ML20052A082
| ML20052A082 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 04/12/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8204270051 | |
| Download: ML20052A082 (6) | |
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DISTRIBUTION tlITHOUT EllCLOSURE 1:
Dockt File RIngram Il0rnstein flRC PDR fiPadovan EBlackwood L PDR DEisenhut ORB #4 Rdg 0 ELD Docket No. 50-312 h0D p
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I Mr. J. J. Mattinoe 7
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Assistant General Manager and r
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6201 S Street
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P. O. Box 15830
'D Sacramento, California 95813
Dear Mr. flattinoe:
For sone tine, there has been a growing awareness of the need to reexanine the rethods by which we inpose new requirenents on the nuclear industry.
As you know, a significant step in this direction has been taken with the establishnent of the Comittee to Review Generic Requirerents that reports to the Executive Director for Operations. We believe that the extra neasure of review that will be provided by this comittee will help ensere that future new requirenents strike a proper balance between potential safety enhancenent and potential inpacts.
One inportant elenent in our decision-naking process for new requirenents is the deternination of the appropriate tine-scale for when the requirenent should be innlenented. We have learned through several recent exanples that the establishment of a single industry-wide date for inplenenting a new requirenent is of ten not the best way to proceed, particularly for f tens for which an innediate, highest-priority response is not needed.
Sinila rly, to inpose arbitrary corpletion dates on all itens could lead, and nay have already led, to situations where utilities, in an ef fort to be responsive, either divert engineering resources from other work which nay be more safety significant in the long run, or to a less than adequate engineering job in order to neet the inposed deadlines. We are, therefore, considering deternining implerentation schedules on a plant-specific basis rather than atterpting to inpose industry-wide inplerentation dates.
To further explore this approach, we solicit your assistance. He would like to work with a few licensees over the next few weeks to develop a practical procedural approach that can then be applied to all licensees. As a first step in the effort, we believe that we need to develop a nutually understood inventory of the workload f acing you that constitutes a denand on your resources or requires plant shutdown tine.
We recognize that this inventory includes itens fron several sources, including, NRC-inposed post-licensing 'requirenents (either direct or implied) and your own plans for special plant naintenance or design nodifications.
Enclosed is a copy of 140 REG-07t8, which contains a listing of all of the itens for which 11RR is tracking progress. Also enclosed is a listing of the IE Bulletins that have not yet been closed out s;m pi at;.
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. applicability to your plant, and identify any additional items that will corpete for your resources over the next two years.
In deciding on what kind of items should be listed, we recognize the need for some threshold criteria that would eliminate the smaller, less consequential tasks.
Your thoughts on this would be appreciated. Upon -receipt of your response, which _should include a total inventory of what you see facing you in the next couple of years, including resources and plant shutdown impact, we would like to meet with you to explore ways in which this workload, as well as. future new requirements, can be scheduled in a manner consistent with safety needs and in a manner that will make the most effective use of both your and our resources. The system ultimately adopted, or course, will have to be periodically updated to maintain its accuracy.
The end product of this effort will be a program that we plan to initiate industry-wide to bring better control and predictability to our regulatory process as it affects operating reactors. Your participation in this developmental effort is vital to its success.
Your pronpt response including suggestions to enhance the efficiency and usefulness of the data collection and utilization, would be appreciated.
Sincerely, UWnal signed bp Darrell G. Eisenhut, Director Division of Licensing 4
Enclosures:
As stated cc: See next page i
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4 onep NHC FORM 3141460) NRCM Quo OFFIClAL RECORD COPY uso m i,.i-m m
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=y Sacramento Municipal Utility Rancho Seco, Docket No. 50-312 District cc w/ enclosure (s):
' David S. Kaplan, Secretary and Christopher Ellison, Esq.
General Counsel Dian Grueufch, Esq.
Sacramento !!unicipal Utility California Energy Comission District 1111 Howe Avenue 620i S Street Sacramento, California 95825 P. O. Box 15830 Sacramento, California 95813 Ms. Eleanor Schwartz California State Office Sacramento County 600 Pennsylvania Avenue, S.E., Rm. 201 Board of Supervisors Washington, D. C.
20003 827 7th Street, Room 424 Sacramento, California 95814 Docketing and Service Section Office of the Secretary Business and Municipal Department U.S. Nuclear Regulcory Comission Sacramento City-County Library Washington, D. C.
20555 828 I Street Resident Inspcctor/ Rancho Seco Sacramento, California 95814 c/o U. S. H. R. C.
