ML20024D349
| ML20024D349 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 03/08/1983 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2079, NUDOCS 8308040611 | |
| Download: ML20024D349 (11) | |
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7 PROPOSED MEETING MINUTES OF THE ACRS - CRBR WORKING GROUP APR 2 41983 ON SYSTEMS INTEGRATION AND INSTRUMENTATION AND CONTROL SUBCOMMITTEE FEBRUARY 24, 1983 - WASHINGTON, D.C.
The ACRS CRBR Working Group on Systems Integration and Instrumentation and Control held a meeting on February 24,1983, at 1717 H Street, N.W., Washington, D.C. 20555.
The purpose of this meeting was to continue the Working Group review of the CRBR Construction permit for Application. The principle area of discussion were as follows:
(1) Design changes which have been made in CRBR based on the lessons learned from TMI, (2) Control room design, (3) The Application of human factors in the Control Room Design, and Instrumentation and Control Sys tems (4) The safety related reliability program, (5) the Reliability Assessment of the shutdown heat removal systems, (6) The use of Probabilistic Risk Assessment.
The subcommittee heard presentations from representatives of NRR, the CRBR Project and DOE. The notice for this meeting was published in the Federal Register on Wednesday, February 9, 1983. A copy of this notice is included as Attachment A.
A list of attendees is included as Attachment B.
A scheduled for this meeting is included as Attachment C.
And selective portions of the handouts for this meeting are included as Attachment D.
A comple.te set of meeting handouts are in the ACRS Files. The meeting was begun at 8:30 a.m. with a short executive session in which Dr. Kerr, Subconmittee Chainnan, summarized the objectives of today's review. The meeting was adjourned at approximately 4:30 p.m. on this day, and was conducted entirely in open session.
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CRBR Working Group Mtg Minutes 2/24/83 The meeting was attended by:
W. Kerr, Chairman J. Ebersole, ACRS Member D. Ward, ACRS Member W. Lipinski, ACRS Consultant R. Nertney, ACRS Consultant A. Bice, ACRS Fellow P. Boehnert, ACRS Staf f R. Savio, ACRS*
NRC STAFF COMMENTS, R. STARK (NRC), T. KING (NRC), E. RUMBLE (NRC CONSULTANT)
Mr. Stark, Mr. King, and Mr. Rumble summarized the status of the NRC review of the CRBR reliability program. The CRBR reliability program is designed to assure safe operation and high plant availability. The safety related portion of reliability program is designed to enhance and implement the level of plant reliability that will result from the application of the General Design Criteria and to assure that the public risk from associated with the CRBR is no greater than the public risk which is associated with a current generation LWR.
Specifically, the program addresses those functions which prevent CUA's and those functions which mitigate accidents to keep site boundary doses below the 10CFR100 guidelines. A summary of the activities associated with this program is given on page 1 of attachment D.
The NRC is currently reviewing the CRBR program and is using SAI as a consultant. A list of the NRC sponsored reliability oriantated studies for the CRBR is given on pages 2 and 3 of attachment D.
The CRBR Pruject will perform probabilistic risk assessment study of the CRBR plant. This study will be completed in the later part of 1984.
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CRBR Working Group Mtg Minutes 2/24/83 Introduction by P. Gross, CRBRP Mr. Gross summarized the goals of the reliability assurance program. They are to assure the achievement of a high reliability inherent in the CRBR I
plant design concept and to assure that the risks from the CRBR is comparable to that of light water reactor. The elements of the program will assist in control over the design and manufacturing process, independent evaluation programs, equipment testing, the performance of a PRA, and a comprehensive system startup test program.
Design Changes Based on Lessons Learned from THI, by P. Dickson, CRBRP Mr. Dickson summarized the actions taken as a result of the lessons learned from Titi. The project reviewed the NUREG-0718, requirements for applica-bility to the CRBR reactor. All applicable items not previously addressed in the design were addressed in this design review. A summary of the most significant items is given on pages 4 through 8 of Attachment D.
