ML19296D251
| ML19296D251 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/13/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19296D252 | List: |
| References | |
| NUDOCS 8003030087 | |
| Download: ML19296D251 (35) | |
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0, UNITED STATES
[
i NUCLEAR REGULATORY COMMISSION s,
3 E
WASHINGTON, D. C. 20555 o
s.,
/
TENNESSEE VALLEY AUTHORITY 00CXET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 29, 1979, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Ccmmission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withcut endangering the health and safety of the public, and (ii) tnat such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical. Saec-ifications as indicated in the attachment to this license amendment and paragrach 2.C(2) of Facility License No. OPR-33 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amencment No. 58, are hereby incorporated in the license. The licensee shall ocerate the facility in accordance with tne Tecnnical Specifications.
800303o
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION Thoma
. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changas to the Technical Specifications Date of Issuance:
February 13, 1980 Y
ATTACHMENT TO LICENSE AMENDMENT N0. 58 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
332/333 334/335 T36/37T 2.
The underlined pages are those being changed; marginal lines on these pages indicate the revised area. The overleaf pages are provided fcr convenience.
3.
Add the following new pages:
333A 334A
5.0 hpMINISTRATIVE CANTPCLS
.1 orcanizatien A.
The plant superintendent has en-site responsibility for the safe operation of the f:cility and anall rejort to the Chief, Nuclear Generation Branch.
In the abconce of the plant superintendent., tne assist nt superintendr.et will assume his responsibilitrec.
B.
Tne portion of TVA managenent which relates to the operation of the plant is shown in Figure 6.1-1.
C.
The functional crqanizatien for the operation of the station shall be ac shown in Figurc 6.1-2.
D.
Shif t manning requirements shall, a s a minimum, be as described in section 6.8.
E.
Qualifications of the 3rcuns Ferry Nucica Plant managenent and operating staff shall meet the inimum acceptable levels as described in AN3: - N16.1, Selection and Training cf Nuclear Power Plant Personnel, dated March 8, 1971. The qualifications of the Health Phycies Supervisor. vill meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated Sept. 1975.
F.
Retraining and replacement training of station p?rsonnel shall be in accordance witn ANSI - N13.1, selec. ion and Training of Nuclear Power Plant Personnel, dated March 8,
1971.
The minimum f requency of the retraining program shall be every tuo years.
G.
An Indusirial Security Prograe shall be maintained for the life of ne plant.
H.
Responsibilities of a post-fire everall restoratica coordinator will consist of duties as described in section 6.9.
I I.
The Safety Engineer shall have the following qualifications:
a.
Must have a sound understanding and thorough technical knculedge of safety and fire protection practices, proceoUres, standards, and other codes relating to electrical utility operations. Must be able to read and understand engineering drawings. Must possess an analytical ability for problem solving stid data analysis.
Must be able to comunicata well both orally and in writing and must be able to write investigative reports and prepare written procedures. Mus t ha ve the abi li ty to secure the cocoeration of management, employees and graues in the imold-entatien of safety programs. Must be able to conduct safety presentations for supervisors and. employees.
b.
Should have experience in safety engineering work at this level or have 3 years experienca'in safety and/or Nre protecticn engineering. It is desirable tnat tne incumeent te a graduate of an accredited college or universi ty with a degree in inductrial, recnanical, electrical, or safety engineering or fir?. protection engineering.
Amendment No. 32 332
s l
6.0 ADMINISTRATIVE CONTROLS 6.2 REIVEV AND AUDIT The Manager of Power is respensible for the safe operation of all TVA power plants, including the Browns Ferry Nuclear Plant. The functional organization for Review and Audit is shown in Figure 6.2-1.
Organizational units for the review of f acility operation shall be constituted and have the responsibilities and authorities listed i
below.
A.
NUCLEAR SAFETY REVIEW 30AF3 (NSR3) 1.
FUNCTION The NSR3 shall function to provide independent review and audit of designated activities La the areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radioche=1stry d.
metallurgy instrumentacion and control e.
f.
radiological safety mechanical and electrical engineering g.
h.
quality assurance practices.
