ML17297B272
| ML17297B272 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/03/1982 |
| From: | Licitra E Office of Nuclear Reactor Regulation |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8202110327 | |
| Download: ML17297B272 (18) | |
Text
FEB 3 "'982 Docket Nos:
0-5
/50-529 and 5 - 30 MEMORANDUM FOR:
FROIl:
SUBJECT:
f./J~,
~ac'@~/is F. J. Miraglia, Chief, Licensing Branch No. 3, DL E. A. Licitra, Project Manager, Licensing Branch No. 3, DL FORTHCOMING SITE VISIT BY CASELOAD FORECAST PANEL FOR PALO VERDE, UNITS 1, 2 AND 3 DATE 5 TINE:
LOCATION:
PURPOSE:
- Tuesday, March 16 thru Friday, March 20, 1982 9:30 AM (each day)
Palo Verde Site, Administration Building Maricapa County, Arizona To discuss the status of construction for each unit (Agenda attached) and to tour the facilities PARTICIPANTS:
APS E.
Van Brunt and W. quinn, et. al.
BECHTEL Representatives NRC I
82021i0327 820203 PDR Pop{,g pgPPPg28 A
PDR W. Lovelace, E. Licitra. L. Vorderbrueggen and G. Fiorelli
Attachment:
Agenda cc:
See next page
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Emanuel A. Licitra, Project Manager Licensing Branch No.
3 Division of Licensing See attache sheet for distribution OFFICE/
SURNAME) 0AVED DL:L ¹3 2/
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/82 DL 3
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/82 NRC FORM 3IB IIO/80)NRCM0240 OFFICIAL RECORD COPY a USGPO; 198~29.824
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C.
Mr. E. E. Van Brunt, Jr.
Vice President - Nuclear Projects Arizona Public Service Company P. 0.
Box 21666 Phoenix, Arizona 85036 PALO VERDE cc~
Arthur C. Gehr, Esq.
Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Charles S. Pierson Assistant Attorney General 200 State Capitol 1700 West Washington Phoenix, Arizona 85007 Charles R. Kocher, Esq., Assistant Counsel James A. Beoletto, Esq.
Southern California Edison Company P. 0. Box 800
- Rosemead, California 91770 Margaret Walker Deputy Director of Energy Programs Economic Planning and Development Office 1700 West Washington Phoenix, Arizona 85007 Mr. Rand L. Greenfield Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Resident Inspector Palo Verde/NPS U.S. Nuclear Regulatory Commission P. 0.
Box 21324 Phoenix, Arizona 85001 Ms. Patricia Lee Hourihan 6413 S. 26th Street
- Phoenix, Arizona 85040
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PALO VERDE UNITS 1, 2, AND 3 CASELOAD FORECAST PANEL SITE VISIT MEETING AGENDA l.
Overview of project construction schedule including progress and major milestones completed, current problems, and any
'nticipated problem areas that may impact the current projected fuel load dates for each unit.
2.'etailed review and current status of design and engineering effort (by major discipline) including any potential problems that may arise from necessary rework for each unit.
3.
Detailed review and current status of procurement activities including valves, pipe, instruments,
- cable, major components, etc. for each unit.
4.
Actual and proposed craft work force (by major craft), craft availability, productivity, potential labor negotiations and problems for each unit.
5.
Detailed review and current status of all large and small bore pipe hangers, restraints, snubbers, etc., including design, rework, procurement, fabrication, delivery, and installation for each unit.
6.
Detailed review of project schedule identifying critical path items, near critical items, amount of float for various activities, the current critical path to fuel loading, methods of implementation of corrective action for any activities with negative float, and provisions for contingencies for each unit.
The estimated project percent construction complete as of February 28, 1982 for each unit.
7.
Detailed review and current status of bulk quantities including current estimated quantities, quantities installed to date, quantities scheduled to date, current percent complete for
- each, actual versus forecast installation rates, and basis for figures for each unit.
(a)
Concrete (CY)
(b)
Process Pipe (LF)
Large Bore Pipe (2 1/2" and larger)
Small Bore Pipe (2" and smaller)
(c)
Yard Pipe (LF)
(d)
Large Bore Pipe Hangers, Restraints, Snubbers (ea)
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(e)
Small Bore Pipe Hangers, Restraints (ea)
(f)
Cable Tray (LF)
(g)
Total Conduit (LF)
(h)
Total Exposed Metal Conduit (LF)
(i) i Cable (LF)
Power Control Security Instrumentation Plant Lighting (j)
Terminations (ea)
Power Contr ol Security Instrumentation Plant Lighting (k)
Electrical Circuits (ea)
Power Control Security (1)
Instrumentation (ea) 8.
Detailed review and current status of preparation of preop and acceptance test procedures, integration of preop and acceptance test activities with construction
- schedule, system turnover schedule, preop and acceptance tests
- schedule, current and proposed preop and acceptance tests program manpower for each unit.
(a)
Total number of procedures required for fuel load.
(b)
Number of draft procedures not started.
(c)
Number of draft procedures being written.')
Number of procedures approved.
e Number of procedures in review.
(f)
Total number of preop and acceptance tests required for fuel load.
(g)
Number of preop and acceptance tests completed.
(h)
Number of preop and acceptance tests currently in progress.
(i)
Number of systems turned over to start-up.
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9.
Detailed discussion of potential schedular influence due to changes attributed to NUREG-0737 and other recent licensing requirements and status for each unit.
10.
Discussion of schedular impact, if any, regarding potential deficiencies reported in accordance with 10 CFR 50.55(e) for each unit.
ll.
