ML20028B303
| ML20028B303 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/15/1982 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028B304 | List: |
| References | |
| NUDOCS 8211300270 | |
| Download: ML20028B303 (14) | |
Text
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UNITED STATES
,i' ?a.. [I i f<UCL. E AR REGOLATORYfCOMMISSION 1 l<. '
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5Ah LliGO GAS 6 ELEClRIC COM'sAhY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNI A
. DOCKET NO.
50-362
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SAN CNOFRE NUCLEAR GENERATING STATIJy, UNIT 3 l
FACILITY OPERAllt.G LICENSE a
License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) hes found that:
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A.
The application for licenses filed by the Southern California Edison Ccmpany, San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (the licensees), as anended, complies with the standards and re:uirere s Of the Atenic Energy Act of 1954, as are'nded (the Act), anc tne C ission's regulations set forth in 10 CFR Cha;:er I, arc all reru're: rotificatiens to Other agencies or bodies have beer. culy race; 1
E.
C: I: u::icr. :f the Sar Cr.cfre Nuclear sencra ing Stati:n, Uni: 3 (the f aciid:y), ' as been substantially cnoleted in ccqformity e
4-wri:n C stru::i:r. r --it
'.'o. CFFR-96 and the a;olication as amended, e
- ne :r vis': s f tre :.ct, and :ne regulaticns of r.e Cc -issicn; i
l C.
Tne facility vcill c?erate in conformity with the application, as a er.cer, :ne provisicns of the Act, and the regulations'of the Ccn-ission; D.
Tnere is reascratie assurance:
(i) that the activities authorized l
by :his coeratirg license can be conducted without endangering the i
F.eal:n ar.d safety of the public, and (ii) that such activit,ies will be conducted in compliance with the regulations of the Commission set forth in 10 CFR Chapter I; E.
Tne Scu:hern Calif trnia Edison Company" is technically qualified to engage in the activities authorized by..this operating license in accordance with the Ccar.ission's regulaticns set forth in 10 CFR Chapter I;
'ine Sca nern Calif ornia Edison Conpany is authorized to act as agent for the c:Ler co-cuners and has exclusive resconsibility and control over the physical
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l 8211300270 821115
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F.
ine licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.
The issuance of this. license will not be inimical to the common defense and security 'or to the health and safety of the public; 4
H.
After weighing the environmental, economic, technical, an'd othe'r benefits of the facility against envirennental and other costs and considering available alternatives, the issuance of' Facility Operating License No. NPF-15, subject to th'e condition for pro-
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tection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and.
l 1.
The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accor-dance with the Commission's regulatiens in 10 CFF. Parts 30, 40 anc 70.
2.
Eared : the fcres ' g fir. dings, the Cartial Initial Decisien issued by
- e ::;nic Safety anc Licer. sinc Ecarc cn January li,1952, and the
- -itial Cecisi:n iss.ed by the A onic Safety ar.d Licensine Board en
" ; l',1;E2 regar:ir;
'is facility, Faci".ity :;eratinc License No.
3
' F 1E is herery issucc to the Scutnern California E:iscq Conpany, the Sa D c;; Gas a-d Eie::ric Cc.rany, ne City of :.ive side, California, a.:
ne City cf Ar.a ai, Cali!:rria :c reac as f:llo.s:
A.
Tris license applies to the San Onofre ';uclear Ger.erating Station, 4
I Uni: 3, a pressurized water nuclear rea: tor anc asscciated equipnent,,
(:ne f acility), curan by the licensees.
Tne facility is located in San Diego County, California, and is described in the Final Safety,
i
- .alysis Report, as arenced, through A.er.dment 20, and the Environmental Re
- Ort, as amendec, thrcLgh Amendr.ent 6.
B.
Subject to the conditions and requirements incorporated herein, the j
C. issi:n hereby' licenses:
(1) Southern California Edison Company, San Dieco Gas anc Electric Ccepany, the City of Rivers.ide, Californi.a.