2.
CCMPOSITION The NSR3 shall be ec= posed of at least five nembers, including the Chairman. Me=bers of the NSR3 =ay be from the Office of Power or other T7A organizations, or external to T7A.
3.
OUALIFICATIONS The Chair.an, me=bers, and alternate me=bers of the NSR3 shall be appointed in writing by the Manager of Power and shall have an acade=1 degree in engineering or physical science field, or the equivalent; and in addition, shall have a minimum of five years technical experience in one or more areas given in 6.2.A.l.
No more than two alternates sna11 parricipate as voting =e=bers in NSR3 activities at any one time.
333 Amendment No. 58
4 CONSUT TRCS Ccusultants shall be utili:ed as deter =ined by the NSR3 Chair =an to provide expert advice to the NSR3.
5.
!'EETINO FREOUC;CY The NSR3 shall meet at least once per six months.
6.
QUCRUM The dni=um quorum of the NSR3 recessary for the perfor=ance of the NSa3 review and audit functions of these technical specifications shall consist of more than half of the NSE3 me:barship or at least five =e=bers, whichever is greater.
The quorum shall inicude the Chai :an or his appointed alternate and the NSRS = embers including ap;ointed alternate =e=bers eseting the requirements of 6.2. A.3.
No more than a minority of the quorum shall have li:e responsibility for operatien of the unit.
7.
REVIE*J The NSR3 shall review:
The safety evaluations f or C changes to procedures, a.
equipment or systems and 2) tests or experiments completed under the provisi:: cf Section 50.59, 10 CFR, to verify that such acti:ns did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or syste=s which involve an unreviewed saf ety question as defined in Sectica 50.59, 10 C7R.
c.
Proposed tests or exper. rents which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
Violations of codes, regulations, orders. Technical e.
Specifications, license require ents, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnor._alities or deviations from nor=al and expected parfor=ance of unit equip =ent that af f act nuclear saf ety.
233A Amendment No. 58
e 3
All vrittes reports requiring 24-hour notification to the Co==issics.
h.
All recogni:ed indications of an unanticipated deficiency in se e asp:ct of design or operation of structures, syste=s, or co=ponents that could af f ect auclear saf ety.
1.
Reports a:d =eeting minutes of the PCRC.
8.
AUDITS Audits of cai; activities shall be performed under the cognizance of the NS23. These audits shall ence= pass.
a.
The confor:ance of unit operacien to provisions contained within the Technical Specifications and applicable license cc:ditions at least once per 12 =enths.
b.
The perfer ance, training and qualifications of the entire unit s taf f at least once per 12 months.
c.
The reruits of actions taken to correct deficiencies occurring is unit equipment, structures, syste=s or
=ethod of operation that af f ect nuclear safety at least oc:e per 6 :onths.
d.
The perfor:ance of activities required by the Operational Qcalic-Assurance Program to =eet the criteria of Appendix "I",10 CFR 50, at least once per 24 =ener,
e.
The Site Radiological E=ergency Plan and i=plementing proced:res at least once per 24 =enths.
f.
The ?last ?hysical Security Plan and 1 plementing procedures at least once per 24 =enths.
g.
A:y other area of unit operation considered appropriate by the 55R3 or the Manager of Power.
h.
The Ta:ility Fi:n Protection Program and i=ple=enting procec2res at least once per 24 =enths.
1.
An isdapendent fire protection and loss prevention prog ss inspection and audit shall be perfer:ed annually utili:ing either qualified off site licensee personnel or as cutJide fire protection firm.
j.
A: ins;e: tion and audit of the fire protection and loss preve:ti:: progra= shall be perfor=ed by an outside qualified fire t::su tant at tr.tervals no greater than 3 years.
33' Amendment No. 58
6.0 ADMINISTRATIVE CCSr01.5-B.
Plant Operations Aeviaw Committee f 7C RC) 1.
Mem ber s hip The PORC shall censist of the plant superintendent, assistant plant suoerin t endent, electric =2intenance superiisor, =echanical maintenance superiisor, instrument =aintenance superiisor, health physics supervisor, operations supervisor, results supervisor, and QA staf f supervisor. An assistant plant superiisor may serve as an alternate cocmittee nember when his supervisor is absent.
