ML19326B914
| ML19326B914 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/07/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19326B911 | List: |
| References | |
| NUDOCS 8004180636 | |
| Download: ML19326B914 (15) | |
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umTro starts NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 APKANSAS NUCLEAR ONE - UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 34 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated January 20, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8004180 [3 [
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-51 is hereby amenced to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 34, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificationf.
3.
This license amendment is ef'ective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
1.
Ot
.f p-I.
Robert W. Peid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the lechnica?
Specifications Date of Issuance:
August 7,1978 l
f
ATTACHMENT TO LICENSE Af1ENDMENT NO. 34 FACILITY OPERATING LICENSE NO. DPR-51
! DOCKET NO. 50-313 Revise Appendix A Technical Specifications as follows:
Remove Pages Insert Panes 11 11 117 117 119-127-119-127 129-134 129 Changes on the revised pages are identified by marginal lines.
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SECTION TITLE PACQ c.
SURVEIL.I.ANCC. TCUISI.fE' TS 67 4.1 OPLTeTiC.AL a.V~.IY 1!i".S 67 4.2 REACOR CDOLx.i SYSTE1 SUT.VEILLt4CC 76 4.3 If ACOR CCOLxiT SYSTIM II.TEGRI1Y FOLLOW!.'iG E:;T3Y 78 4.4 R -TOR SUILDINC 79 4.4.1 Reac;cr Building Lenk:?? Tes:
79 4.4.2 5tru::urst Inte:7 :v SS 4.5 DrcRGE.NC Y CCri CZL':.G SYSTri AND RSACOR BUILDING COOLING SYSTI:t PERIODIC TESTING 92 4.5.1 Energency Core C:oline S.s:e=
92 4.5.2 Rea::: Lu:tctn: C::.;ne 5.s:c-s 95 4.6 AU11L;Aar ELECTRIO.sk 5 57Et T3ST3 100 4.7 REACTOR CONT;0; R00 SYSTI:! TTSTS 102 4.7.1 Centrol Pod Drive Sys ten Functices! Tests 102 4.7.2 Con:rol Roc P:: ::: ver:ites::en 104
4.8 DIERCE6C
Fide.AiLA PCIP IiST1;G 105 4.9 RIACT1VITY AN0!GLIES 106 4.10 CONTROL ROO.1 E.'3RGENCY AIR CONDITICNING SYSTE4 SURVEILLASCE 107 4.1I PENETRAT!ON ROO I VE.NTI!ATICN SYSTEM SURVEILLANCE 109 4.12 KYDROCEN PURC7 SYSTE:1 SURVEILLANCE 109b 4.13 DERGENCY C0 CLING POND 110s 4.14 PADICACIV*.turERIALS SOURCES SURVEILLANCE 1105 4.15 AUC4ENTED INSERVICE INSPECION PROGR.A ! FOR HIGi ENERGY LINES CUTSIOE CF ::.'. TAI OtENT 110e 4.16 SHOCK SUPPRESSORS (SNUBBERS) 110e 4.16.1 Hydraulic Sheek Sue:ressors 110e 4.17 FUEL HANDLINO AREA VE:.TILATICN SYSTE>l SURVEILLANCI 11Lh 4.18 STEAM CTNERATOR TUBING SURVEILLANCE 110j 4.19 FIRE DETECTION INSTRUMENTATION 110p 4.20 FIRE SUPPRESSION WATER SYSTEM 110q 4.21 SPRINKLER SYSTEMS 110t 4.22 CONTROL R00v AND AUXILIARY CONTROL ROOM HALON SYSTD15 110u 4.23 FIRE HOSE $TATIONS 11oy 4.24 PENETRATION FIRE BARRIERS 13 0, S.
DESIGN FEATURES 111 S.1' SITE lil S.2 REACTOR SL'ILDINC 112 l
S.3 REACTOR 114 S.4 NEW AND SPENT FUCL STORAGE FACILITIES 116
' )
6.
