ML19270H314
| ML19270H314 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/15/1979 |
| From: | Reeves E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-12391, TAC-12963, NUDOCS 7906260179 | |
| Download: ML19270H314 (4) | |
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UNITED STATES 33 i%
NUCLEAR REGULATORY COMMISSION j,{
j WASHINGTON, D. C. 20555 e
1 5 1979 gy Docket No. 50-348 LICENSEE: Alabama Power Company (APCO)
FACILITY: Farley Nuclear Plant, Unit No.1
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 8, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEMS AND RELATED AREAS On May 8,1979 representatives of APC0 met with the Regulatory Staff in Bethesda, Maryland to discuss the auxiliary feedwater system and related station information. The purpose of the meeting was to assemble infor-mation for an NRC staff meeting report. The areas discussed are listed in enclosures 1 and 2.
Meeting attendees are listed in enclosure 3.
APC0 personnel presented information to the NRC staff for discussion.
Certain plant drawings and existing Final Safety Analysis Report sections were reviewed. Operating experience and the most current operational, test and maintenance procedures were presented and discussed. APC0 noted that Farley Unit No. I was shutdown on March 8,1979 for start of Cycle 2 fueling. Scheduled startup is late May or early June,1979.
APC0 (Epps) noted that their company policy was to maintain all current '
operational procedures at the plant site. However, APC0 provided copies of the latest versions (some still under review by APC0 staff) of proce-dures identified in enclosure 1 for review during the meeting. Other material presented to the NRC staff by APC0 will be held by the NRC Project Manager pending completion of the NRC staff report.
By enclosure 2 we requested APC0 to provide written responses at the meetings.
Due to the short notice prior to the meeting, APC0 presented the information in preliminary form for informaticn only. We accepted the data presented for use as background information and agreed to contact APC0 (T. N. Epps) if further data was needed.
4 Edward A. Reeves, Project Manager Operating Reactors Branch #1 Division of Operating Reactors
Enclosures:
As stated 2318 138 cc: w/enclosuressee attached list 790626009
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Meeting Summary for Farley Nuclear Plant, Unit No.1 ggy 1 3 7979
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Docket Files NRC PDR Ruble A. Thomas, Vice President Local PDR.
i i Southern Services, Inc.
ORBI Reading i Post Office Box 2625 NRR Reading.
Birmingham, Alabama 35202 H. Denton E. Case George F. Trowbridge, Esquire V. Stello Shaw, Pittman, Potts and Trowbridge D. Eisenhut 1800 M Street, N.W.
B. Grimes Washington, D. C.
20036 R. Vollmer A. Schwencer
. John Bingham, Esquire D. Ziemann I Balch, Bingham, Baker, Hawthorne, P. Check Williams and Ward G. Lainas 600 North 18th Street D. Davis Birmingham, Alabama 35202
- 8. Grimes T. Ippolito Edward H. Keiler, Esquire R. Reid Keiler and Buckley V. Noonan 9047 Jefferson Highway G. Knighton River Ridge, Louisiana 70123
- 0. Brinkman Project Manager George S. Houston Memorial Library GELD
'212 W. Berdeshaw Street OI&E (3)
Dothan, Alabama 36303 C. Parrish NRC Participants J. Buchanan (TEF)
LTcensee Short Service List P. Mathews L. Kintner T. N. Epps, APCjg }}g .-w-t--- w..w+ '*h.**=c e w es*
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l .[ 1- - Enclosure'1 ..As part nf its on-going review of the Three Mile Island Unit 2 accident, the staff finds that it needs additional information regarding the auxiliary ~~. feedwater systt,. (AFWS). This information as outlined below, is required to evaluate AFE reliability for Combustion Engineering (CE) and Westinghouse (W) designed pressurized water reactors. The requested information is in addition to that requested in the IE Bulletins, and should be brought to the meeting scheduled with the staff on May 8 thru Hay 12, 1979. Written system description (as built) including: u_ List of Support Systeas for Auxiliary Feed System Operation (Both Electric ,) ,b i": and Steam) Water Supplies for AFWS (primary and backup) Current operating procedures and test and maintenance requirements including: All LCO's for AnlS, main FW system and related support systems. Listing of operator actions (local and/or control room) and timing require-ments for such actions. I Procedures for reinitiating main feedwater flow. As Built P& ids with symbol keys including condensate and steam side Ledgible Equipment layouts drawings including: Isometrics, if available Identification of inhibits preventing accessibility to AFWS components and related electrical equipment Relevant control systems description including: Schematic or logic control diagrams Listing of actuation signals / logic and control MSIS logic for isolating AFWS, if installed electric power dependences 1 All " readouts" available in control room for AFWS operatica AC & DC Power One line diagrams (normal and emergency power supplies) . Divisional designation e.g., Train A, Train B, requirements on all AFWS components and support systems List of normal valve states and loss-of-actuation pcwer failure position .C Oparating Experience, including Number of main feedwater interruptions per year experienced to date for each unit Number of demands on AFWS per year to date (test and actual) for each unit Sumary of AFWS malfunctions, problems, failures u Provide Available reliability analyses Steam Generator dry-out times (assuming loss of all feedwater flow, with 100% initial power, with Reactor trip, no line breaks) System design bases including: Seismic and environmental qualification Code and Quality, QA M18 140 emes se -e mmem e. wen.- m-_ ww+, +gw-m-ee-we-- eem
~ Wh 6 h hemp 6me Enciesdre 2 May 4, 1979 Provide written responses to the following set of questions by 5/8/79 Describe backup systems available (to auxiliary feedwater) for providing feedwater to steam generators. Discuss actions and time required to make these systems available. Are procedures available? If so, provide. Provide the following procedures: loss of offsite power loss of feedwater . LOCA (small and large) Steam Line Break Provide following information for PORY's: Number-capacity setpoints (open and close) manufacturer and model indications of position i record of periods isolated (isolation valve shut) challenges during life of plant (from plant records) including perfomance of valve, cause of challenge. s experience of two-phase or subcooled discharge of PORVs and safety valves with description of valve performance Provide indications of PORV isolation valve in the control room. i 4 Provide the following infomation on ECCS: initiation setpoints system description pump perfomance characteristics (head curves) ] Provide reactor protection system trip setpoints. I Provide infomation on charging pumps, how they relate to ECCS including: l number j flow vs. pressure I power sources and backup water sources seismic qualification i List all challenges (and cause) to ECCS as indicated on plant records. List and discuss all instances during which your plant has undergone natur circulation. Describe all automatic and manual features which canstop the reactor coolant pumps. 2318 141 'W***' G W eime'
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~ ALABAMA POWER COMPANY MEETING ON 5/8/79 LIST OF ATTENDEES Ed Reeves NRC/ DOR Bill LeFave NRC/ASB i Stu Asselin Sandia Labs (For NRC/ PAS) Gordon Edison NRC/ PAS S. H. Hanauer
- NRC/ DSS P. D. O'Reilly NRC/DPM T. N. Epps Alabama Power Co.
Dan Poole Alabama Power Co. J. N. Alvarez Bechtel Corp. H. G. Huff Bechtel Corp. Richard Gallaghe-Bechtel Corp.
- Part Time 23}8 l4}
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