ML20039B376
| ML20039B376 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Palo Verde  |
| Issue date: | 12/02/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039B377 | List: |
| References | |
| NUDOCS 8112220604 | |
| Download: ML20039B376 (42) | |
Text
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' 8' o
UNITED STATES
~,,
8 NUCLEAR REGULATORY COMMISSION o
E wAssiscTON. D. C. 20555
/
TENNESSEE VALLEY AUTHORI'TY DOCKET N0. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments by Tennessee Valley Authority, (the licensee) dated May 15, 1981, as supplemented by letter dated July 13, 1981 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 applicatioi1[.
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 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the ccamon defense and security or to the health an'd 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. Spec-ifications as indicated in the attachment to this 1icense amendment and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:
(2) Technical'Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
8112220604 811202 PDR ADOCK 05000529
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_A 3.
This license amendment is effective as of the date of its issuance.
a FOR THE NUCLEAR REGULATORY COMMISSION I
A N
Thomas A.
ppolito, Chief Opt ' ting Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications 9
Date of Issuance:
December 2, 19.81
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 79 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259-Revise Appendix A as follows:
~
1.
Replace the following pages with the identically numbered pages:
'332-335 336-337 346-358
'359 361 362
~
363 364 Marginal lines on the above pages indicate the areas being revised.
2.
The overleaf pages are not being revisad and should be retained.
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8 S
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De
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4.0 ADMINISTftATIve co.:Titet.S i
aA ne_ifn i
t 6.1 The plant superintendent has on-site responsibilities for A.
to the Assistant the safe operation of the facility and shall report Director of Nuclear Power (Operations). In the absence of the plant superintendent, an assistant superintendent will assu:ne his remnnnaihilities.
The portion of TVA manacement which relates to the is shown in Figure 6.1-1.
B.
operation of the plant The functional organ'ization for the operation of the starion shall be as shown in Figure 6.1-2.
C.
shift manning requirements shall, as a minimum, be as,
D.
described in section 6.8.
Qualifications of the Brcwns Ferry Nuclear Plantmanageme E.
acceptable levels as described in AUSI - N18.1,Personnel, selection and Training of Nuclear Power Plant 1971. The qualifications of th
. dated March 8, Supervisor will meet or exceed the mininu:s acceptable Retraining and replacement training of station personnel Selection and shall te in accordance with ANSI - N18.1, F.
Training of Nuclear Power Plant Persennel, dated March The minimum frequency of the retraining 2-8, 1971.
program shall be every two years.
An Industrial Security Program shall be maintiined for C.
the life of the plant.
The Safety Engineer shall have the felicwing qualifications:
H.
Must have a sound understanding and thorough technical knowledge of safety and fire protection practices, a.
procedures, standards, and other ccdes relating toMust be.able to read electrical utility operations.
Must possess an and understand engineering drawings.
analytical ability for problem solving'and data analysis.
Must be able to comunicate well both orally and in writing and rust be able to write investigative raports Must nave the ability and prepare written procedures.
to secure the cocoeration of ranagement, employees and Must groups in the implemantation of sa fety programs.
be able to conduct safety presentations for supervisors and eeployees.
b.. Should have ex:erience in safety engineering work at this level or have 3 years esperience in safety and/or fire It is desirable that the protectiun engine:: ring.incuccent be a graduate of an accredited college university with a degree in inductrial, hecnanical, electrica.1, or safety _ engineering or fire protection engineering.
.332 b
Amendment No. [79
t 6.n N dtNITTRt.TIVC CONTROLS 4
f E.
Plant Operations Review Comeittee f PORE 1.
Membership The PORC shall consist of the plant superintendent, or his representative, electric maintenance section supervisor; mechanical maintenance section supervisor, instrument maintenance section supervisor, health physics supervisor, operations sectT6n supervisor, engineering section supervisor, and quality assurance supervisor. An assistant plant supervisor may serve as an alternate cocsittee memeber when his supervisor is absent.
The plant superintendent will serve as chairman of l
t he PORc. His representative will serve as chairman in the absence of the plant superintendent.
2.
Meetine F eeueng
~
The p0RC shall meet at regular monthly intervals anc for special meetings as called by the chairman or as requested by individual members.
3.
Quorum l
Superintendent or his representative, plus five of the seven other member.', or their alternate, will constitute a quorum. A member will be censidered present if he is in telephone communication with the committee.
335 Amendment. No. g, 79
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6.0 ogniu]STRATIVE CONTROLS s
E.
RMtiE401.82RE2!1Mikil.1112M The POHC serveu in an advisory capacity to the plant superintendent and as an investigating and reporting body to the Nuclear Safety Review Board in matters related to safety in plant operations.
