ML14190A313
| ML14190A313 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/18/1979 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906260190 | |
| Download: ML14190A313 (6) | |
Text
Docket No.
50-261 LICENSEE: CAROLINA POWER AND LIGHTCOMPANY
'FACIL ITY:
H. B. ROBINSON UNIT NO. 2
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 10, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEM AT H. B. ROBINSON UNIT NO. 2 On May 10, 1979, the:NRC staff met with 'representatives of Carolina Power and Light Co. and Westinghouse Electric Corporation (W) for a detailed discussion of the auxiliary feedwater system atH. -B.
Robinson. Unit No. 2. 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. Jllants 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 an.NRC staff report to the Commission. It will include information generic to W plants and specific information on H. B.. Robinson Unit No. 2. 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).
Aththe conclusion of the meeting, thd information w'ten by the staff with respect to this system was reviewed with bhe licensee.
C. M. Trammell 7 9 0 6 2 6 0(7 SURNAME*
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Meeting Summary for H. B. Robinson
- 2 Docket Files G. F. Trowbridge, Esquire NRC POR Shaw, Pittman, Potts and Trowbridge Local PDR 1800 M Street, N.W.
ORBI Reading Washington, D. C. 20036 NRR Reading H. Denton Hartsville Memorial Library E. Case Home and Fifth Avenues V. Stello Hartsville, South Carolina 29550 D. Eisenhut B. Grimes John F. Wolf, Esquire, Chairman R. Vollmer 3409 Shepherd Street A. Schwencer Chevy Chase, Maryland 20015
- 0. Ziemann P. Check Dr. A. Dixon Callihan G. Lainas Union Carbide Corporation
- 0. Davis P. 0. Box Y B. Grimes Oak Ridge, Tennessee 37830 T. Ippolito R. Reid Dr. Richard F. Cole V. Noonan Atomic Safety and Licensing Board G. Knighton U. S. Nuclear Regulatory Commission D. Brinkman Washington, D. C. 20555 Project Manager OELD OI&E (3)
C. Parrish ACRS (16)
NRC Participants J. Buchanan TERA Licensee Short Service List
PA REG&j.
-t oUNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 May 18, 1979 Docket No. 50-261 LICENSEE:
CAROLINA POWER AND LIGHT COMPANY FACILITY: H. B. ROBINSON UNIT NO. 2
SUBJECT:
SUMMARY
OF MEETING HELD ON MAY 10, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEM AT H. B. ROBINSON UNIT NO. 2 On May 10, 1979, the NRC staff met with representatives of Carolina Power and Light Co. and Westinghouse Electric Corporation (W) for a detailed discussion of the auxiliary feedwater system at H. B.
Robinson Unit No. 2. 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 ihformation gathered at this meeting will be included in an NRC staff report to the Commission. It will include information generic to W plants and specific information on H. B. Robinson Unit No. 2. 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).
At the conclusion of the meeting, the information written by the staff with respect to this system was reviewed with the licensee.
. M. Trammell, Project Manager Operating Reactors Branch #1 Division of Operating Reactors cc: See next page
ATTACHMENT 1 LIST OF ATTENDEES CP&L MEETING MAY 10, 1979 CP&L NRC D. Waters R. Giardina M. Page C. Trammell
- 0. Bensinger E. Peterson (BNL)
H. Smith D. Carlson (Sandia)
W L. Kincaid
As part of its on-going review of the Three Mile Island Unit 2 accidant, the staff finds that it needs additional information regarding the auxiliary feedwater systems (AFWS).
This information as outlined below, is rcuired 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 Support 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 LCO's for AF14S, 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 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 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
Provide written res onses 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 information 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 canstop the reactor coolant pumps.