14410 Twin Cities Road Herald, CA 95638 Dr. Rir.hard F. Cole Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Regional Radiation f.epresentative EPA Recion IX Mr. Frederick J. Shon 215 Fremont Street Atomic Safety and Licensing Board San Francisco, California 94111 Panel U.S. Nuclear Regulatory Comission Mr. Robert B. Borsum Washington, D. C.
20555 Babcock & Wilcox Nuclear Power Generation Division Elizabeth S. Bowers, Esq.
Suite 220, 7910 Woodmont Avenue Chairman, Atomic Safety and Bethesda, Maryland 20814 Licensing Board Panel U.S. Nuclear Regulatory Comission Thomas Baxter, Esq.
Washington, D. C.
20555 Shaw, Pittman, Potts & Trowbridge 1800 M Street, N.W.
Washington, D. C.
20036 Herbert H. Brown, Esq.
Lawrence Coe Lanpher, Esq.
Hill, Christopher and Phillips, P.C.
1900 M Street, N.W.
Atomic Safety and Licensing Board Washington, D. C.
20036 Panel U.S. Nuclear Regulatory Commission Helen Hubbard Washington, D. C.
20555 P. O. Box 63 Sunol, California 94586 l
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Sacraments Municipal Utility
- District Atomic Safety and Licensing Appeal Mr. Robert H. Engelken, Regional Administrator U. S. Nuclear Regulatory Commission, Region V Board Panel U.S. Nuclear Regulatory Commission 1990 N. California Boulevard, Suite 202 Washington, D. C.
20555 Walnut Craek, California 94596 Alan S. Rosenthal, Chairman.-
Atomic Safety and Licensing Appeal Board U. S. Nucicar Regulatory Connission Washington, D. C.
20555 Dr. John H. Buck Atonic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Christine M. Kohl Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Commission Washington, D. C.
20555
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California Department of Health ATTN: Chief. Environmental Radiation Control Unit' Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 e
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.C IE BULLETINS WHICH HAVE NOT YET BEEN CLOSED OUT ON SOME PLANTS Bulletin No.
Date of Number of Plants and Title Issue Affected 79-02, Pipe Support Base 3/8/79 All power reactors Plates Using Concrete having a CP or OL Expension Anchor Bolts 79-13, Cracking in 10/16/79 Al1 PWR's having-Feedwater System Piping CP or OL e
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79-14. -Seismic Analysis having a CP or*0L Systems 79-15 Deep Draft 7/9/79 All power reactors Pump Deficiencies having a CP or OL
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79-21, Temperature Effects 8/13/79 All PWRs having an OL -
on Level Measurements 79-26, Boron Loss from 11/20/79 (Rev. 1 All operating BWR plants; BWR Control Blades was issued on for BWRs under constructir 8/29/80 to change
- NRR is to include require-required submittal ments in licensing date for the metal-Process.
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79-27, Loss of Non-Class 11/30/79 All power reactors with IE Instrumentation and an OL and those plants Control Power System Bus nearing OL licensing.
During Operation 80-06 Engineering Safety 3/13/80
_ All power. reactors Features (ESF) Reset having an OL Controls s
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Date of Number of Plants
' Jnd Title Issue Affected 80-07. BWR Jet Pump 4/4/80 All BWR-3 and B',lR-4 Beam Failure plants having an OL 80-08, Examination of 4/7/80 All power reactors Containment Liner having a CP or OL Penetration Welds
---8'0,_1l1, Masonry Wall; Design 5/6/80 Allp[w a CP or.er reactors hav OL b- %&~n es.
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S/12/80 All BNR plants having ~
. Sprhy Spargers an OL':
80-16, Potentihl Misapplication 6/27/80 All power reactors having of Rosemount Pressure Trans-a CP or OL mitters
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'80-21 Valve Yokes ~ Supplied 11/6/80 All power reactors having by Malcolm Foundry Co., Inc.
a CP or OL 80-25, Operating Problems with 12/19/80 All operating and NTOL Target Rock Safety-Relief 3WR plants; for BWRs unde Valves at BWRs oonstruction, NRR is to include requirerents
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81-01, Surveillance of.
1/26/81~ revised All power reactors having p.
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3/4/81 to change an OL plus six NT0Ls.* J the affected CP
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. 81-02, Failure of Gate Type 4/9/81 AllplantsI1avingaCPor Valves to Close Against OL Differential Pressure 81-02, Supplement 1, Failure 8/1 8/81 All plants having a CP of Gate Type Valves to Close or OL Against Differential Pressure 81-03, Flow Blockage of Cooling 4/lb/81 All plants having a CP or Water to Safety Related Com-ponents by CORBICULA SP, (Asiatic Clam) and MYTILUS SP, (Mussel) 4
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