The plant superintendent will serve as chairman of the PORC.
The assistant plant superintendent will serve as chair: nan in the absence of the plant super in t endent.
Meetina Frequency The PORC snall meet at regular -ionthly interials and for special meetings as called by the chairman or as raquested by individual memoers.
3.
Ouorum Superint andent or assistant su p e. in t end ent, plus lwillconstituteaquorum.
five of the seven other members, er their alternate, A memner will be considered present it he is in telephone communication with th f conuni tt e e.
335 Amendment No. 58
k.
The radiological environmental =enitoring program and the results thereof at least once per 12 =enths.
1.
The performance of activities required by the Quality Assurance Program to =eet the criteria of Regulatory Guide 4.15, Dece=ber 1977 at least once per 12 months.
9.
AUTHORITY The NSR3 shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2.A.7 and 6.2.A.8.
10.
RECORDS Records of NSR3 activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSR3 =eeting shall be prepared, approved and forwarded to the Manager of Power within 14 days f olicwing each meeting.
b.
Reports of reviews enco= passed by Section 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power within 14 days following completion of the review.
c.
Audit reports ence= passed by Section 6.2.A.8 above, shall be forwarded to the Manager of Power and to the =anagement positions responsible for the areas audited within 30 days after completion of the audit.
334A Amendment No.
58
6.0 ADMIrlISTRATIVE cot TKL3 3-22LiC2 1Gl_3fRL20WikklilirW Tb-a nn: i.- r v s in an advi sory c ipaci t y to th++
plant s u p e r i nt e nd e n t and.iu an a nveu t tgati ng and reportino body to the Nuclear Safety Peview Boaci in matters related to saf ety in plant operations.
Tne plant superintendent has the final responsicility in determining the matters that should be referred to the Nuclear Saf ety Review Board.
The responsibility of tne committee will include:
a.
Review all standard and emergency operating and maintenance instructions and any proposed revisions thereto, with principal attention to provisions for safe operation, b.
Feview porposed changes to the Technical Specifications.
c.
Feview croposed changes to equipment or systems having sa f ety sig nif icance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.59.
d.
Investiaate reported or suspected incidents involving safety questions, violations of the Technical Specifications, and violaticns of plant instructions pertinent to nuclear safety.
e.
ceview renortable occurrences. unusual events, 0;:erating anomalies and abnor,al cerfor-ance of 31 ant ecuicment.
f.
Maintain a general surveillance of plant activities to identif y possible saf ety hazards.
g.
Review plans for special fuel handling, plant maintenance, operations, and tests or experiements which may involve special saf ety considerations, and the results thereci, wnere applicaole.
h.
9eview adequacy of quality assurance procram and recommend any appropriate changes.
1.
Review i.?pleme n t ating procedures of tne Radiological Emergency Plan and the Industrial Security Procram on an annual basis.
336
6.0 A. D 9.1.n 5?,vATT Vr CO NT90LS a
rograms
).
Rev;ew 4d equa cy of employee trainina e and recommend change.
5.
Autneriev The PORC shg11 be advisory t0
- t. e pl&.tt superintendent.
6.
Records Minutes snall be rept for all PCFC meeting s with copies sent to Director, Power Production. Chief, Nuclear Generation Branen; Chaarman, NSR3.
7 Procedures written admtnistrative procedures f or comm: tee opera:Lon snall be prepared and maan*a.ned descr:oang :ne metnod for sa: assion and :en t en t of presentations to the committee, rev;ew and approval ey memsers of committee act;on s, dissemination of manutes, agenda and seneduling of meetings.
C.
237 Amendment No. 58
I y
o, UNITED STATES y j *y(3 i
NUCLEAR REGULATORY COf ullSSION
.E WASHINGTON, D. C. 20555 5(%H.
j
%.w.... j TENNESSEE VALLEY AUTHORITY DOCXET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Ccemission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 29, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will ocerate in confomity with the application,-
the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amencment can be concucted withcut endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and s
E.
