ML20151M697
| ML20151M697 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/16/1985 |
| From: | Richard Lee Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8601020664 | |
| Download: ML20151M697 (33) | |
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UNITED STATES 7.
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555
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DEC 161985 Docket No.: 50-368 LICENSEE: Arkansas Power & Light Company (AP&L)
FACILITY: Arkansas Nuclear One, Unit No. 2 (ANO-2)
SUBJECT:
S1!MMARY OF NOVEMBER 14, 1985 MEETING WITH AP&L AND NRC STAFF REGARDING THE REllABILITY OF THE ANO-2 EMERGENCY FEEDWATER (EFW)
SYSTEM INTRODUCTION At the request of the NRC staff, a meeting was held on November 14,1985 at the NRC offices in Bethesda, Maryland, on the above subject. The purpose of the meeting was to exchange information to establish the level of reliability of the ANO-2 EFW system. Enclosure 1 identifies a list of attendees. Enclosure 2 is a' copy of the viewgraphs that the licensee presented during the meeting.
SUMMARY
The licensee presented the current ANO-2 EFW system confinoration and discussed many upgrades made to the system since the early 1980's. As a result of these upgrades, the ANO-2 EFW system has a reliability which has not allowed a failure of a train since the end of 1981. The ANO-2 EFW system consists of two trains; one includes a motor-driven pump and the other a turbine-driven pump.
With respect to the numerical reliability of the current ANO-2 EFW system, the licensee does not plan to undertake a reliability study until the NRC staff provides additional guidance on this matter. However, the licensee indicated that the ANO-2 EFW system does meet the reliability criterion in the Standard Review Plan (SRP). The reliability criterion in Section 10.4.9 of the SRP allows a larger unreliability of the EFW system if other reliable methods for cooling the reactor core during abnomal conditions are available.
In this regard, the licensee believes that an extraordinary decay heat renoval capability utilizing the large ECCS vent-line which is unique to ANO-2 is available.
In addition, the licensee believes that the ANO-2 EFW system does meet all the applicable regulations and is a highly reliable system as indicated by its past performance. Accordingly, the licensee indicated that their resources would be concentrated on reducing challenges to safety systems, namely, reducing the reactor trip frequency and improving the reliability of the main feedwater system instead of further improving the EFW system which the licensee believes to be a reliable system.
FUTURE WORK The staff gave the licensee an overview of the staff initiatives i'n' this area.
The staff is developing a CRGR pykage t ur,1 reliability in the range of 10 to 10'5 equire all PWRs to have EFW system r
per demand. Most of the PWRs are 8601020664 851216 PDR ADOCK 05000368 p
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4 Mr. John M. Griffin Arkansas Nuclear One Arkansas Power & Light Company Unit No. 2 CC:
Mr. J. Ted Enos, Manager, Licensino Mr. Charlie B. Brinkman, Manaaer Arkansas Power.& Light Company Washington Nuclear Operations P. O. Box 551 C-E Power Systems k
Little Rock, Arkanses 72203 7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. James M. Levine, General Manager Arkansas Nuclear One P. O. Box 608-Russellville, Arkansas 72801 Nicholas S. Reyr. olds. Eso.
Bishop, Liberman, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Suite 700 Washington, D.C.
20036 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 R.yan Plaza Drive, Suite 1000 Arlington, Texas 76011 4
Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 2090 i
Russellville, Arkansas 72801 Mr. Frank Wilson, Director Division of Environmental Health l
Protection Arkansas Department of Health 4815 West Markam Street Little Rock, Arkansas 72201 Mr. Robert B. Borsura Babcock & Wilcox Nuclear Power Generation Division Suite 220 7910 Woodmont Avenue Bethesda, Maryland 20814 f
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ANO-2 EMERGENCY FEEDWATER SYSTEM MEETING ATTENDANCE LIST NAME.
