Robert B. Borsum Timothy V. A. Dillon, Esq.
Sabcock & Wilcox Suite 380
!!uclear Power Generation Division 1850 K Street, N.W.
Suite 420, 7735 Old Georgetown Road Washington, D.C.
20006 Eat.Sesda, Maryland 20014 James S. Reed, Esq.
Michael H. Remy, Esq.
Reed, Samuel & Remy 7]7 X $tregt, $gite 40$
Sacramento, California 95814
!.'. ? b 3 2 }
Page 2 of 2 e
Sacramento Municipal Utility District Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Ato.T/ - Safety and Licensing Appeal Board Panel V. S. Nuclear Regulatory Commission Washington, D.C.
20555 fir. Richard D. Castro 2231 K Street Sacramento, California 95814 Mr. Gary Hursh, Esq.
520 Capital Mall Suite 700 Sacramento, California 95814 California Department of Health ATTN: Chief. Environmental Radiation Control Unit Radiological Health Section 714 P Stre. ?.,
Room 498 Sacramento, California 95814
!76 322
ENCLOSURE 1 LIST OF ATTENDEES RANCHO SECO AFW RELIABILITY STUDY MEETING AUGUST 30, 1979 NAME ORGANIZATION S. I. Anderson SMUD (Nuclear Engineer)
R. J. Finnin B&W (Licensi.ig)
W. W. Weaver B&W (Tech. Staff)
R. W. Dorman B&W (Plant Integration)
B. J. Short B&W (Customer Service)
T. M. Novak NRC (Deputy Dir. B&O Task Force)
P. R. Matthews NRC (Section Leader, Systems Group, B&O Task Force)
C. Y. Liang NRC (Systems Group, B&O Task Force)
W. T. LeFave NRC (Systems Group, B&O Task Force)
M. A. Taylor NRC (Probabilistic Analysis Branch)
R. A. Capra NRC (B&W Project Manager, B&O Task Force)
!??6 323
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!?'6 328 t
ENCLOSURE 3 page 1 ASSUMPTIONS / CRITERIA FOR SMUD AFWS RELIABILITY STUDY 1.
Definition of Mission Success -
Flow from at least one pump to at least one steam generator within 5, 15 and 30 minutes.
2.
Assumed validity of NRC - suoplied unreliability data including hardware, human factors, preventive maintenance.
3.
Power Availability -
LMFW - All AC and DC available with probability of 1.0.
LOOP - Most limiting DG is unavailable with a probability of 10-2
. The other generator (typically CG "B") is available with a probability of 1.0 LOAC - Only DC and battery-backed AC is available with a probability of 1.0.
4.
Lines of I 1" were ignored as possible diverted flow paths.
5.
Assumed coupled.1anual initiation of valves with identical function.
i.e.,
valves were assumed both opened manually or both not opened.
6.
Degraded failures were not considered i.e., components were either 100% okay or were considered failed.
(Exception was loss of power to E/p converters re-considered not failed closed).
sulting in 50% valve position Condensate Storage Tank failure probability = 5x10-6 7.
8.
Assumed a single ain for ICS control and initiation with a failure pro-bability of 7x10-
!P6 329
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ENCLOSURE 4 PROPOSED OUTLINE FOR SMUD REPORT ON AUXILIARY FEEDWATER SYSTEM RELIABILITY 1.0 Introduction 1.1 Background - NRC study for W and CE 1.2 Objectives - Comparative reliability assessment, identi-fication of dominant failure contributors 1.3 Scope - 3 cases: LMFW, LOOP and LOAC; 3 times:
5, 15 and 30 minutes; Baseline confiauration: 1 Aunust 1979 1.4 Analysis Technique - Fault tree analysis leadino to reliability insights 1.5 Assumptions and Criteria 1)
Power availability for each case 2)
Criteria for mission success 3)
NRC failure data 4) etc.
2.0 system Descriotion 2.1 Overall AFWS Desian 2.2 Supportina Systems - Including backup water sources 2.3 Power Sources 2.4 Instrumentation and Control - Initiation and Control 2.5 Human Factors - Initiation, backup actions, indications and contols available 2.6 Maintenance / Testing - Frequency, extent, duration 2.7 Tech Spac - Limitations imposed 3.0 Reliability Evaluation 3.1 Comparative Reliability - Table for comparison with W and CE 3.2 Dominant Failure Contributors 3.2.1 LM F'4 3.2.2 LOOP 3.2.3 LOAC 1'96 343