The issuance of this amendment is in accordance witn 10 CFR Part 51 of the Commission's regulations and all soplicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-52 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Soecifications contained in Appendices A and 3, as revised through Amencment No. 53, are herecy incorporatec in the license. The licensee shall coerate the facility in accordance with the Technical Specifications.
2 3.
This license amendraent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n
4 Thomas A./'Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 13, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
333/334 335/336 T57/338 2.
The underlined pages are those being changed; marginal lines on these pages indicate the revised area. The overleaf pages are provided for convenience.
3.
Add the following new pages:
333A 334A
6.0 ADMINISTMTIVE CONTROLS 6.1 REIVFJ AND AQIT The Manager of ?over is responsible for the safe operation of all TVA power plants, including the 3rowns Ferry Nuclear Plant. The functienal organi:ation for Review and Audit is shown in Figure 6.2-1.
Organi:ational units for the review or' facility operation shall be constituted and have the responsibilities and authorities listed below.
A.
NUCLEAR SAFETY REVIr4 BOAD (NSR3) 1.
FUNCTION The NSR3 shall function to provide independent review and audit of designa:ed activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistri d.
netallurgy icstrumentation and control e.
f.
radiological safe:y nechanical and electrical engineering g.
h.
quality assurance prac: ices.
2.
COM?CSITION The SSR3 shall be conposed of at leas: five nesbers, including the Chairnan. Menbers of the NSRB nay be from the Office of Power or other TVA organi:aticus, or external to 77A.
3.
CUALIFICATIONS The Chair an, nenbers, and alternate nenbers of the SSRB shall be appoin:ed in writing by the Manager of Power and shall have an acadenic degree in engineering or physical science field, er :he equivalent; and in addition, shall have a =inimum of five years technical experience in one or more areas given in 6.2.A.l.
No more thar. two alternates shall par:1:1pate as voting me=bers in NSRL activities at any one tina.
333 Amendment No. 53
All written reports requiring 24-hour notification to the g.
Co==1ssion.
h.
All recogni:ed indications of an unanticipated deficzency in some aspect of design or operation of structures, syste=s, or co=ponents that could aff ect nuclear safety.
i.
Reports and meeting minutes of the ? ORC.
8.
AUDITS Audits of unit activities shall be perfor=ed under the cognizance of the NSR3. These audits shall enco: pass.
The confor=ance of unit operation to provisions contained a.
within the Technical Specifications and applicable license conditions at least once per 12 =enths.
The perf or=ance, training and qualifications of the entire b.
unit staff at least once per 12 =enths.
The results of actions taken to correct deficiencies c.
occurring in unit equip =ent, structures, syste=s or method of operation that af fect nuclear safety at least once per 6 =onths.
d.
The perfor=ance of activities required by the Operational Quality Assurance Progra= to meet the criteria of Appendix "3",10 CFR 50, at least once per 24 monti...
The Site Radiological E=ergency Plan and i=ple=enting e.
procedures at least once per 24 =onths.
f.
The Plant Physical Security Plan and i=ple=enting procedures at least once per 24 months.
Any other area of unit operation considered appropriate g.
by the NSR3 or the Manager of Power.
h.
The Facility Fire Protection Progra= and i=ple=enting procedures at least once per 24 =enths.
1.
An independent fire protection and loss prevention progra= inspection and audit shall be performed annually utili:ing either qualified off site licensee personnel or an outside fire protection Oir=.
An inspection and audit of the fire protection and loss j.
prevention program shall be performed by an outside qualified
~
fire consultant at t:tervals no greater than 3 years.
l 334 Amendment No.
53
4 CONSULTANTS Consultants shall be utili:ed as determined by the NSR3 Chairman to provide expert advice to the NSR3.
5.
MEETING FREOUENCY The NSRB shall meet at least once per six :onths.
6.
QUORUM The minimun quorum of the NSR3 necessary for the performance of the NSR3 review and audit functions of these technical specificati:ns shall consist of = ore than half of the NSK3
=e=bership or at least five members, whichever is greater.