ADMINISTRAT!YE CONTROLS 117 6.1
- RES PCN'51a l LITT 117 6.2 ORGANIZATION 117 6.3 FACILITY STAFF QUALIFICATIONS 117 6.4 TRAINING 117 6.5 REVIEW AND AUDIT 117 6.6
. REPORTABLE OCCURRENCE ACTION 126 6.7 SAFETY LIMIT VIOLATION 126 6.5 PROCEDURES 127 0.9 RECORD RETENTION 128 c.10 RADIATION PROTECTION PROGRAM 129 6.11 DELETED 129 6.12 REPORTING REQUIREMENTS 140 d
Anendmerit No. 23, 74, J, N 11
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6.0. AD*l!NISTRATIVC CONTRO!..S 4.1 RESPONSIBILITY 6.1.1 The Plsnt Pbnager shall be resrensible for overall facility operation.
In his absence, the Assistant Plant Manager of Power Plant shs11 assu=c all responsibility and perform all duties of the Plant Manager.
If both the P1snt Manager and his assistant are, absent, these respon-sibilitics and duties are sssuaed by the Optrations Superintendent followed~ by the Technical Support Engineer.
6 ORCAN12ATION OFFSITE 6.2.1 The of fsite organt:at ion for factittv n.ina gemen t and technical support shall be as shown on Figure o.2-1.
FACILITY STAFF 6.2.2 The Facility or;sni:stion shall be ss shown on Figure 6.2-2A and 6.2-2B and each on dut y shift shall be composed of at least the minimum shaft crew escpos t t t on shown in Tsble 6. 2-1.
6.3 FACILITY STAFF QUAlil lCATIONS 6.3.1 Each ne-her of the fa ility stsff.hsil =cet or exceed the minimum qualifiestions of AN51 NIS.1-1971 for cowpsrable position, except for the ficslth Ph> -s es Supervisor who shall meet or exceed the qualifications of Reguistory Guide 1.8, September 19 75.
6.4 TRAIN 1NC 6.4.1 A retritning and replacement training program for the facility staff s.'all be maintained and shall =ect or exceed the requirements and reco:n.cndations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 Ch1 Part 55.
- 6. 4. 2 A training program for fire protection training shall be maintained and shall meet or exceed the requirements of Section 27 of the NFPA Code 1975 with the exception of frequency of t e..ining which th:all be six times per year.
6.5 REVIEh' AND AUDIT 6.5.1
,Pisnt Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Co atttee shall function ts advise the Plant Manager on all mat ters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Conntttee shall be composed of the:
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,,A_mendment No.
34
-121-(EKANSAS POWER 8 LIGHT CO.
ARKANSAS NUCLE AR ONE-UNIT I 6.2 - 2 B
-s 5
Chai rman:
Assistant Plant Manager Member:
Technteal Support Engineer Member:
instrumentation 4 Centrols Supervisor
~,
Member:
Operations Superintendent j
i Hembe r:
Maintenance Superintendent i
Hember:
Nuclear Eng:ncer Member:
!!calth Physics Supervisor The Plant Manager sha!! appoint an acting chair-man in the absence of the Ass tstant Plant Manager.
ALTER. NATES 6.5.1.3 All alternate memcers shall be appointed in writing by the PSC Chairman to serve on a temporary basis; however. no more than two alternates shall participate as vsang members in PSC activities at any one time.
KEETING FREQUENCY I
6.5.1.4 The PSC shall meet at 1 cast once per calendar month and as con-vened by the PSC Chair =an or his designated siternate.
QUORIAt 6.5.1.5 A quorum of the PSC shall consist of the chairman and three meebers including alternates.
RESPONSIBILITICS 6.5.1.6 The Plant Safety Committee shall be responsible for:
a.
Review of 1) all procedures requt red by Specification 6.8 and revisinns thereto, 2) any other proposed procedures or revisions thereto as determined by the Plant Manager to affcet nuclear safety.
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b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the Appendix "A" Tech-c.
nical Specifications.
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d.
