ML19263E815
| ML19263E815 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/09/1979 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906250317 | |
| Download: ML19263E815 (4) | |
Text
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, pin ntcr4S UNITED STATES g'
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NUCLEAR REGULATORY COMMisslON g, (f, (y -j WASHINGTON, O. C. 20555
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May 9,1979
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Docket No. 50-338 LICENSEE:
Virginia Electric Power Company (VEPCO)
FACILITY:
North Anna Power Station, Unit No.1 SC JECT:
SUMMARY
OF MEETING HELD ON MAY 8,1979 TO DISCUSS THE AUXILIARY FEEDWATER LYSTEMS AND PELATED AREAS On May 8,1979 representatives of VEPC0 met with the Regulatory Staff to discuss the auxiliary feedwater system and related station areas.
The purpose of the meeting was to assemble information for an NRC report. The areas discussed are listed in enclosures 1 and 2.
The attendees are listed in enclosure 3.
The meeting began at 8:00 am with the discussion of the material listed in enclosure 1.
The meeting was reconvened after lunch to discuss the material in enclosure 7..
This was followed by a review with the licensee of the information written as a result of the morning session. fil questions in both enclosures were answered.
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hy /lu*(' kLe lL~ :-
Marshall Grotenhuis, Project Manager Operating Reactors Branch #1 Division of Operating Reactors
Enclosures:
As Stated cc: w/ enclosures See attached list 22kk 79062505/7'.
Meeting Summary for North Anna Docket Files NRC PCR Mr. Michael W. Maupin Hunton and Williams Local POR Post Office Box 1535 ORBI Reading NRR Reading Richmond, Virginia 23213 Swem Library V. Stello College of William and Mary D. Eisenhut Willitmsburg, Virginia 23185 ho Donald J. Burke 7
A. Schwencer U. S. Nuclear Regulatory Commission D. Ziemann Region II P. Check Office of Inspection and Enforcement G. Lainas 101 Marietta Street, Suita 3100 D. Davis Atlanta, Georgia 30303 B. Grimes T. Ippolito R. Reid V. Noonan G. Knighton D. Brinkman Project Manager (M. Grotenhuis/E. Reeves) 0 ELD OISE (3)
C. Parrish i
ACRS (16)
NRC Participants J. Suchanan
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ee Short Service List A. Thadani M Taylor D. Ross
- 0. Parr A. Dromerick 2214 012
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P[0R ORilN.Al
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As part cf its on-going review of the Three Mile Island Unit 2 accident, "N2 staff fir.ds that it needs additional information regarding the auxiliary faci-ater systems (AFWS). This information as outlined below, is recuired to evaluate AFWS reliability for Combustion Engineering (CE) and Westinghouse (W) dasigned pressurized water reactors.
Tne 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 AFWS, main FW system and related support systems.
Listing of operator actions (local and/or control rcom) and timing require-ments for such actions.
Procedures for reinitiating main feedwater flow.
As Built P& ids with symbol keys including co.tdensate and steam side Ledgible Equipment layouts drawings including:
Isemetrics, if available Identification of inhibits preventing accessibility to AFWS components and related electrical equipment P,elevant 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 AFW5 operation AC & DC Fower One line diagrams (normal and emergency power supplies)
- Divisfonal designation e.a., 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
- llu-ber of main feedwater interruptions per year experienced to date for each unit
- ?! caber of dem:nds on AFWS per year to date (test and actual) for each unit
- Sumary of AFWS malfunctions, problems, failures Pr:vice Available reliability analyses Steam Generator dry-cut times (assuming loss of all fcediater ficw, with 100%
initial power, with F.aattor trip, no line breaks)
S Iter design bases including:
_eismic and anvirccmental qualificaticn
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2de tnd Quality, QA 2214 013
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~ f re.::e.;ritten responses to the folic..-f r.g set cf questicr.s by E/E/79 C2 scribe bacl:up systems available (to auxiliary feedwater) for providing feedwater to steam generators.
Discu s actier.s and time reau f red to r..ake
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these systems available.
Are procedt es 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 p0RV's:
Number capacity setpoints (open and close) manufacturer and model indications of position record of periods isolated (isol= tion 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 p0RVs and safety valves with description of valve performance Provide indications of PORV isolation valve in the control room.
Provide the following information en ECCS:
initiation setpoints system description pump performance characteristics (head curves)
Frovide reactor protection system trip setpoints.
Frovide information on charging pumps, how they reTate to ECCS including:
number ficw 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 undergant natural circulation.
Describe all automatic and manual features which can top the reactor s
coolant cumps.
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ENCLOSURE 3 ATTENDEES Name Representing M. Grotenhuis D0R, ORB #1 David W. Speidell Jr.
VEPC0 - Licensing John Mosticone VEPCO - Nortt Anna W. R. Cartwright VEPC0 - North Anna Sta Manager Eugene S. Grecheck VEPC0 - Licensing David L. Benson VEPC0 - Nuclear Operations P. R. Matthews DSS, ASB A. Bennett OSS, PSB M. Cunningham
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