The quorum shall inicude the Chairman or his appointed alternate and the NSR3 =e:bers including appointed alternate =e=bers meeting the require =ents of 6.2.A.3.
No more than a =inority of the quorum shr.1 have line responsibility for operation of the unit.
7.
REVIEW The NSR3 shall review:
a.
The safety evaluations for 1) changes to procedures, equipment or syste=s and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an onreviewed safety question.
b.
Proposed changes to procedures, equip =ent or systems which involve an unreviewed safety question as defined in Section 30.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License, e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected perfor:ance of unit equipment that affect nuclear safeer.
333A Amendment No. 53
k.
The radiological environmental =enitoring progras and the results thereof at least once per 12 conths, f
1.
The performance of activities required by :he Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, Dece=ber 1977 at least once per 12 onths.
9.
AUTHORITY The NSR3 shall report to and advise the Manager of Power on those l
areas of responsibility specified in Sections 6.2. A.7 and j
6.2.A.S.
10.
RECOROS Records of NSR3 activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Manager of Power within 14 days following each eeting.
b.
Reports of reviews encompassed by See:1or. 6.2.A.7 above, shall be prepared, approved and forwarded to the Manager of Power s/1:hin 14 days following completion of the review.
c.
Audit resorts enecepassed by Section 6.2.A.3 above, shall be forwarded to the Manager of Power and to the canagenent positions responsible for the areas audited within 30 days 6
after ccepletion of the audit.
334A Amendment No. 53
6.0.cMI!:ISTRATI'T! CO!;TROI.S B.
Plant Ooeritions Review Committee (PORC1 1.
Membarship The ? CRC shall censist of the plant superintendent, assistant plant su erintendent, electri: =aintenance supervisor, nechanical =aintenance superiisor, instru=en: =aintenance supervisor, health physics superiisor, operations superiisor, results superiisor, and QA staff supervisor. An assistant plant superiisor may ser te as an alternace co=:sittee nesber when his superiisor is absen:.
The plant superintendent will serve as chair. an of m
the PORC.
The assistant plant superintendent will serve as chairman in the absence of the plant sup er in t endent.
Meetine Frequency The PORC shall meet at requiar monthly intervals and for special meetings as called by the chairman or as requested by individual members.
J.
cuorun Superintendent or assistant supe.intendent, plus ffiveof:hesevenotherme=bers,ertheiral:ernate, will constitute a quorum. A memner will be considered present 1: he is in telephone communication with tne ecmmittee.
335 Amendment No. 53
6.4 A DM I N I ST P AT I'/ F re s t.T P U L:.
'd -
L"J L i'; '.'.10 ! _. 922 L'..".! 21 ! k 1111 '.'!.!
t T t +- n on.
i.
v-s in du.idvi sot y capaci t y t o th'*
plant superintendent and au an in v es t ig a t i ng and reporting body to the Nuclear Safety Review Board in m at e. r. r >1 ate i to n.if s ey in plant opr ations.
The plint suportn!cndent has the final r e s pon c i r.111 t y in determining the matters that should te referred to the Nuclear Saf ety Review Boar 1.
The r - ;pi,o o t t t 1 a t y o t tin. t'onim i t r e.- wil1 include:
a.
R av t. w il l at sodsri and <mergency op-ratinq
.uid in. i t u t ' ni n c e-
' n t tr uction s anil any proposed r-2v i a tons th:reto, with prir.cipal at tention to gravtstanc :or sat: OE,eration.
D.
Feview porposed changes t o the Technical Specifications.
c.
Feview pecpoced changes to equipment or s y s t e:ns hsving safety siq rti f t cance, or which m sy constitute
".in uru.ev iewod sa f et y question," purs>uant to 10 CFR 5 0. 5 ').
d.
Invest aate reported cr suspected incidents involving safety questions, violations of the Technical Specifications, and violaticns of plant inctructions pertinent to nuclear natety.
e-u.. / i. w r.mo r t a b l e - ni i o r r..'n.e s. anusual events, operar.ino anomalie; and abnormai rerform<toce of clant acu i cmen *. -
f.