Control Room Design Philosophy and Human Factors, by P. Planchon, CRBRP Mr. Planchon summarized the control room design for the CRBR and the use of human factors engineering in the plant design.
Photos and drawings of the control room layout are shown on pages 9 through 11 of Attachment D.
A plant computer is used to assist the control room supervisor and unit i
operator in the assessment of the plant status. The plant design is such that basics safety functions are accommodated via automatic control. the philosophy used is that the operator function is to verify the safety
CRBR Working Group Mtg Minutes 2/24/83 J
functions are being carried out and that safety system equipment is operating properly. Operator action is described for accident scenarios which involved multiple or highly unlikely failures and to take actions to improve the safety margins which are provided by the automatic actions. Monitoring the plant status is accomplished with the accidenc monitoring instrumentation and plant comuter displays. The human factors review was done in the initial design prior to the TMI-2 accident. This effort was expanded after the TMI accident and there are plans for doing more work in the future. A summary is given on pages 12 through 15 of Attachment D.
Safety Related Reliability Program, by G. Clare, and G. Macrae, CRBRP Mr. Clare and Mr. Macrae summarized the safety related portion of the CRBR reliability program.
In addition, to the safety related reliability program there is a companion effort which is intended to assure that the plant has a high availability. The program focus in the safety related reliability program is on maintaining the core in a coolable geometry.
Qualitative and quantitative analytical methods have been applied and the reliability analysis has influenced the design of the development and test programs. The initial program had as its objective the quantitative goal that it be established that the probability of exceeding 10CFR100 guidelines would be less than one chance in one million per reactor year. On reexam-ination of the program it became apparent that it would be hard to establish that this goal was meant because of the limited nature of the available data and the inherent uncertainties associated with this type of analysis. Current
CRBR Working Group Mtg Minutes 2/24/83 program objectives are to provide additional assurance that the probability of exceeding the 10CFR100 guidelines is acceptable low. A reliability related critical items list (RRCL) has been established which lists all the components, systems, and subsystems which have a direct impact on the safe shutdown heat removal.
The RRCL establishes the class of equipment which is subjected to safety related reliability design support documen-tation, common cause failure analysis, and failure mode and effect analysis.
Preliminary failure modes and effect analysis were done early in the design process and were used in the design of the component and subsystem test program. The RRCL is given on pages 16 through 20 of Attachment D.
Some of the improvements which have been made to the reactor shutdown system hardware as a result of the reliability analysis and testing are summarized on pages 21-22 of Attachment D. The results of the primary control rod system tests and a summary of the improvements which have been made in this system as a result of the reliability testing are summarized on pages 23 through 26 of Attachment D.
The results of the tests and analysis made on the secondary control rod systems and the major improvements to this system are summarized on pages 27 through 29 of Attachment D. Qualitative and quantitative assess-ments have been performed for the shutdown heat removal system. These have includea failure modes and effects analysis for critical areas of the shutdown heat removal system. The results are summarized on pages 30-31 of Attachment D.
A listing of the most significant changes are given on pages 32 of Attachment D.
CRBR Working Group Mtg Minutes 2/24/83 Systems Availability / Interaction Analysis, by P. Dickson, CRBRP Mr. Dickson summarized the systems availability / interaction analysis which was done for the CRBR plant. The fundamental objective of this work is to assure that the CRBR would provide a demonstration of the reliable operation of a breeder reactor in the utility environment. A plant availability goal of 82% has been set (96% for the balance of the plant and 85% for the nuclear island). The unavailability alloation is summarized on page 33 of Attachment D.
The elements within these programs have been reviewed by Westinghouse, DOE, and a independent contractor working for DOE.
It is believed that these goals are consistent with what has been experienced for well managed LWR plants.
Probabilistic Risk Assessment, by S. Asselin, Technology for Energy Corp.