AFFILIATION l~
A. Thadani NRR R. Lee NRR 0..Parr NRR L. Rubenstein NRR G. Edison NRR i
J. Wermfel NRR J.'Raval NRR A. El-Bassioni NRR W. Regan NRR G. Vissing NRR J. Stolz NRR J. Glynn NRR M. Wegner IE D. Allison IE T. Enos AP&L A. Wrape AP&L t
J. McWilliams AP&L D. Howard AP&L W. Craddock AP&L W. Cawthon AP&L D. Williams AP&L l
T. Cogburn AP&L i
R. Borsum B&W R.-Enzinna B&W E. Schmidt NUS l
L. Kroll NUS e
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ANO-2 EMERGENCY FEEDWATER 4
SYSTEM REVIEW NOVEMBER 14, 1985 M
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OPENING REMARKS o
SYSTEM EVOLUTION G DESCRIPTION OF PRESENT SYSTEM
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o RELIABILITY STUDIES 1
o SYSTEM PERFORMANCE 5
o PLANT TRIP REDUCTION PROGRAM o
CONCLUDING REMARKS r
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ANO-2 EFW SYSTEM' DESIGN BASIS
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Diverse, Redundant Motive & Control Power o
Meets APCSB 10-1 N
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A ANO-2 EFW SYSTEM RELIABILITY MODIFICATIONS o
Controlled EFW Turbine (2K3) Start Solenoid Valve Warmup G Roll Open Steam Admission Gate Valve G
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No Overspeed Trips Experienced on Startup Since Modification 0
Electrohydraulic Discharge Control Valve Operators Replaced with Motor r
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RELIABILITY STUDIES D
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1981 REVISION TO STANDARD REVIEW PLAN l
"An Acceptable AFWS Should Have an Unreliability^ in the Range of 10-4 to 10-5 per Demand Based on an Analysis Using Methods and e
Data Presented in NUREG-0611 and NUREG-0634.
l Compensating Factors such as Other Methods of Accomplishing the Safety Functions of the AFNS or Other Reliable Methods for Cooling the Reactor Core During Abnormal Conditions may be Considered to Justify a Larger Unavailability of the AFWS. '
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DECAY HEAT REMOVAL SYSTEMS ADDRESSED IN ANO-2 E0Ps o
Main Feedwater Pumps
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o Feed & Bleed Cooling ECCS Vent Line E-Full Decay Heat Removal Capability
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1981 1985 EFW TRAIN PERFORMANCE
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Pl. ANT TRIP REDUCTION PROGRAM L
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PLANT TRIP REDUCTION PROGRAM
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Why Have Such a Program?
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ANO-2 TRIP REDUCTION EFFORTS o
NUMARC Followup on all Automatic Scrams Identification of Root Causes Action Plan to Correct Discrepancies E
Goals
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3 or less Auto Trips while Synch 5 or less Auto Trips while Critical E
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Software' Modifications and l
Associated Technical Specification g
Change (A;;,:iting !!RC-ApprGval) Nk ^!]~a1Naiss-t
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Procedure Revisions to Preclude
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Operation with High CPC Penalty i
Factors (2R5/1986) i I
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t ANO-2 TRIP REDUCTION EFFORTS (Continued) o CEDM Technician Training (Complete)
Improved Test Procedures (Complete) r
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E Automatic Control Timing Modules to E
Monitor and Adjust Timing and Voltage o
SG Level Control g
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E low Range FW Flow Indication 1
Provided in Control Room (Comlete) f Plant Specific Simulator for i
Training and Familiarity with Low Power Control (4th Quarter 1986 -
Onsite.
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PROGRAMS TO IMPROVE MAINTENANCE AND HUMAN PERFORMANCE Work Control Center / Maintenance o
Management Computer System i
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Preventative & Predictive Maintenance Improvement Project 0
Technical Manual Review G Update Project l
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Procedure Writer 's Guide G Nriter/
Reviewer Training Program 0
Drawing Updates / Plant Labeling Program a
Training Programs g
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20% of Operator, Technician Time INPO Accreditation Plant Specific Simulators l
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CONCLUDING REMARKS E
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CONCLUSIONS a
o High Guality System a
o System Meets or Exceeds all Applicable Regulations E
o SER Concludes. Compliance With II.E.i.i G l
II.E. i.2 & GL 8i-14 0
0 Meets Reliability Guidance in Standard Review Plan 0
Loss of MFW Challange Rate is low o
Current Plans / Schedules are Concentrated on g
Primary System and Trip Reduction
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DEC 161985 MEETING
SUMMARY
DISTRIBUTION i
DocketNo(s): 50-368 7 NRC PDR.
Local PDR PBD-7 Reading JPartlow 4
GWKnighton i
BGrimes ACRS(10)
EJordan Attorney, OELD GWKnighton i
Project Manager RLee i
NRC PARTICIPANTS R. Lee A. Thadani
- 0. Parr L. Rubenstein G. Edison J. Hermiel J. Raval A. El-Bassioni W. Regan G. Vissing J. Stolz J. Glynn.
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.bec: Applicant & Service List
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believed to have this. The staff indicated that it would be difficult to show a high reliability with a two-train system. The staff will continue to draft the.CRGR package for CRGR. consideration.
If approved, a Generic Letter will be issued.
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Robert S. Lee, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Enclosures:
As stated cc: See next page
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