Review of all proposed changa)./ '.cdifications to plant systems or oluipment that affect nuclear safety.
Investigation of all violations of the Technical Specificatio,s e.
including the preparation and foraarding of reports covering evaluation _and recommendations to prevent recurrence to the Plant Manager, f.
Review of those Reportable Occurrences requiring 24. hour notification of the Cc==tss ten.
Amendment No jP,3k
- 122 -
es g.
Review of f.acility operations to detect potent t'at nuc1c:tr safety ha:ards.
h.
Perfornance of special reviews and investigations and reports thereon as requested by the Plant Stanager.
l 1.
Review of the Plant Security Plan and impicment tng procedures and shall submit recommended changes to the Plant stanager.
l j.
Review of the Emergency Plan and impicmenting procedures and shall submit recorrended changes to the Plant 5fanager.
Alm!ORITY 6.5.1.7.1 The Plant Safety Coccittee shall:
a.
Recor.:end to the Plant afanager w ri t ten approval or disapproval of items considered under 6.5.1.6(a) throuCh (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(s) through (c) above constitutes an unreviewed safety ruestten.
6.5.1.7.2 In the event of a disagreement between the recoraendations of the Plant Safety Co:::nt ttee and the actions contemplated by the Plant >lanager, the course dete: nined by the Plant Stana-l -
ger to Oc more conservattvc will be followed.
Records or the disagreemen will be sent for revtew to the Director, Generation Operations, or 5 tanager, Nuclear Operations and the Chairman of the Safety Review Committee by the Plant ifanager on the next working day.
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RECORDS 6.5.1.8 The Plant Safety Committee shall maintain written minutes of each meeting and copics shall be provided to the Chairman of the Safety Review Cocaittee by the Plant Stanager.
6.5.2 Safety Review Coe.-ittee (SRC)
FUNCTION 6.5.2.1 The Safety Re.*iew Committee shall function to provide independent review and audit of designated activities in the areas of:
a.
nuc1 car power plant operations b.
nucicar engineering
'c.
chemistry and radiochemistry
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Amendment No. 6,*
123 -
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5 c.
instru.ments son and control f.
radiological safety a
g.
mechanical and electrical engineering h.
environmental considerations
- i. other appropriate fields required by the. unique characteristics of the nuclear power plant COMPOSITION 6.5.2.2 The SRC shall be conposed of the:
Chai rman:. Director,. Generation Operations Member:
Director, Generation Technology Member:
Director, Technica1 6 Environmental Services Member:
Manager of Safety, Arkansa Plant Manager Member:
Planager,s NuhIc.ar Onical Analysis Tec Member:
Member:
Arkansas Nuc1 car One Nuelcar Engineer Mceber:
Director, Generation Engineering Member:
Radiat ion and liestth Phys tes Consultant Member:
Nuclear Safety Consultant In his absence, the Chairman shall appoint an Acting Chairman.
ALTERNATES 6.S.2.3 Ali alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternstes shall participate as voting members in SRC activitics at any one time.
CONSULTANTS
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6.5.2.4 Consultants shall be utili:cd as determined by the SRC Chairman to provide expert advice to the SRC.
NEETING FREQUENCY 6.5.2.5 *The SRC shall meet at 1 cast once per calendar quarter during the initial year of factlity operation following fuct loading and at least once per six months thereaf ter.
QUORUM 6.S.2.6 A quorum of SRC shall consist of the Chairman or his designated alternate and four members in:1uding siternstes. No more than l
a minority of the quaram shall have line responsibility for operation of the factitty.
Amendment No.
, 34
- 124
' REVIEW i
6.5.2.7 The SRC shall review:
a.
The safety evatustions for 1) changes to procedures, equip-ment or systems and 2) tests or expertr:ents completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedurcs, equipment or systems which involve an unrevtewed safety question as. defined in Section 50.59, 10 CFR.
Proposed tests er experiments which involve an unreviewed c.
safety quc>tton as defined in Section 50.59, 10 CFR, d.
Proposed changes in Technical Specifications or licenses.