Mr. Asselin summarized the goals of the CRBR Probabilistic Risk Assessment program. The goals are to provide an understanding of plant behavior, to support the reliability assessment program, and to provide input into the design decision process and the emergency operating procedures.
It is intended that the Probabilistic Risk Assessment (PRA) will be part of an ongoing risk management program. The PRA is to be completed and a final report issued in December 1984.
The milestones as currently scheduled are shown on page 34 of Attachment D.
To date initiating event analysis and a preliminary definition of the accident sequence has been completed. System event and fault trees have been constructed and preliminary core and containment phenomenological analysis has been performed.
2/24/83 CRBR Working Group Subcommittee Mtg.
an Meeting was adjourned.
IS ADDITIONAL MEETING DETAILS CAN BE OBTAIN ET, N.W.,
ME. TING AVAILABLE IN THE NRC PUBLIC DOCUMENT ROOM,1 NOTE:
- OMPANY, WASHINGTON, D.C., OR CAN BE PURCHASED FROM ALDERSO 20024, (202) 554-2345.
INC., 400 VIRGINI A AVENUE, S.W., WASHINGTON, D.C.,
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CLINCH RIVER BREEDER REACTOR PLANT CRBRP PROJECT 1
3RIEFING FO'R:
ADVISORY COMMITTEE ON
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REACTOR SAFEGUARDS (ACRS)
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SYSTEMS INTEGRATION AND INSTRUMENTATION I
CONTROL WORKING GROUP i
FEBRUARY 24,1983
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CLINCH RIVER BREEDER REACTOR P i
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BRIEFING FOR ADVISORY COMMITTEE ON i
REACTOR SAFEGUARDS (ACRS)
SYSTEMS INTEGRATION AND INSTR l
CONTROL WORKING GROUP l
i WASHINGTON, D.C.
l FEBRUARY 24,1983 i
AGENDA NRC STAFF l
GROSS INT RO DU CTI O N.....................................
l DESIGN CHANGES BASED ON........................... P.
l LESSONS LEARNED FROM TMI CONTROL ROOM DESIGN PHILOSOPHY........
i AND HUMAN FACTORS l
y SAFETY RELATED RELIABILITY PROGRAM /.. G. CLARE O V ERV IEW......................................G. MACR REACTOR SHUTDOWN SYSTEM............... R. GILCHR l
. G.CLARE SHUTDOWN HEAT REMOV AL SYSTEM
.................... P. DICKSON l
SYSTEMS AVAILABILITY / INTERACTION ANALYSIS i
S. ASSELIN
- PROBABILISTIC RISK ASSESSMENT................
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3059 Fed;rd Regist:r / Vcl. 48. No. 28 / Wadnesd:y. Februtry 9.1983 / Notic s 4 f.
ne Notice of Application on January National Technal Information Service.
DEPARTWENT OF JUSTICE 0.1983, pertaining to Phenylacetone Springfield. Virginia 22161.
A year's subscription to the NUREG-(
Drug Enforcement Administration (8501). Is hereby withdrawn.
0090 series publication, which consista Cm R. Haislip.
of fourissues,is avaIIable from the I
Mnufactu*er of Certtrolled Depury Assistant Adminisuotor. Ofic. of NRC/GPO Sales Program.Divis!an of r
Substances; Application Diversion Contml Drug Enfomement Technicallnformation and Document Administration Control. U.S. Nuclear Regulatory Pursuant to Q301.43(a) of Title 21 ofFeoruary L 1903.
Commission. Wa shingtion. D.C. 20555.
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tas Code of Federal Regulations (CFR).
Era on abaun N Me k4s em]
Microfiche of single, copies of the this is notice that on August 9.1982.
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Publication are also available from this Pharmaceuticals Division. Ciba. Geigy i
Corporation. 556 Morris Avenue.
- source, Dated at Washington,D.C this 4th day of Summit. New Jersey 07901. made NUCLEAR REGULATORY February 1983 f
cpplication to the Drug Enforcement COMMISSION For the Nuclear Regulatory Commission.