Financial commitments to complete Units 1, 2, and 3.
12.
Overview of current construction management organization and activities incorporating each unit.
13.
Site"tour and observation of construction activities for each unit.
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Docket File 50-.
NRC PDR Local PDR NSIC TERA LB¹3 Files E.
Case D. Eisenhut R. Purple R. Tedesco B. J.
Youngblood A. Schwencer.
F. Miraglia E.
Adensam J. Miller G. Lainas
. T. Ippolito B. Russell D. Crutchfield T. Novak S.
Varga D. VaRsallo R. Clark.
J. Stolz R. Vollmer J.
Knight R.
Bosnak F.
Schauer R. Jackson G. Lear
- Attorney, OELD OIE (3)
ACRS (16)
OSD P)
J.
- LeDoux, I&E B. Grimes, I&E M; Wi.lli:ams, DL W. Johnston AS. Pawlicki V. Benaroya Z. Rosztoczy W. Haass D. Muller R. Ballard W.
Regan A. Toalston MEETING NOTICE DISTRIBUTION I&E Region I I&E Region II l&E Region III I&E Region'V I&E Region V
NRC Partici ants W, Lovelace E. Licitra L. Vorderbrueggen G ~ Fiorelli R. Mattson T. Speis M. Srinivasan
- 0. Parr F.
Rosa B: Sheron, Acting L. G. Hulman R. Houston W. Gammill F. Congel
L. Rubenstein W. Butler C. Berlinger F. Schroeder K, Kniel D. Skovholt G. Knighton M. Ernst A. Thadani W. Minners S.
Hanauer H. Thompson D. Vassallo P. Collins D. Ziemann V. Moore Regional Administrator Robert Engelken bcc:
Applicant Servic Branch LB¹3 Project anager E. A; Licitra Licensing Assistant J.
Lee
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gAg P EI )982 p.M r~/e 53-QE Z29y~g MEMlORANDUM FOR:
Frank J. Miraglia, Chief, Licensing Branch 83 Division of Licensing FROM:
SUBJECT:
Faust Rosa, Chief, Instrumentation
& Control Systems Branch Division of Systems Integration
RESPONSE
TO ACRS COMMENTS ON PALO VERDE OPERATING LICENSE REVIEtl BLC~g'EQ FES 8 1982~
m Lent> EKtut.u rUU. <<e Z
DiihQH VJ Witt 2R TlDC Plant Name:
Palo Verde Nuclear Generating Station, Unit Docket Nos.:
50-528/529/530 Licensing Status:
Not Applicable Responsible Branch:
LB 83 Project Manager:
J. Kerrigan Review Branch:
ICSB Review Status:
SSER Per the request of Manny Licitra, attached is a proposed r
ACRS member Mr. Bender's comments on Regulatory Guide 1.97 contained in the ARCS letter of December 15, 1981, on Palo Verde.
The response indicates general agreement with Hr. Bender's comments and states the staff belief that the criteria recommended by Mr. Bender have been and are being followed.
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R. Mattson J. Rosenthal E. Henzinger A. Hintze F.
Rosa C. Rossi J. Kerrigan R. Capra H. Licitra T.. Speis
Contact:
C. E. Rossi X27140 "Ori8inal signor gy:
Faust'Rosa" Faust Rosa, Chief Instrumentation 5 Control Systems Branch Division of Systems Integration
- 'DISTRIBUTION:
ICSB Reading File C. E. Rossi (PF)
Palo Verde Subject File
'I OFFICE SURNAME DATE i
.ct 1/Zg /82 ICSB SI FRosa 1/g I/82 NRC FORM 318 (10.80) NRCM 0240 OFFICIAL RECORD COPY
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ENCLOSURE 1
Regulatory Guide 1.97 was developed over a period of several years.
(beginning before the TMI-2 event) and made extensive use of work performed by the IEEE and ANS to develop IEEE Std. 497-1977, "Trial-Use Standard "Criteria for Post Accident Monitoring Instrumentation for Nuclear Power Generating Stations" and ANSI/ANS-4.5-1989, "Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors".
Through-out the period of development of the Regulatory Guide, comments from industry and the ACRS were received and considered.
Atomic Industrial Forum input was also used in development of the list of parameters in the final regulatory guide.
" The staff believes that the specific criteria proposed by Mr. Bender in the ACRS letter of December 15, 1981, were included in developing the guidance delineated in Regulatory Guide 1.97.
The staff agrees that only a few additions to the pre-TMI-accident instru-mentation should be necessary.
Furthermore, since regulatory guides are not regulations,'ndivi'dual licensees may take exceptions to the guidance in Regulatory Guide 1.97 to reflect plant specific design features.
The effect of implementing Regulatory Guide 1.97 will not be to provide indications for a large number of additional plant parameters, since most of the parameters are currently indicated in plant control rooms.
It should also be noted that riot all parameters listed in the Regulatory Guide are to be continuously displayed.
Some must only be available should the need arise after an accident has occurred.
The primary,effect of implementing the Regulatory Guide will be to insure that 1) the equip-ment used for indication of specific parameters will survive the accident
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environment which could exist when the indication is required, and 2) sufficient redundancy of indications is provided to insure that required information will be available following single equipment failures (such as loss of a single power source).
The staff goal is that the Regulatory Guide 1.97 instrument displays, the Safety Parameter Display System, the control room design review, and.the development of symptom oriented emer-gency operating procedures be integrated with respect to the overall enhancement of operator ability to comprehend plant conditions.
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