and the City of Anaheim, California to possess the facility at the designated locatic, in San Diego County, California, in acccrdance with the procecures and limi-tations set forth ir, this license; (2)
Southern California Edison Ccmpany (SCE), pursuant to Section 103 of the Act and 10 CFR Dart 50, " Domestic Lice ting of Tr;du::i:n a-d U.ili stier. Ft:elities,' to
- ste:s, ;~e, and c:,0ra.s ; ;a f a:# 1ity ::
.3 dcsigna:ed I C c at i : n i n.'s'l [ispo C:.r.;j, Cal'ftrni! ir a:ccid;r.ce wi:h the 7"O:i;J~es
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SCE, pursuan
- o :ne A:. an: 10 CFR Par: 70, to re.s ve, possess, and use at any time special nuclear material as
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reactor fuel, in accordance with the limitations for storage and anounts recuired for reactor operation, as described in the Final Safety Analysis Report, as supplemented and. amended; (4)
SCE, pursuant to the A:: and 10 CFP Parts 30, 40, and 70, to receive, possess, and use at any time any. byproduct, source and special nuclear materials as sealed neutron sources fo'r reactor startup, sealed sources for reactor instrumentation 1
and radiation nonitoring equipment calibration, and as fission detectors in amounts as required; (5)
SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to i
receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or ccmponents; and l
'f)
SCE, cursuant to the * : and 10 CFF. Parts 30, 40, and 70 to pessess, N: r.o: se:arate, such by r:d :t a.c special nu:Isar r.ateriais as nay be producec by the cperation of tne facility.
C.
Tnis license shall be ces ed to c:ntair. anc is subje:: to the conditicns s:t:ifiec ir the Comissicn's regulatiens set farth in 10 CFR Chapter I I: is subje:: :: all at:lica;ie provisi0ns of the A:t a.d to the rules, e;;la:i rs tr.: tr:ers Of':te C:rissi:r r:- or nereafter in ef fect; an: is sa: jet; to the acditional ccnditicas specified or incer;: orated below:
(1) Maxir.am ;Orcer Level Southern California E:isen C:mpary (SCE) is authorized te operate ne facility at reactor core power levels l
not in excess of 3390 regavatts thermal in accordance with the conditions specified herein and in Attachment 1 j
to tnis license.
The preoperational tests, startup tests and other items identified in Attachment 1 to this license l
l shall oe completed as specified. is hereby l
incorporated into this license.
Pending Cem-ission approval, l
this license is restricted to core power levels not to exceed fi.e percent of full pr.ser (169.5 r.egawatts thermal).
- - -. ~... -
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i (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B attached hereto are hereby' incorpcrated in this license.
SCE shall cperate the facility in accordance with the Technical Speci,fi-cations and the Environnental Protection Plan.
(3)
Antitrust Conditions SCE shall comply with the antitrust conditions delineated in Appendix C to this license.
(4)
Containment Tendon Surveillance (Sectien* 3.8.1, SER, SSER #5)
Within two (2) years of the date cf issuance of this license, SCE shall provide for NRC approval, and within three (3) years of :*.e :::e cf issuance of this l';ense, SCE shall inplement a tend:n surveillance test procram which will ensure full conformance
- v. i : - :ne :revisicr.s Of Esgula:Ory 5;ide 1.25 and Regulatory Guice i
1.35.1.
inis :end:n surveillance ;rcgran snail incluce a specific -
prc;rar and ccm-it ents for re-tensiening of the tendens, such tha; the predi;tec ;restressir.; for:e of eac$ ter.cen will be greater than the required design prestressir.; for:e of the ter. don fcr the.er ire :lant life.
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(E)
Envir:- ental Ouelification (Secticn 3.11, SER, SSER 43, SSER 44) a.
Prie-to startu: 'olioning the first refuelin'g dutage, the facility shall du ':, compliance ui:n the provisia.1s of NUREG..
CE?E, "Interie Staff Position en Environmental Qualification.of Sa fety-Rela ted Electrical Equi;nent," Revision 1, dated July
(
19El, for safety-related electrical equi; ent exposed to a j
harsn environment.
I l
b.
Complete a'nd auditaole records shall be available and caintained at a central location which describe the environmental cualification status for all safety-related electrical ecuipment.
Such records shall be updated and maintained current as ecuipment is replaced, further tested, or otherwise further cualified to document complete compliance.
l I
c.
SCE shall inplement and keep in effect at all times the environmental qualification maintenance procedures identified in the SCE letter of August 23,19S2, as modified by the NRC le:.ir of August 30, ;EEE.
-~ 1.e : -(n: ret;;ai n:::.:cn foi':s'r; ite ;itle f rary li:ense ce ditions
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Prior to startup following the first refueling outage, SCE c.
shall provide affirmation of implementation of the improved
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surveillance and improved maintenance program procedures.