Administration (DEA) for registration as o bulk n'anufacturer of the Schedule D Abnormal Occurrence Report; Section samuel).cw!k, controlled substance Methylphenidate 208 Report Submitted to the Congress s,cretaryofthecommission.
I Pa D = esa m ru. Sa.as. a.s
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(1724).
Notice is hereby given that pursuant
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Any other such' applicant and any to the requirements of Section 208 of the l
person who is presently registered with Energy Reorganization Act ofl974, as i
DEA to manufacture such substance amended, the Nuclear Regulatory Adytacey Committee on floactor T
may file comments or objections to the Commission (NRC) has published and Safeguarda; Subcommittee on C8incts issuance of the above application and issued the periodic report to Congress h We RucM@ng W I
may also fi!e a written request for a on abnormal occumnces (NUREG@90, on Systemn integration and hearing thereon in accordance with 21 Vol 5 No.3)
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instrumentation and Control; Meeting 1 nder the Energy Reorganiistion Act
,The ACRS Subcommittee on Clinch l
b 1 FR 316 4 f 1974.which created the NRC, an River Breeder Reactor (CRBR) Working Any such comments. objections or abnormal occurrence is defined as 'an requests for a hearing may be addressed unscheduled acident or event which the Group o Instrumentation Control will hold a to the Deputy Assistant Administrator Commission (NRC) determines is meeting on February 24.1983. Room r
significant from the standpoint of public 1167.1717 H Street.NW Washington, Drug Enforcement Administration.
United States Department of Just,ce.
health or safety." The NRC has made a DC.The Subcommitee will continue its i
1405. I Street. N.W.. Weshing'on. D C.
determinataon. based on entens discussions of the design of the plant I
20537 Attention: DEA FederalRegister pubhshed in the Fedaral Register (42 Mt protection and control systems, the i
10950) on February 24,1977, that eventa reliability program, actions resulting f
Representative (Room 1203) and must -
be filed no later than hf arch 11,1963 Involving an actualloss or sigrdficant from the post-Th0 2 accident review, reduction in the degree of protection and the use of human factors Cena R. Ifaistip, against radioactive properties of source, engineering in the design. Notice of this Deputy Assistent Administmtor. Ogcc of special nuclear, and byproduct materials meeting was published january 18,1983.
,f Diversion Contml. Drug Enforcement are abnormal occurrences.
In accordance with the procedures Administmtion.
His report to Congress is for the third outlined in the Federal Registar on -
February 1.19a3.
calendar quarter of1982.The report October 1.1982 (47 FR 43474), oral or gra om ses ruw na ses g identifies the occurences or events thatwritten statements may be presented by an.uwo coot mm-as the Commission determined tobe members of the public, recordings will
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significant and reportable; the remedial be permitted only during those portions
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actions that were undertaken are also of the meeting when a transcript is being Manufacturer of Controlled described. During the report period.
kept, and questions may be asked only Substances; Correction there were two abnormal occurrences:
by members of the Subcommittee,its one at a licensed nuclear power plant consultants, and Staff. Persons desiring On January 61983. the Drug and one at another NRClicensee.The to make oral statements should notify Er.forcen ent Administruiion put. fished a first involved!oss of auxiliary electrical the Cognizant Federal Employee as,far Notice of Application in the Federal power and the second involved rupture in advance as practilable so that Register (Vol. 48. No. 4. pgs. 757 and 758) of at least one americium.241 well appropriate arrangements can be tnade stating that the Pharmaceuticals logging source.ne Agreement States' to allow the necessary time during the Division. Ciba.Ceigy Corporation. 55e reported no abnormal oqcurtrences to meeting for such statements.
hfortis Avenue. Summit.New jessey the NRC.
The entire meeting will be open to,.
07901,had submitted en applicht en for The report also contains information public attendanca, registration as a bulk manufacturer of updating some previously reported De agenda for subject meeting shall Thenylacetone (8501), a basis class of abnormal occurrences.
be as follows:
cor. trolled. substance in Schedule !!.
