ML19270H313
| ML19270H313 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/15/1979 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906260176 | |
| Download: ML19270H313 (5) | |
Text
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Mr. C. N. Dunn Duquesne Light Company cc: Gerald Cnarnoff, Esquire Mr. James A. Werling Jay E. Silberg, Esquire Plant Superintancent Shaw, ?i ttman, Potts ana Troworidge 3eaver Valley Dower Station 1800 M Street, N.W.
P. O. Box 4 Washington, D. C.
20036 Shippingport, Dennsylvania 15077 Karin Carter, Esquire Soecial Assistant Attorney General Bureau of acministrative Enforcement 5th Floor, Executive Mcuse Harrisourg, Pennsylvania 17120 Mr. J. M. Cumi skey Stone and Weoster Engineering Corporation
?. O. 3cx 2325 Boston, ' Massachusetts 02107 Mr. J. D. Woodward R & O Center Westinghouse Electric Corporation Builcing 7-303 Pittsourgh, Pennsylvania 15230
- 3. F. Jones Memorial Library 663 Franklin Avenue Aliquippa, Pennsylvania 15C01 Mr. Jack Carey Tecnnical Assistant Duquesne Lignt Ccepany P. O. Box 4 Shippingport, Pennsylvania 15077 Mr. R. E. Martin Ducuesne Lignt Ccmoany 2318 132 435 Sixtn Avenue Pi ttsourgn, Pennsylvania 15219 Marvin r in e
Utili ty Counsel Ci ty of Pi ttsourgn 313 Ci ty-County 3uil ding Pi ttsburgn, Pennsylvania 15219 79062601%
r Meeting Summary for Duquesne Light Ccepany Docket Files NRC PDR Local POR CRBI Reading NRR Reading H. Denton E. Case V. Stello D. Eisenhut
- 3. Grimes R. Yollmer A. Schwencer D. Ziemann P. Check G. Lainas D. Davis
- 3. Grimes T. Ipcoli to R. Reid V. Noonan G. <nignton D. Brinkman Project Manager CELD 0:3E (3) 2318 133 C. Parrish ACRS (16 )
NRC Participants J. Suchanan ee Short Service List
'o, UNITED STATES
[}3r,, 'i NUCLEAR REGULATORY COMMISSION
- Jy
. C WASHINGTON, D. C. 20555 o a May 15,1979 Docket No.
50-334 LICENSEE:
Duquesne Light Company FACILITY:
Beaver Valley, Unit No. 1
SUBJECT:
SUMMARY
OF MEETING ON MAY 12, 1979 TO DISCUSS THE AUXILIARY FEEDWATER SYSTEMS AND RELATED AREAS On May 12,1979, representatives of Duquesne Light Company 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 a discussion of the material listed in.
The material requested in Enclosure 2 aad been sent to the Project Manager prior to the meeting. The challenges to the PORV's were not included in this package, but will be submitted within several days.
m
-j A I
's &
t L. N. Olshan, Project Manager Operating Reactors Branch ul Division of Operating Reactors
Enclosures:
As stated cc:
See next page 2318 134
/
As part of its en-going review of the Three Mile Island L'r.it 2 accident, the staff finds that it needs additional information regarding the auxiiiary feed. ater sys tems ( AFdS). This information as outlined below, is required to evaluate AFWS reliability for Combusticn 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 en 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 AF45 (primary and backup)
Current operating precedures and test and maintenance requirements including:
- All LCO's for AFAS, main FW system and raiated su;;crt systems.
Listing of cperatcr actions (local and/cr control rccm) and timing require-ments for such actions.
- Procedures for reinitiating main feedwater ficw.
As Built P& ids with spbel keys including condensate and steam side Ledgible Equipment layouts drawings including:
Iscmetrics, 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 "readcuts" available in control reca for AFWS cperation AC & DC Pcwer One line diagrams (normal and emergency pcwer supplies)
- Divisional designation e.g., Train A, Train 3, requirements en all AFWS components and support systems
- List of nomal valve states and loss-of-actuatien pcwer failure positicn Operating Experience, including Number of main feedwater interruptions per year experienced to date for each unit
.tmber of demands on AFWS per year to date (test and actual) far each unit
- Sur: ary of AFWS malfunctions, problems, f ailures Provide Available reliability analyses Steam Generator dry-cut times (assuming 1 css of all feedsater ficw, with 100%
initial pcwer, with Reactor trip, ne line breaks)
System design bases including:
- Seismic and environmental qualificatien Code and Quality, QA 2318 135 9
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1 tnClosure 2 i :;
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f.; M.-. ' rov 1de written responses c the following set of cuestions by 5/E/79
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Describe backup systems available (to auxiliary feet..a:er) fcr pr: vicing t=..+
feed <.ater to steam genera 6 rs.
Discuss acticrs and time re;uired to rake j
these systems available. Are procedures available?
If so, pr: vide, p
?
Provide the following procedures:
loss of offsite power loss of feedwater LOCA (small and large)
Steam Line Sreak Provide folicwing information for PORV's:
? lumber capacity setpcints (cpen and close) manufacturer and mcdel indications of position record of periods isolated (is:!ation valve shut) challenges during life of plant (from plant re::rds) including perfom.ance cf valve, cause of challenge.
experience of two, phase or subccoled discharge of PCRVs and safety valves with description of valve perf rmance Provide indications of PCRV isolation valve in the control r:cm.
Provide the following information on ECCS:
initiation setpoints system description pump performance characteristics (head curves)
Provide reactor protection system trip se: points.
Provide informaticn on charging pumps, hcw they relate to ECC5 inclucing:
number flow vs. pressure power sources and backup water sources seismic qualification List all challenges (and cause) to ECCS as indicated en plant records.
List and discuss all instances during which your plant has undergere natural circulation.
Describe all automatic and manual features whi:n can t:0 tne reactor s
cociant pumps.
2318 136
LIST OF ATTENDEES DUQUESNE LIGHT COMPANY MEETING ON MAY 12, 1979 DUQUESNE LIGHT COMPANY J. J. Cargy D. A. Crouch L. G. Schad NRC V. T. Leung L. N. Olshan M. A. Taylorjg j37}}