Maintain o general surveillance of plant activities to identif y possible saf ety h a:: a r d s,
g.
Revier plans for special fuel ha n dling, plant maintenance, operations, and tests or experiements wnich may invc lve special saf ety considerations, and the res uits thereof, wnere applicable.
h.
Peview adequacy c f quality assurance program and recommend any apt.ropriz,te changes.
1.
Review i.Tplementattna procedures of the Radiological Eme rgency Plan and the Indus t r:.a1 Security Procram on an annual basis.
336
6.0 q.1Qa tggATIV5 Crat.iaC:,:3 j.
Revtew ed equa cy of empicyee ::aaning pecq ams and reco. mend enange.
5.
_Au t no r : t v Che PCRC sn.LL be advisory to the plant supertn:endent.
6.
Recerds Minutes snali ce kept tot all POPC meta tng s w;:n copies sent to Otrector, Power Produe:1:n ; Chief, Nuclear Generatten Br anen; Cnaarman, N S ?3.
7.
Procedures Written administrative procedures f: committee sperata:n shall ce prepared and m.ainta:ned descr :;ng sne method for su: mission and centent of presentations to :ne ecm.,;; tee, revtew and approval
- y memcers of committee ac:Lons, dissem natten of minutes, agenda and seneduling of meetings.
C.
337
/vnendmant No. 53
6.0 ADMI!f f STRATIVE CONTROLS
- 6. 3 Procedures A.
Detailed written procedures, i ncluding applicable check-of f li sts covering items lis rd below shall be prepared, approved and adhered to.
1.
Normal startup, operation and shutdown of the reactor and of all systems and components involving nuclear saf ety of the f acility.
2.
Refueling operations.
3.
Actions to be taken to correct specific and foreseen potential calf unctions of syst ems or com ponen ts, including responses to alarmo, suspected primary system leaks and abnormal reactivity changes.
4 Emergency conditions involving potential or actual release of Radioactivity.
5.
Preventive or corrective maintemince opera tions which could have an ef f ect on the saf ety of the reactor.
6.
Surveillance and testing requirements.
7.
Radiation centrol procedures.
8.
Radiological Energency Plan implementing procedures.
9.
Plant security program implementing procedures.
10.
Fire protection and prevention procedures.
B.
Written procedures pertaining to those items listed above shall be reviewed by pORC and approved by the plant superint endent prior to implementation.
Temporary changes to a procedures which do not change the intent of the approved procedure may be made by a member of the plant staf f knowledgeable in the area af f ected by the procedure except that temporary changes to those itema listed above e xcept i tem 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on t he u ni t aff ected.
Such changes shall be documented and subsequently reviewed by PORC and approved by the plant superint end ent.
338
[ " %
UNITED STATES yqs
^\\
NUCLEAR REGULATORY COMMISSION j.f fI g WASHINGTON, D. C. 20555
- ? ? Nv f 5 g.... f TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMENOMENT TO FACILITY OPEPATING LICENSE Amendment No. 31 License No. OPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 29, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the acplication, the provisions of the Act, and the rules and regulations of the Ccmmission; C.
There is reasonable assurance (i) that the activities authorized by this amencment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be concuctec in cm;liance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amencment is in accordanc6 with 10 CFR Part 51 of the Commission's regulations and all a:clicable requirements have been satisfied.
2.
Accorcingly, the license is amended by changes to the Technical Spec-ifications as incica:ed in the attachment to this license amendment and caragraph 2.C(2) of Facility License No. DPR-68 is hereby amended to read as fellcws:
(2) Technical S:eci#ications The Technical Scecifications contained in Appendices A and B, as revised tnrough Amendment No. 31, are herecy incorporated in the license. The licensee snall ocerate the facility in accordance witn the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[
9-Thomas'. Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: February 13, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
13 57 362A*
363 364 365 367 2.
Marginal lines indicate revised area.
- The change on page 362A is to move, verbatim, the first two paragraphs of Section 6.2 from page 362A to the top of page 363.
3.