(6) _Hich Burnuo Fission Gas Release (Section 4.2.2.2, SER)
Prior to beginning the cycle of reactor cperation during wh,ich
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peak fuel pellet burnups will achieve greater than 20,000 megawatt
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days per metric tor of uranium, SCE shall provide revised analyses using fission gas release models acceptable to the NRC staff.
(7)
_ Low Temperature 0/erpressurization Protection (Section 5.2.2.2, SER)
/
Prior to operation for more than five (5) effective full power years, SCE shall provide a report describing its reexamination of the Technical Specification requirements for steam generator /
reactor coolant system delta temperature and shutdown cooling system initiation tenpe ature linits that are presently provided fcr cversressure p ctection.
The report must either de : strate that the current Technical S;ecificati:n limits are stil' scitanly conservative, or procose and justify revised i
limits.
'5)
'.cle e Cc-trol Tank Centrol Locic (Secticn 7.2.5, SSEE 64) tric c s rtup fol:0,:'r; the 'irst re;jelin; cutace, the volume
- r.:rci tant cutie: valve cen rcl Ic;ic shall be modified to ansure :ta: the valve coes nct change pcsitior, folicwing safet.y ir.jection actuation signal reset.
In the interim, SCE shall raintain er.ercency procede es *. hat requi e the voltet. control tank outle:
valve to be placed in the manuel mode prior to SIAS rese:.
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Com lian:e.cith Peculatorv Guide 1.97 (Section 7.5.1, SER, SSER -5)
Prior to startuo following the first refueling outage, SCE shall c; ply with the reccamendations of Revision 2 to Regulatory Guide 1.97, "Instrurentation for Light-Water-Cooled Nuclear Fower Plants to Assess Plant and Environs Conditions During and Following an* Accident," as descirbed in the SCE letter of "ay 13, 1952.
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6 (10)
Cen:rcl Systen Failures (Secticn 7.7, SER, SSER 54)
By April 1,1983, SCE shall provide an evaluation, for NRC staff review and approval, of contr.1 system failures caused by high energy line break, and by failures of any power sources, sensors, or sens6r irpulse lines which provice power or signals
- o two or more control systems.
Implementation of any corrective
+
action resulting from this evaluation shall be completed on a schedule acceptable to the NRC.
(11)
Diesel Generator Medifications (Section 8.3.1, SER)
Prior to startup following the first refueling outage, SCE shall install a heavy duty turbocharger gear. drive assembly on the emergency diesel generators.
(12)
Fire Protection (Section 9.5.1, SER, SSER #4, SSER #5, Sec1on 1.12, SSER 75) a.
SCE shall c.aintain in effect and fully impienent all provisions of the a: roved Fire Protecticr. Plan as 2 ended through Amer.dment 12 ar.d tre ';P.C staff's Fire Frc sction Review described in the.
SER, Supcle ents 4 and 5 to the SER, and in the Safety Evaluation is:ued.:ith : bis licerse.
In acditior., SCE chall reet the te:r.nical recaircrer:ts of Secti:n III.G, " Fire Protection cf Safe Shu:cown Ca; ability," III.J "Emer;ency Lighting,"
a r.: :I:.0 ":il C: Jie::f:r Iyste-fcr Fea::ce Ccolant Furp" cf A; pen:ix R to IC CFR 50.
b.
?rior to exceeding five (5) percent cower, SCE shall complete' the installaticn of the folicwing items and shall submit a license arencoent recuest to add items 1, 3 and 5 to the
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Technical Specifications (Appendix A to this license).
1.
Provice fire detection in fire zones 11, 28, a5, 62, and 72.
2.
In' stall metal shrouding on the afb' turbine lube oil system.
3.
Install additional sprinklers ~ in the AF',l pusp roon.
4 Previde a 1 1/2 hour fire damper for ene of tne three charging punp rocas.
5.
Provide fire detection and portable extinguishers in the technical support center.
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(13) _ Turbine Disc Inspection (Section 10.2.2, SER)
Prior to startup following the second refueling outage, the bores of the low pressure turbine disc shall be inspected for flaws using ultr'asonic testing.
The results of the inspe: tion shall be submitted to the NRC staff.
(14)
Radioactive Waste System (Section 11.1, SER, SSER #5)
" Wet" solid radraste shall not be shipped frem the facility until the NRC has approved the waste solidification Process (ontrol Program.
(15)
Purce System Monitors (Section 11.3, SER, SSER #5)
Prior to startuo following the first refueling outage, equipment having the capability to-centinuously m:nitor and sanple the containnent purce exhaust directly from the urge stack shall be cperable.