Interested persons may revi,ew the Thursday. february 2d.1983-a.30 Dis Notice sidvtses that the report at the NRC's Public Document o m. until the conclusion of business.
Pharmaceuticals Division. Ciba-Ceigy Room.1717 H Street. NW Washington, During the initial protion of the Corporation.556 hforris Avenue.
D C., or at ony of the nuclear power mcclir.g. the Sabcurra.~ttee. = fung with Summit.Ncw [ctscy 07901. did out a pply plant Lneet public Decument Rooms for res;istration as a bu!k manufaturer throughout the country. Single copies of any of its consultants who may be t
present,muy exchange preliminary of Phenylacetone 18501)..
the report. designated NtJREG-0000, Vol. 5.No. 3.may be purchased from the views regarding matters to be
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6060' Federal Recister / Vol..lR. No. 28 I Wednesday, l'ebrum 9.1983 / Noticzs 1
considerzd dunng the ba!.mce of the of events smc2 issurnee of the Palo compara e to, and perhn s svan farster Verde Nuclear Generating Station than. that undcriaien pnur to the meeting Ti.- Sibror-*r"".a.* w.II !I'-n her ron4tt ui.tp.n perm t 8n the l'censees. 'ba e nr,4;ructiert giormit review.
pr-nentations by and hold decus inns sisffs of the Offire of Nuc! car Reactor Subsequent to it.e fahng of the with ;ne aftpartment ct Energy and :ne ir twgc:.stion and sne Omce ci Executae ongmat t P appucanon, douthern represenistives. the hTsC Staif and their le;.1 D;i c:or. Leicaliu seierred tu as Califurr ia 1.disun Ccmpany (SCEl. Los c nsultaMs. and other inter-e d the " staff". hne inintly ennelu led. after Anges Departrrent of Water and c
persons regarding this review.
consulting with the Department of Power (LADWP) and Southern 4 -
Further information ggstding topics justice, that the changes that have California Public Power Authority
-- i to be discussed, whether the meeting occurred since the antitrust construction (SCPPA) become participants and the
'W 3 has been cancelled or rescheduled, the permit reviews are not "significant"in M.S.R Pub!!c Power Agency became a yi Chairman's ruling on requests for the the antitrust context to require a second tentative participant in Palo Verde.The i!#
cpportunity to present oral statercents formal antitrust review at the operating cewtrut.ran permit review of SCE.
cnd the ti'ne allotted therefur can be license stage of the application for completed in 1976 did not reveal a need gbtained by a prepaid telephone call to licenses. Staff has concluded that those to Irnpose license conditions on SCE's the Cognizant Decig,ated Federal changes which have occurred either are participation in Palo Verde. Still la ter, in 2
Employee. Dr. Richard Savio (te!ephone not reasonably attributable to the 1951. en examination by staff of ACE's 202/C':4-3287) between 0.15 a.m. and licensees or do not have antitrust activities since the issuance of the San d,
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implications that would likely warrant Onofre 2 and 3 construction permits a
some Com:nissit: remedy. In reachir'4 resdted in a statt finding that no
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this conclusion, the staff considered the "significant changes"in SCE's activities
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structure of the electric utility industry had occurred with respect to the San
- ? 4 Ejl AuWsory Committe, Mono;,mant Officer-in the south. western United States, the Onofre 2 and 3 eperating license Ci tra o r. wus r.Se a-w e" *1 events rcle.unt to the Palo Verde application. In tne bnef time period am m o caos r m i-u construction per: nit antitrust reviews since the issuance of the San Onofre 2
,E and the events that have occurred and 3 operating license finding, the staff d-4 subsequent to those permit reviews.
has not obtained any information that
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[ Docket Nos. 50-520 A. 529Al "The Conclusion of the stairs analysis woud nutgest a contrary finding of Arizona Public Service Co. et.at.;
is as follows:
"significant change" with respect to the id? J Finding of No Significant Antritrust The staff has applied the Palo Verde 1 and 2 operating license.