Add the following new pages.-
463A 364A
SAFCTY LIMIT LIMITING san
- TEM 87:TTI NG 1.1 FUEL CLADDING INTEGRITY 2.1 FUEL CLADDING INTEGRITY C.
Whenever the reactor is in C.
Scram and isola-2 538 in.
the shutdown condition tion reactor above with irradiated f uel in low water vessel the reactor vessel, the level zero water level shall not be less than 17.7 in, above D.
Sc ra m--turbin e 5 10 per-the top of the normal stop valve cent valve closure closure active fuel zone.
E.
Sc ra m--turbine control valve 1.
Fast clo sur e--U pon trip of the fast acting solenoid valves 2.
Loss of con-2 1,100 psig trol oil pressure F.
Scram--Ic
- on-2 23 inches denser vt. Jam Hg vacuus G.
Scra m--m :
5 10 per-steam li.
cent valve isolation closure H.
Main steam isola-s 825 psig tion valve closure
--nuclear system low pressure I.
Core spray and 2 378 in.
LPCI actuation--
above reactor low water vessel level zero J.
actuation--reac-aDove tor low water vessel level zero K.
Main steam isola-2 470 in.
tion valve above closure--r eactor vessel low water level zero 13 knen fment tio.
31
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35:A hendment No, 37
6.0 ACMINISUATIVE CON'"ROLS 6.2 REIVr4 AND AUDIT The Manager of Power is responsible for the safe operation of all TVA power plants, including the Browns Ferry Nuclear Plant. The functional organization for Review and Audit is shown in Figure 6.2-1.
Orgaaizational units for the review of f acility operation shall be constituted and have the responsibilities and authorities listed below.
A.
N1'CLT.AR SATITY REVII'4 SCA.C (NSP3) 1.
F'JNCTICN The NSRB shall function to provide independent review and audit of designated activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineericg c.
chemistry and radiochemistry d.
metallurgy instrumentation and control e.
f.
radiological safety
- ochanical and electrical engineering g.
h.
quality assurance practices.
2.
CttPCSITION The NSR3 shall be composed of at least five = embers, including the Chair:an. Me=cers of the NSR3 may be f rom the Office of Power or other TVA orgsnizaticus, or external to TVA.
3.
OUALIFICATICNS The Chairmar., ne=bers, and alternate members of the NSRS shall be appointed in writing by the Manager of Power and shall have an academic degree in engineering or physical science field, or the equivalent; and in addition, shall have a mini =um of five years technical experience in one or more areas given in 6.2.A.1.
No more than two alternates shall participate as voting me=bers in NSRI activities at any one ti=e.
363 Amendment tio. 31
4 CCNSULTANTS Consultants shall be utili:ed as deter =ined by ths NSR3 Chairman to provide expert advice to the NSR3.
5.
MEETINC. FRECUE' ICY The NSR3 shall =eet at least once per six =enths.
6.
OUORUM The mini =u: quorus of the NSR3 necessary for the perfor=ance of the NSR3 review and audit functions of these technical specifications shall consist of ore than half of the NSR3
=e=bership or at least five =e=bers, whichever is greater.
shall inicude the Chairsan or his appointed alternate The quoru:
and the NSR3 =e=bers including appointed alternate me=bers
=eeting the require =ents of 6.2.A.3.
No = ore than a minority of the quorum shall have line responsibility for operation of the unit.
7.
REVIEW The NSR3 shall review:
The safety evaluations for 1) changes to procedures, a.
equip =ent or syste=s and 2; tests or experi=ents ce=pleted under the provision of Section 50.59: 10 CFR, to verify that such actic=s did not constitute an rareviewed safety question.
b.
Proposed changes to procedures, eculp=ent or syste=s which involve an unreviewed safety questien as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety questien as defined in Sectica 50.59, 10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
Violations of codes, regulations, orders, Technical e.
Specifications, license require =ents, or of Laternal procedures or instructions having nuclese safety significanc4.
f.
Significant operating abnor=alities or deviations from nor=al and expected perf or=ance of unit equip =ent that affect nuclear safety.
Amendment No. 31 363A
All written reports requiring 24-hour notification to the g.