Vioistions of sp;ilicable statuter., codes, regulations, orders,
c.
Techntest Specifiestions, Iteense requirements, or of internst procedures or instructions having nuclear safety significance.
f.
Significant operating abnomalitics or deviations from nomst and expected perfomance of plar.t equipment that affect nucitar safety.
g.
Reportable occurrences requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Cor::mi s s ion, h.
Reports and meeting sinutes of the PSC.
At!DITS S.S.2.8 Audits of facility activitics shall be perfor:ied under the cogni:ance of the SRC. These audits shall encompass:
a.
The confomance of facility operstion to provisions contained within the Technical Specifications an,d applicabic license condttions at 1 cast once per year.
b.
The perfomance and retraining of all members of the plant management and opet stions staf f. snd the perfomance, training,
and qualifications of new members of the entire plant staff at least once per year.
- c.
The results of all sctions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nucicar safety' at least once per six months.
d.
The Facility Energency Plan and implementing procedures at least once per two years.
The Facility Fire Protection Program and Implementing procedures e.
at least once per 24 months.
Amendment No.
, 31
- 125 -
l
f.
The Fac. aity sceurity Plan and tcp tement
.g procedures at 6
least once per t o years.
g.
Any other arcs of fact!!ty operation considered appropriate by the SRC or the Executive Director Generation & Construction I
(EDC f.C).
l g
6.5.2.9 Special Inspections and Audits A.
An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per 12 months utilizing et,ther qualf fied of fsite licensee personnel or an outside fire protection fim.
AtTTHORITY 6.5.2.10 The SRC shall report to and advise the Executive Director, Generation 5 Construction (FDCf.C) within 30 days following, each meeting.
RECORDS
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6.5.2.11 Records of SRC setivtttes shall be prepared, approved and dis-tributed as indicated below:
Minutes of each SRC meeting shall be prepared, approved and a.
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forwarded to the Executive Director, Generation 5 Construction (EUGT.C)within 30 days' follow'ing es'ch meeting, b.
Reports of reviews encompassed by Section 6.5.2.7 e, f, g and h above, shall be prepared, approved and forwarded to the Executive Director, C*neration S Construction (EDGSC)
Githin 30 days following'*co,pletion of the review.
c.
Audit reports ence passed by Section 6.5.2.8 above, shall be forwarded to the E(ecutivo Director, Generation 5 Construction f
(EDG6C) and to the management positions responsible for the areas audited within 30 days aftgr completion of the.sudit.
6.6 REPORTABLE OCCURRLNCE ACTION 6.6.1 The following actions shall be taken for Reportsbic Occurrences:
The Commission shall be notified and/or a report submitted a.
pursuant to the requirements of Specifiestion 6.12.
b.
Each Reportable Oecurrence requtring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Conntssion sh all be reviewed by the PSC and submitted to the SRC and the Manager ~,. Nuclear Operations by the Plant Manager.
6.7 SAFETY LIMIT V!
'S 6.7.1 The following acttons shall be taken in the event a Safety 1.imit is violated:
a.
The facility shall be placed in at least hot shutdown within one hour.
b.
The Nuclear Reguistory Cor. mission shall be notified and a report sabni: ted pursuant to the requirements of 10 CFR 50.36
' and Specif t estton :.12.3.1
- 126 -
AmendmentNo.p,
,g
s 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and mair,tained covering the activities referenced below; a.
The applicable precedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the Plant Manager
~
prior'to implementation and reviewcu periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered, b.
The change is approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PSC and approved by the ' Plant Manager within 14 days of implemen ation.
l
/
Amendment No. p,
, 34 127 -
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as h,
Records of in-service inspections performed purs ant to these-Technica' l Specifications.
~
i.
Records of Quality Assurance activities required by Section 17 of the Qustity Assurance Pfanust for Operations, j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of coetings of the PSC and the SRC.
~
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radi-ation exposure.
6.11 DELETED Amendment No. k([ 34
- 129 -
(The next page is 140.)
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