ML19224C376
| ML19224C376 | |
| 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 | |
| FOIA-79-98 NUDOCS 7907020243 | |
| Download: ML19224C376 (5) | |
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Meetin Summary f W N.
north An j V C DR Mr. Michael W. Maupin Local PCR Hunton.and Wil1iams Post Office Box 153S CRBI Reading NRR Reading Richmond, Virginia 23213 Swem Library V. Stello College of William and Mary D. Eisenhut Williamsburg, Virginia 22185 f,'o r
s Donald J. Burke p
A. Schwencer U. j. Nuclear Regulacry Commission D. Ziemann Region II P. Check Office or, Inspection and Enforcement G. Lainas 101 Marietta Street, Suite 3100
- 0. Davis Atlanta, Georgia 30303
- 3. Grimes T. Ippolito R. Reid V. Hoonan G. Knighton D. Brinkman Project Manager (M. Grotenhuis/E. Reeves)
CELD O!3E (3)
C. Parrish MRS (16)
' AC Participants J. Suchanan TERA Licensee Short Service List A. Thadani M. - lor Ro '-
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A. Dromerick 269 14; 7907020M3 gijm A A) n-M
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UNITED STATES w -
NUC1. EAR REGULATORY CCMMissiCN
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WASHINGTON, D. C. 20555
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May 9, 1979
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Cocket No. 50-338 LICENSEE:
Virginia Electric Pcwer Company (VEPCO)
FACILITY: North Anna Pcwer Station, Unit No.1
SUBJECT:
SUFFARY'0F MEETING HELD ON MAY 8,1979 TO DISCUSS THE AUXILIARY FE2DWATER SYSTEMS At:0 RELATED 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 repo rt.
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 2.
This was followed by a review with the licensee of the information written as a result of the morning session. All questions in both enclosures were answered.
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Marshall Grotenhuis, Project Manager Operating Reactors Branch #1 Division of Operating Reactors Enclosures :
As Stated cc: w/ enclosures See attached list 2b) f,j['
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ar; of its on-going review of the Three Mile island L' nit 2 accident,
' ~ 2 s taff fir.ds that it naeds additional informaticn regarcing the auxiliary faed..ater systems ( AFWS). This information as outlined beicw, is recaired to evaluate AFWS reliability for Combustien Engineering (CE) and Westinghcuse (W) d2 signed pressuriced water reactors.
The recuested information is in addition to that requested in the IE Sulletins, 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 (Ecth Electric and Steam)
'a'ater Supplies for AFWS (primary and backup)
Current operating procedures and test and maintenance requirements including:
All LCO's for AFHS, main FW system and related support systems.
Listing of cperator actions (local and/or ccntrol rccm) and timing require-mants for such actions.
precedures for reinitiating main feedwater ficw.
As Built P& ids with symbol keys including condensate and steam side Ledgible Equipment layouts drawings including:
Isemetrics, if available Identification of inhibits preventing accessibility to AFWS components and related electrical equipment F.elevant control systems description including:
- Schematic cr logic ccntrol diagrams Listing of actuation signais/ logic and control
- MSIS logic fcr isolating AFWS, if installed electric power dependences
.Ali " readouts" available in control room for AFWS cperation AC L SC pcuer One line diagrams (normal and emergency power supplies)
- Divisional designation e.g., Train A, Train B, requirements on all AFWS ccmponents and support systems List of normal valve states and loss-of-actuation pcwer failure pcsition Operating Experience, including
- !! umber of main feedwater interruptions per year experienced to date for each unit
!: umber of dem:nds on AFWS per year to date (test and actual) for each unit
- Su=ary of AFWS malfunctions, problems, failures Fr:vice Available reliability analyses 5: aim 'laneratcr dry-cut timas (assumir.g icts of all fc26 tater ficw, with ICC';
Mitiai ;c..2r, with F.22: tor trip, no line breaks)
- 2. ::1 casign bases including:
- :5.:-ic and anvircreer.tal qualificacicn
- 12 and Qualicy, QA z
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7::..:e ;-itt n respenses to the felic.ii.g set cf T.estiens t.s E/E/79 Cascribe bac!:u; systems available (to auxiliary feedaater) for providing feet. ater to steam ganerators.
Discuss acticns and time required to make these systems available. Are procedures available?
If so, provide.
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Frevide the following procedur4,r less of offsite power less of feedwater LOCA (small and l'
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Steam Line 2 Frovide follcwing information for PORV's:
Number capacity setpoints (open and close) canufacturer and model indications of position record of periods isolated (isolatien valve shut) challenges during life of plant (from plant records) including performance of valve, cause of challenge.
experience of two-phase or subccoled discharge of PCRVs and safety valves with description of valve performance Provide indications of PCRV isolation valve in the centrol recm.
Previde the folicwing information on ECCS:
initiation setpoints system description pump performance characteristics (head curves)
Frevide reactor protecticn system trip setpoints.
Provide information on charging pumps, hcw they reiate to ECCS including:
number ficw vs. pressure pcwer sources and backup water scurces seismic cualification List all challenges (and cause) to ECCS as indicated on plant records.
List and discuss all instances during which your plant has undergene natural circulation.
Cescribe all autcmatic and manual features which can top ine reacter s
ccolant pumps.
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ENCLOSURE 3 ATTENDEES Name Reo resentino M. Grotenhuis DOR, ORB #1 David W. Speidell Jr.
VEPC0 - Licensing John Mosticone VEPC0 - North 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 DSS, PSB M. Cunningham
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