ML19263E696
| ML19263E696 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/16/1979 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906250056 | |
| Download: ML19263E696 (4) | |
Text
[pnnuo, v
o, UNITED STATES
! h c,c j
NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D. C. 20555
- /
May 16, 1979 Docket Nos. 50-266 and 50-301 LICENSEE: Northern States Power Company (NSP)
FACILITY:
Prairie I: land Nuclear Generating Plant, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 12, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEM AND RELATED AREA On May 12,1979 representatives of NSP and the Regulatory Staff met to discuss the Auxiliary Feedwater System (AFS) and related areas. The purpose of the meeting was to assemble information for an NRC report.
The areas discussed are listed in attachments 1 and 2.
The attendees are.isted in attachment 3.
The meeting began at 8:00 am with a discussion of the material listed in attachment 1.
The information in attachment 2 has been submitted by telecopy on May 11, 1979 and was supplemented on May 12, 1979.
The meeting was closed after the licensee reviewed the draft material written as a result of the discussion. All questions in the attachments were answered.
{.
Mgudd<
~INA~.
Marshall Grotenhuis, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Attachments:
As Stated cc: w/ attachments See next page 2218 153 7906250D86 jo
ATTACHMENT 1 6 o /' "
As part of its on-going review of the Three Mile Island Unit 2 accident, the staff finds that it needs additioral information regarding the auxiliary feedwater systems (AFWS).
This information as outlined below, is required to evaluate AFWS 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 May 12, 1979.
Written system description (as built) including:
List of Suoport Systems for Auxiliary Feed System Operation (Both Electric and Steam)
Water Supplies for AFWS (primary and backup)
Current operating procedures and test and maintenance requirements including:
All LC0's for AFWS, main FW system and related support systems.
Listing of operator actions (local and/or control room) and timing require-ments for such actions.
Procedures for reinitiating main feedwater f!aw.
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 electr' cal 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 power 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 feedwater flow, with 100%
initial power, with Reactor trip, no line breaks)
System design bases including:
Seismic and environmental qualification Code and Quality, QA 2218 154
ATTACHMENT 2 i o/ l.' 979 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 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 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 as indicated on plant records.
List and discuss all instances during which your plant has undergone natural circulation.
Describe all automatic and manual features which can top the reactor s
coolant pumps.
2218 155
ATTACHMENT 3 LIST OF ATTENDEES M. Grotenhuis, Nuclear Regulatory Comission A. Bennet, Nuclear Regulatory Comission M. Cunningham, Nuclear Regulatory Commission J. Gonyeau, Northern States Power Company A. Smith, Northern States Power Company 2218 156
h.
Meeting Summary for May 16,1979 Northern States Power Company Docket Files Gerald Charnoff, Esquire NRC POR Local POR Shaw, Pittman, Potts and Troworidge 1800 N Street, N.W.
ORB 1 Reading NRR Reading Washington, D. C.
20036 H. Denton E. Case Sandra S. Gardecring Executive Director V. Stello O. Eisenhut Minnesota Pollution Control Agency 7935 W. County Road 32 B. Grimes R. Vollmer Roseville, Minnesota 55113 A. Schwencer The Environmental Conservation Library D. Ziemann P. Check Minneapolis Public Library 300 Nicollet Mall G. Lainas Minneapolis, Minnesota 55401
- 0. Davis B. Grimes T. Ippolito Mr. F. P. Tierney, Plant Manager R. Reid Prairie Island Nuclear Generating Plant V. Noonan Northern States Power Company Route 2 G. Knighton Welch, Minnesota 55089 G. Brinkman Project Manager Joc1yn F. Olson, Esquire OELO OI&E (3)
Special Assistant Attorney General C. Parrish Minnesota Pollution Control Agency 1935 W. County Road 32 ACRS (16)
Roseville, Minnesota 55113 NRC Participants Buchanan Robert L. Nybo, Jr., Chairman