M-Ch:nges and Time for Filing of Commission s "significant change 1.ADWP and SCPPA became owners of
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Requests for Reevatuation criteria in examining the antitrust Patn Verde in 1981.The construr. tion a
d 11 f\\h permit review of1.ADWP and SCPPA
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/ The Director of Nuclear Reactor
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Rigulation has made an initial finding in (p$jg'a'nts for the Palo Verde 1 end 2 which terminated on April 8.1982
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accordance with Section 105c[2) ci the operating licenses subsequent te the S-R ncently withdnw its participation -, M. 2 Atom!:Ener y Act cf12:1. cs c=en:kd Comnussion's previous construction th t no signibcant (antitrust) changes in permit antitrust reviews.
- I*'.ly brief period of time since the thz licensees
- activities or proposed Arizona Public Service Company c mpletion of me castmcuon permit g
cetivities have occurred subsequent to (APS) and Salt River Project reviews of1.ADWP and SCPPA the staff g tha previous construction permit Agricultural and Improvement District has not kcome aware of any actual or reviews of Palo Verde Units 1 and 2 by (SRPj. two of the four remaining original Potential antitrust problems.
7j, the Attorney General and the applicants for the Palo Verde Tand on de fangoing analysis.the Commission.The finding is as fo!!aws:
construction permit, had agreed to the
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"Section 105c(2) of the Atomic Energy inclusion of a wheelinglicense condition staff has, cecluded that the changes in the appbcant s activities since the
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Act of 1954, as amended provides for an in the construction permit so as to completion of the Palo Verde g
cntitrust review of an application for an mitigate potential anticompetitive constmetion perrnit antitrust reviews do cperatinglicense.if the Commission problems arising from contracts with not have any antitrust implications and, y dif ermines that significant changes in smaller utilities. In the period since the thus, do not require a further. formal
.g, the licensee's activities or proposed construction permit review both APS ant l trust review at the operating bcense 7j activities have occurred subsequent to and SRP have provided. In staffs view, the previous construction permit review. wheeeling services consistent with the 2., age with respect to Palo Verde 1 and Q'
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The Commission has delegated the intent of the license condition. Further.
finding that a formal operating license" Bas
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authority to make the "significant ASP and SRP have continued to provide f
l ch:nge" determination with respect to other types of bulk power services to nuclear reactors to the Director. Office smaller utilities not dissimilar to those antitrust review of the !!censees with
,p cf Nuclear Reactor Regulation-offered psfor to the completion of the respect to the Palo Verde Nuclear y
" Participating in the Palo Verde construction permit review. Public Generating Station. Units 1 and 2. Is not, Jte Nuclear Generating Station. Units 1 and Service Company of New Mexico nquind."
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R.Denton. Director. Office of Nucleme,,m Signed on January 28,1983, by flarold f.
2 are Arizona Public Service Company.
(PSNM) and El Paso Electric Company Salt River Project Agricultural (EPE). the other two remaining original
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..q Improvement and Power District. Public Palo Verde applicants.were not Reactor Regulation.
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Any iT;.cn whe.a kiaMi anay L6 W-,2-s l
l Paso Electric Company. Southern the enn=tructinn permit stage.
affected pursuant to this initial
- * :.,"g 4 California Edison Company. I.os Nonetheless. PSNM and EPE have deterrnination may fi!c with full
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An&ds Departmant of Water and i.uniued to offer ud pruside to p.a;Uco!.ts a request for mealuation
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Power. and Southern California Public smaller utilities whotesate power with the Directnr of Nuclear Reactor Commission. Washington. D.C. 205 Re;;ufation. U.S. Nuclear Regulatory Power Authority, collectively referred to service, wheeling serdce and various cs " licensee " Based upon examination ot' er cocIdination services on a scale
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