ML19270H321
| ML19270H321 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/18/1979 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906260193 | |
| Download: ML19270H321 (5) | |
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UNITED STATES 4) 7 f.,
NUCLEAR REGULATORY COMMISSION 4
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WASHINGTON. D. C. 20555 May 18, 1979 Docket No. 50-344 LICENSEE: Portland General Electric Company FACILITY: Trojan Nuclear Plant
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 12, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEM AT TROJAN NUCLEAR PLANT On May 12, 1979, the NRC staff met with representatives of Portland General Electric Company for a detailed discussion of the auxiliary feedwater system at Trojan Nuclear Plant. Attendees are listed in attachment (1).
The meeting was a part of a larger scope task to consider what, if any, changes are required for non-B&W plants in light of the Three Mile Island Unit 2 experience. The material discussed is listed in attachment (2).
The information gathered at this meeting will be included in a NRC staff report to the Comission.
It will include information generic ?.o W plants and specific information on Trojan. The report will include any recommended changes the staff believes are needed and present conclusions as to whether or not continued operation is justified (all CE and W plants).
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stL4 Charles Trammell Operating Reactors Branch #1 Division of Operating Reactors Attachments:
As stated cc: See next page 2318 206 0 6 2 6 0M3
Meeting Summary for Trojan Nuclear Plant May ~8, 1979 Docket Files NRC PDR Mr. H. H. Phillips Local PDR Portland General Electric Company ORB 1 Reading I
121 S.W. Salmon Street 4
NRR Reading Portland, Oregon 97204 H. Denton E. Case Warren Hastings, Esquire i
V. Stello Counsel for Portland General D. Eisenhut Electric Company 121 S.W. Salmon Street B. Grimes R. Vollmer Portland, Oregon 97204 l
A. Schwencer i
Mr. J. L. Frewing, Manager D. Ziemann Generation Licensing and Analysis P. Check G. Lainas Portland General Electric Company D. Davis 121 S.W. Salmon Street B. Grimes Portland, Oregon 97204 T. Ippolito R. Reid Columbia County Courthouse V. Noonan Law Library, Circuit Court Room G. Knighton St. Helens, Oregon 97501 D. Brinkman Project Manager Director, Oregon Department of Energy OELD Labor and Industries Building, Room 111 OI&E (3)
' Salem, Oregon 97310 C. Parrish ACRS (16)
Richard M. Sandvik, Esquire NRC Participants Counsel for Oregon Energy Facility 4_3uchanan Siting Counsel and Oregon Department FIERA) of Energy L71 ensee 500 Pacific Building Short Service List 520 S.W. Yamhill A. Thadani Portlaiid, Oregon 97204 P. Mathews R. Ross Michael Malmrose U. S. Nuclear Regulatory Commission Trojan Nuclear Plant P. O. Box 0 Rainier, Oregon 97048 2318 207
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LIST OF ATTENDEES PORTLAND GENERAL ELECTRIC COMPANY MEETING May 12, 1979 PGE NRC H. Schmidt W. LeFave G. Zimmerman C. Trammell R. Barkhurst S. Asselin (Sandia)
S. Hoag J. Hickman (Sandia) 2318 208 e..-
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~!; part of its en-going review of the Three Mile Island U.it 2 accif:-t, the staff finds thi.t it needs additional information regarding the nxiliary feedwater systems (A 1lS).
This information as outlined balow, is rc;uired to evaluate AFWS rc ! ability for Combustion Engineering (CE) and ' es-inghouse (W:
designed pressurize:d water reactors.
The requested information is in addition to that requested in the IE Bulletins, and should be brought to the maeting scheduled with the staff on May 8 thru May 12, 1979.
Written system description (as built) including:
l List of Support Systems for Auxiliary Feed System Operation (Both Electric j
and Steam)
Water Supplies for AFWS (primary and backup)
Current operating procedures and test and maintenance requirements including:
All LCO's for AFWS, main FW system and related support systems.
Listing of operator actions (local and/or control rocm) and timing require-ments for such actions.
Procedures for reinitiating main feedwater flow.
e 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 A WS 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 All " readouts" available in control room for AFWS operation 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 Operating 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
- Summary of AFWS malfunctions, problems, failures Provide Available reliability analyses Steam Generator dry-out times (assuming loss of all feed < cater flew, with 100%
initial pcwer, with Reactor trip, no line breaks)
System design bases including:
- Seismic and environmental qualification 2318 209 Code and Quality, QA h
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U: Vide s.rF.E resp r.ses to the folicwinc st: Of cuss'tTc?.TV.E;-
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j Describe backup systems available (to auxiliary fe:d.:ater) for ;reviding i
feedwater to steam generators.
Discuss actions and time re;uirec to make these systems available. Are procedures available?
If so, pr: vide.
Provide the fo11cwing procedures:
loss of offsite pcwer loss of feedwater LOCA (small and large)
Steam Line Break Provide following information for PORV's:
l Number i
capacit setpoints (open and close) manufacturer and model l
~ i fndications of position record of periods isolated (isolation valve shut) challenges during life of. plant (from plant records) including performance of valve, cause of challenge.
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.
Provide the following information on ECCS:
initiation setpoints system description pump perfomance characteristics (head curves)
Provide reactor protection system trip setpoints.
Provide infomation on charging pumps, how they rel. ate to ECCS including:
number flow vs. pressure power sources and backup water ~ sources seismic qualification List all challenges (and cause) to ECCS as indicated on plant records.
List 'nd discuss all instances during which your plant has undergone natura a
circulation.
Describe all automatic and manual features which canstop the reactor coolant pumps.
2318 210
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