Co==ission.
All recognized indications of an unanticipated deficiency h.
in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
1.
Reports and =eeting minutes of the P0RC.
8.
AUDITS Audits of unit activities shall be performed under the cognizance of the NSR3. These audits shall encompass.
The conformance of unit operation to provisions centained a.
within the Technical Specifications and applicable license conditions at least once per 12 months.
The perf ormance, training and qualifications of the entire b.
unit staff at least once per 12 months.
The results of actions taken to correct deficiencies c.
occurring in unit equipcent, structures, systeca or method of operation that af f ect nuclear saf ety at least once per 6 =onths, The performance of activities required by the Operational d.
the criteria of Quality Assurance Progras to =eet Appendix "B", 10 CFR 50, at least once per 24 ontha.
Tc s Site Radiological E=ergency Plan and i=plementing e.
pr.cedures at least once per 24 months.
f.
The riant Physical Security Plan and i=ple=enting procedures at least once per 24 =enths.
Any other area of unit operation considered appropriate g.
by the NSR3 or the M.anager of Power.
h.
The Facility Fire Protection Program sud i=plementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention progran inspection and audic shall be perfor ed annually utiliting either qualified offsite licensee personnel or an outside f1re protection firm.
An inspection and audit of the fire protection and loss j.
prevention program shall be performed by an outside qualified l
fire consultant at intervals no greater than 3 years.
364 Amendment No. 31
k.
The radiological environmental onitoring prt tram and the results thereof at least once per 12 months.
1.
The performance of activities required by the Quality Assurance Program to meet the c-iteria of Regulatory Guide 4.15, December 1977 at leas: once per 12 months.
9.
AUTHCRITY The NSR3 shall report to and advise the Manager of Power on those areas of responsibility specified in Sections 6.2. A.7 and 6.2.A.8.
10.
RECORDS Records of NSR3 activities shall be. prepared, approved and distributed as indicated below:
a.
Minu:es of each NSR3 meeting shall be prepared, approved and f orwarded :o the Manager of Power within 14 days following each =eeting.
b.
Reports of reviews encompassed by See:1on 6.2. A. 7 above, shall be prepared, approved and f orwarded to the Manager of Power within 14 days following completion of the review.
c.
Audi: reports encompassed by Sec:1on 6.2.A.8 above, shall be f orwarded to the Manager of Power and :o the =anagement positions responsible for the areas audited within 10 days af:e completion of the audit.
364A Amendment No. 31
6.0.GMINISTRATIVE CON 17.OI.S B.
Plant Ceerstions Reviaw Ccmmittee (PORC) 1.
Membershio ne FORC shall censist of the plant superintendent, assistant plant suoerintendent, electric =aintenance super-risor, mechanical =aintenance supervisor, instru=ent naintenance supervisce, health physics supervisor, operations supervisor, resulta su ertiser, and QA staf f supervisor. An assistant plant supervisor may serve a an alternate corr..ittee me=ber when his supervisor is absent.
The plant superlatendent will serve as chairman of the PORC.
The assistant plant superintendent will serve as chairman in the absence of the plant superintendent.
2.
Meetine Frecuency The PORC shall meet at requiar monthly intervals and for special meetings as called by the chairman or as requested by individual members.
3.
Ouorum superintendent or assistant superintendent, plus l five of the seven other nembers, or their alternate, will constitute a quorum.
A member will be considered present if he is in telephone communication with the ccmaittee.
365 Amendnent No. 3i
6.0 A DM I N T ';ThATI V5_C97R C.5 i.
Review adequacy of employee training programs and roccamend change.
5.
Authority The PORC snall be advisory to the plant superintendent.
6.
Fecords Minutes shall be kept f or all PCFC meetings with copies sent to Director, Power Production ; Chief, Nuclear Generation Stanch; Ch airma n, NSRS.
7 Procedures Written administrative procedures for committee operation shall be prepared and maintained descricing the method for sucmission and content of presentations to the committee, review and approval by members of committee actions, dissemination of minutes, agenda and seneduling of meetings.
C.
U-Amendtnent No.
31 367