(16)
Initial Test Prc;rar (Section 14, SER)
SCE snali condu:: the post-fuel leading ir.itial test ;rogram (se; for:n in Se: tion 14 of the San Onofre Ur.its 2 and 3 Final Safety Analysis Report, as.arencec,.through A.endesq: 30) without a::i.; a ;.
af er
- ificati:ns to this pr:gra urless sucn
.::ificati:ns nave been iter.tified and nave received prior NEC approval.
Major nodifications are cefined as:
4.
Elirination of any est identified in Section 14.of the Final Safety Anaiysis Report, as amended, as'being essential, b.
Pedificatien of test objectives, methods, or acceptance criteria for any test identified in Section 14 of the Final Safety Analysis Report, as amended, as being essential.
c.
Performance of any test at a power level different than that described in the test procedure.
d.
Failure to ccmplete any tests included in the describec prograr (plannec or seneduled for power levels up to the authorized power level).
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l (47) h.i.EG-0717 Conciticns (Section 22)
Each of the following conditions shall be completed to the satisfaction of the NRC.
Each iten references the related subpart of Section 22 of the SER ar.d/or its supplements.
a.
Precedures for Transients and Accidents (I.C.1, SSER #1, SSER 72, SSER75)
Emercency procedures based on guidelines approved by the NRC shall le implemented prior to startup following the first refueling cutage that occurs six months or more after f.'RC approval of the guidelines.
1 b.
Procedures for Verifying Correct Perfor$ance of Ooerating*
Activities (I.C.o, 55ER #1)
Prior to fuel loading, SCE shall implement a, system. for verifying the correct performance of cperating activities, anc snall keep the system in effect thereafter.
c.
Cor
- R::- Cesier Review (I.D.1. SSER #1)
The ::-trol rco-.::ifica:icns identified as required in SE::i:- 22, Ite-I.D.1 Of Surple ent NO. I to the SER shall be -.stallet ind " Ice creraticnal cn the schedules icen:'"ed for eacr
- dificatic-in Sup:lement Nc. 1 :o
- n e I E O,.
c.
Ocs: *::icer.: Samoline (II.S.2. SSER el, SSER ec. Section 1.12, 55EE -5; Prior :c exceecinc five (5) percent power, the post-ac:iden; sampling system shall be operable anc the post-a:ciden: sanpling prcgran shall be fully implemented.
e.
Direct Ind-ication of Safety Val:.e Position (II.D.3, SSER #1) 4 The safety valve position indication system shall be environmentally and seismically cualified consistent with the ccrp nent or systen to which it is attached, and do:::entation of this shall be caintained.
f.
AFk' Oc-- 4E-hour Er: trance Test (II.E.1.1, SSER #1)
Prior to exceeding five (5) percent power, SCE shall conduct a 4S-hour endurance test of all auxiliary feer ::cr r; rs.
T':
ctults of the test shall be su' 1:'c:
- 0 thi NPC staff.
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g.
Emercency Power Supply for Pressurizer Heaters (II.E.2.1, SSER #1, SSER #5)
SCE shall maintain in effect procedures to preclude the automatic reapplication of pressurizer heaters to Class IE-buses upon SIAS reset.
h.
ICC Instrumentation (II.F.2, SSER 41, SSER #2, SSER #4)
Prior to fuel loading, the following items shall be completed, and shall be naintained therea'fter:
1.
The subcooling monitors shall be modified to include the maximum unheated junction thermocouple temperature and the representative core exit thermocouple input.
2.
Incore detector assemblies (core exit thermocouples and associated cabling) shall be environ 3entally cualified and shall have seisnic and envircr. mentally cualified Class IE connectors.
3.
Qualified cabies snall be. installed fcr the ccre exit thernocouples.
l 4
Tr.e heated functi:n therm : tple or:te and associated
- :ess instru e laticn shall be installed.
Prior to startup foilewing the first refueling outace, the hea ed junction therm couple system and the safety parameter dis;1ay systen shall be operable an: shall be niir.tained operable thereaftr.
l i.
Plent-Soecific Calculations for Co?.Llian:e with 10 CFR Section 50.c6 (11.K..31, SSER #1)
Within one year after model revisions are approved by the NRC, SCE shall provide a supplemental plant-specific analysis to verify compliance with 10 CFR 50.45, using the revised models ceveloped under Item II.K.3.30.
j.
