ML19269E432
| ML19269E432 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/21/1979 |
| From: | Conner E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906290033 | |
| Download: ML19269E432 (4) | |
Text
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UNITED STATES y
g NUCLEAR REGULATORY COMMISSION p
WASHINGTON, D. C. 20555 g-f May 21,1979 Docxet No. 50-336 LICENSEE:
NORTHEAST NUCLEAR ENERGY COMPANY (NNECO)
FACILITY: MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 11, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEMS AND RELATED AREAS On May 11, 1979 representatives of NNECO met with the Regulatory Staff to discuss the auxiliary feedwater system and related station areas.
The purpose of the meeting was to assemble infomation for an NRC report.
The areas discussed are listed in Enclosure 1.
The attendees are listed in.
The meeting began at 8:00 a.m. with the discussion of the material listed in Enclosure 1.
A review with the licensee of the information written as a result of the moring session was completed.
All questions in Enclosure 1 were answered.
& y 'A E. L. Conner, Jr., Project Manager Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
Areas Ofscussed 2.
List of Attendees cc w/ enclosures:
See attached list 2265 294
e
..A As part of its on-going review of the Three Mile Island Unit 2 ac:ident, the staff finds that it needs additional information regarding the auxiliary feedwater systems (AFWS). This information as outlined below, is required to "v>1uate AFWS reliability for Combustion Engineering (CE) and Westinghouse (W) de' '..r ed pressurized water reactors. The requested information is in addition to t'.t requested in the IE Bulletins, and should be brought to the meeting scheduled with the staff on May 8 thru May 12, 1979.
Written system description (as built) including:
List of Support Systems for Auxiliary Feed System Operation (Soth Electric and Steam)
Water Supplies for AFWS (primary and backup)
Current operating procedures and test and maintenance recuirenents including:
All LCO's for AFWS, main FW system and related support systems.
Listing of operator actions (local and/or control rocc) and timing require-ments for such actions.
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 All " readouts" available in control room for AFKS operation AC & DC Power One 1tne 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 Nunber of demands on AFWS per year to date (test and actual) for each unit Sumary of AFWS malfunctions, problems, failures Provide Available reliability analyses Steam Generator dry-out times (assuming loss of all feedwater ficw, with 100%
initial power, with Reactor trip, no line breaks)
System design bases including:
Seismic and environmental qualification Code and Quality, QA 2265 295
Pace 2 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 PORV's:
Number capacity setpoints (open and close) manufacturer and model indications 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 witn description of valve performance Provide indications of PORY isolation valve in the control room.
Provide the following infonnation on ECCS:
initiation setpoints system description pump performance characteristics (head curves)
Provide reactor protection system trip setpoints.
Provide infonnation on charging pumps, how they relate to ECCS including:
number flow vs. pressure power sources and backup water sources seismic qualification List all challenges (and cause) to ECCS r_
..dicated on plant records.
List and discuss all instances during which your plant has undergone natural circulation.
Cescribe all automatic and manual features which canstop tne reactor coolant pumps.
2265 29~6
5 LIST OF ATTENDEES NUSCO NRC David B. Vail A. B. Bennett Rik Wells Mark Cunningham Monte Conner Richard D. Hart Richard Kacich Paul M. Blanch BECHTEL POWER CORP.
NNCCO Harry S. Xassiec, Jr.
Jim Kelley 2265 297
4 MEETING
SUMMARY
DISTRIBUTION ORB #4 Mr. W. G. Counsil, V'ce President Nuclear Engineering & Operations Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Dock ile R. Reid PD V. Noonan L PDR P. Check ORB #4 Rdg G. Lainas NRR Rdg G. Knighton H. Denton Project Manager E. G. Case OELD V. Stello OI&E(3)
D. Eisenhut R. Ingram R. Vollmer R. Fraley, ACRS (16)
W. Russell Program Support Branch B. Grimes TERA T. J. Carter J. R. Buchanan A. Schwencer Meeting Summary File D. Ziemann NRC Participants T. Ippolito Mark Cunningham A. B. Bennett 2265 298