Imoroving Licensee Emergency Prec'aredness (III.h.2, SSER =1. 55ER -5) 1.
By January 1, 1953, the upcraded emercency support facilities shall be operational.
2.
SCE shall maintai,n interin emercency suop:rt
'cci!i::es ('ec.' tical 5 ;ptrt Csmter, ::erations f
t Ccnter 1": the E~2rJ2ncy ?? ira *.:n2 Facility)
J
- '1 Itc c?gr;::: facilities are cc.'iste:.
2.
n.
(IS)
Etercency Presarecness Conditions a.
Conditions of ASLB Initial Decision of May 14, 1922 Sy February 1.7, 1983, SCE shall:
1.
Provide evidence that both ceteorological towers and the Health Physics Computer System are ifully installed and operational.
SCE shall maintain offsite assess-ment and conitoring capabilities, essentially as described in the hearing (see Initial Decision,Section IV, Paragraph D.1-12, pp. 136-140), at no less than that level of readiness, pending develop-cent of satisfactory capability of offsite response Paragraph D.27, pp. 145-146, and Section V, Paragraph B, pp. 213-214).
2.
Provide an assesstent of whether public information regarding erergen:y plannir; sh:uld also be pres'ented in Spanish (see Initial Decision,Section IV, Fara-graph F.32, cc.163, ard Se::icn V, Faragraph C.2 pp. 215).
2.
- rc'. i de ;1ar.s cercr.stratir.;
- P.a SCE a.d offsite Juriscic icns tr.e develepa: and stand ready to in;ieren: a"ra.;crents for e:ical services fer
.er.ners of tre ffsite ;.: ':.
- cu e ta:icr. cf the arranger.ents ar.c provisiens ac.e sFall te ;rovided to ne Atcr.ic f afety and Licensing 5:ard as rel.1 as to the NP.
staff (see Initial Decision, Secticn III, pp. 43
'7, and Section V, Paragraph D, pp. ?l6-217).
4 Provide revised plans demonstratine ina: :ne " extended" Energency Plannine Zone (EP:) cer. cept has been deleted fron tne San Dr.cfre ensite and offsite plais and the Plume Exposure Pathway EPZ boundary has been extended, l
alone with siren coverage, to Dana Point ano all of l
San Juan Capistrano (see Initi,al Decision,Section IV, Faragrapn D.25, pp. 98, anc Section V, Paragraph C.5, pc. 216; see also Order (Making Clarifying Change in Initial Decision) dated May 25,1982).
b.
Ccmcletion of Enercency Preparedness Recuireneats I
l In the event that the NRC finds that the lack of progress in conpletion of the crocedures in the Federal Energency "ar.acement Agency's or: posed ruiss, '4 CFP 250, is an
'.:ic tier tha; a mij:r s;t_.an:ive ;r:::c e> s:s in
.;'iCvi"3 cr ~ai"*.ai"#~g P
N 0 Ite s'.E** :' :"C? ired-
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-(19)
RCS Depressurization System (PORV's)
By June 30, 1983, SCE shall provide a complete response to the NRC letter of March 27, 1982, including information relative to the capability of San Onofre 3 for rapid depressurization and decay heat removel without power operated relief valves (PORVs).
(20) Ovalification of Auxiliary Feedwater (AFW)' Pums Motor Bearinas Prior to exceeding 5% of full power, SCE shall submit a proposed hardware modific.::icn and schedule for implementation that will increase the reliability of the AFU motor-driven pumps in the event of a break in the high energy line feeding the steam-driven pump.
Prior to the installation of a hardware modification acceptable to the NRC staff, SCE shall perform an augmented in-service inspection of the steam line in accordance with SCE's letter of July 12, 1982.,
'21)
Surveillance ?rcerar (Secticn 1.12. SSER A5)
Fri:r c enter nc ary c;eraticcel de for :te first tine, i
inciucir.g ir.i ial fuel leadinc, SCE shall:
E ve c
- le'.e
- a review cf the surveillance procedures a;pli:stle te the chen;e Of m;:e, and cstermined that the pro:e: es cer: I rate the cperability Of :te reevired sy! e 5 itr reI:et: o all a :ertarte criteria c'efine in the Tec aical S;ecificaticns.
b.
Have dissatt ied written certification to the hRC Regicnol A:r':.istrator, Rcgion V, nat the a: ions defined in (1),
above, have been completed for the node er nodes to be entered.
(22)
'uxiliary Builcinc 'ientilation System SCE shall cenplete all codifications to the auxiliary building ver.tilation systen described in the November 5, 1922 letter fren H. Ray, SCE, to R. Encelken, hRC, on the schedule proposed in the November 5, 1982 letter.
C.
Exer;;icns to certain re:uire ents of Apendices G, H and J to 10 CFR Fart 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report.
These exenptions are av:horized by law and will not endanger life or prcperty or the ccnmon defense and security and are otherwise in th! public interest.
Therefore, these eie ::icnt e e hereby crz.ted.
The facility will Operite, to the c.:c: avu.:rized e cv, in i rfc -ity.ci n t*.2 a::lica ica, as
~~.;;,
- .e pT '.i!i:T. I Li.ie 50, an:
I.e "f.c p 2 '.'..E Of the C ; ' '- i S c i : :.
G
- 9 E.
SCE shall maintain in effect and fully implement all provisions of the Commission-approved physical security and guard training and qualification plans, including amendments made pursuant to the authority of 10 CFR Section 50.54(p). The approved plans, which contain 10 CFR 73.21 informatien, are collectively entitled " Physical Security Plan, San Onofre Nuclear Gen ~eration Station, Units 1, 2, and 3,"(which includes the contingency plan as Chapter 8) dated March 9,1981, as revised July 22, 1981, November 30, 1981, December 30, 1981, January 25, 1982, June 30, 1982, and August 18, 1982, including amendments and changes dated December 12, 1979 and August 14, 1981; and the " Guard Training and Oualification Plan, San Onofre Nuclear Generating Station, Units 1, 2, 3" dated August 23, 1979, as revised September 3,1980 and December 15, 1981.
The identificatior of vital areas and measures used to control access to these areat, as described in thi physical security plan, may be subject to arendnents in the future based upon a confirmatory evaluation of the plant to determine those areas where acts of sabotage might cause a release of radionuclides in sufficient cuantities to result in dose rates ecual to or exceeding 10 CFR Part
- D; lir,its.
F.
!*.is license is suDject to tr.e follcaing acciticnal condition for ne prc sctica cf the enviror. rent:
s' crc en;iging in activities that r,ay result in a significant
a:verre envircn. ental ir;act :%a: was no*. evalcated or that is ea:er nan tha; evaluatec in : e Fi.al Environrental ri;nifd car:iv m 5:a:emer.,53E'sta'.1;'oviceawri:er,r.::ift:2:i:- of such a :ivities
- the NRC Office cf Nuclear Peactor Regulation anc receive written a;preval from that office before proceeding with such' activities.
G.
SCE shail recor; any vi.olatier.s of the raysireren's contained in Section 2, Items C.(1), C.(3) throuch C.(22),
E., and F. of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirm'by telegran, railgram, or f acsimile transmission to the NRC Pegional Adminis-r trator, Region V, or his designee, no later than the first working day following the v.iolation, with a written followup report within fourteen (14) days.
H.
SCE shall notify the Commission, as soon as possible but not later than one hour, of any accident at this facility which could result in an unplanned release of quantities of fission products in excess of allowable limits for ncrmal operation established by the Cc=miss' ion.
I.
SCE shall have and maintain financial protection of such type and in such anounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as arended, to cover rublic liability clai s.
J.
! tis lice se is ene::ive as M :o date of ist_r :: anc s!.all es.rire at midnign: On {c Cter
'E, 2013.
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In accordance with the Commission's direction in its Statement of*
Policy, Licensing and Regulatory Policy and Procedures for Environment'al Prot 1ction; Uranium Fuel Cycle Impacts, October 29, 1932, this license is subject to the fina) resolution of the pending litigation involving Table 5-3.
See Natural Resources Defense Council v. NRC, No. 74-15E5 (D.-C. Cir.,' April 27,1962).
FORTHENUCLEARREGULATORY'0MMIS5 ION
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Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:
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Attacf. ment 1 4
2.
Irre dir. (Technical S ecificatier.s) 3.
A:;r; cix E (Enviror.. ental Protectica Plan) 2
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s TO l,'? F-15 Ine following iten must be co.pleted prior to initial criticality:
The :'eficiency ic'entified by the SCE letter, dated July 19, 1982, to R. H. Engelken fron Dr. L.T. Papay regarding discrepant inputs 60 the Core erotection Calculator from Reactor Coolant Pump shaft speed and Control Elenent Assembly position indication shall be corrected.
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