The plant superintendent han the final responsibility in determining the matters that should be referred to the Nuclear Safety Review Board.
The responsibility of the committee will include:
a.
Review all standard and emergency operating and maintenance instructions and any proposed revisions ther,eto, with principal attention to provisions for saf e operation.
b.
Review proposed changes to the Technical Specifications.
c.
Review proposed changes to equipment or systems having safety significance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.SS.
d.
Investigate reported or suspected incidents involving saf ety questions, violations of the Technical Specifications, and violaticns of plant instructions pertinent to nuclear safety.
e.
Review reportable occurences, unusual events, operating anomalies and abnormal perf ormance of plant equipment.
f.
Maintain a general surveillance of plant activities to identify possible safety 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 thereof, where applicable.
h.
Review adequacy of quality assurance program and recommend any appropriate changes.
i.
Review implementating procedures of the Radiological Emergency. Plan and the Industrial Security Program on an annual basis.
336 i
Amendment No. 79
A
'.9 ets*I" W M HyS_VUf7E M e
i.
w.'v iet w.silequacy of employee training programs
.a nr*. tecommend Change.
5 Authority Tne FORC shall be advisory to the plant superintendent.',
6.
Records Minutes shall be kept for all PORC meetings with copies sent to Director, Nuclear Power; Assistant Director of Nuclear Power (Operationsl; Chairman, NSRB 7
Procedures Written administrative procedures for committee 1
operation snall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of committee actions, dissemination of acenda and scheduling of metings.
- minutes, c~
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337 Amendment No. % 79
es
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a,. O AD.11 N E; fu,TI VLLJ t;T1* OLS of a Reportabic Occurrence Actions to be Taicen in the Event 6.4 in P1 ant cueration (Ref. Section 6.71_
Any reportable occurrence shall be promptly reported to A.
the Assistant Director, Nuclear Power' (Operations) and shall beThis committee shall prepare promptly reviewed by PORC.
This a sepa rate report 'f or each reportable. occurrence. include an evaluation of th report shall occurrence and recommendations for appropriate action to 7
or reduce the probability of a repetition of the prevent occu r r ence.
Copies of all such reports shall be submitted to the Assistant Director, Nuclear Power (Operations), the Manager of Power, B.
and tne Chairman of the NSRB for their review.'
The plant superintendent shall notify the NRC as specified in specification.6.7 of the circumstances of C.
any reportable occurrence.
6.5 Action to ba___T a k e n in the Event a sa f etv Limit is Exceeded If a sa f ety limit is exceeded, the reactor shall be shut down be resumed until authorized and reactor operation shall not by the flRC.
A pro.npt report shall, be t-ade to t he Assistant Director, Nuclear Power (Operations), and the Chairman of the NSRS.
A co. plete analysis of the circumstances Icading up to anuwith recommendations together This resulting from the situation,shall be prepared by the PORC.
to prevent a recurrence, report shall be submitted to the Assistant Director, Nuclear Power (Operations),
l the Manager of Power, Notification of such occurrences and the NGRB.
will be made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G.6 Station op_cratipq hcords in a manner convenient Records and/or logs shall be kept A.
for review as indicated below:
1.
All normal plant oteration including such items r
power level, fuel ex'posure, and r.hutdowns 2.
Princi. pal maintenance activities 3.
Pc;criable occurrences 146 Amendment No. 79 O
6.O htt<!ILS '!Tt^.U.VI GWHE%s i
e 6.3 Mi ni mu m Plant Staffing The minimum plant staffing for monitoring and conduct of operations is as f ollows.
1.
A licensed senior operator shall be present at the site at all times when:there is fuel in the reactor.
- 2. -
A licens== operator shall be in the control room whenever there is fuel in the reactor.
3.
A licensed senior operator shall be in direct charge of a reactor refueling operation; i.e., able to devote full time to the refueling operation.
' A health physics technician shall be present at the 4
facility at all times there is fuel in the reactor.
5.
Two licensed operators shall be in the. control room during-any cold startups, while shutting down the reactor, and during recovery from unit trip.
l 6.
Either the plant superintendent or an assistant plint superintendent shall have acquired the experience and training normally required for examination by the NRC for a senior Reactor operator's License, whether or not the examination is taken.
In addition, either the operations supervisor or the assistant operations supe rvisor snell have an sRo license.
D
- 358, Amendment No. dt,' 79
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Amendment No. 79 361
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Nuclear Plant Superintendent Plant Operations Review Coenitte REVIEW AND AUDIT FUNCTION FICURE 6.2-1 363 Amendment No. 79
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nne...a 3r,4 knendment Noe 79
8 o
UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
j WASHINGTON O. C. 20555 e
TENNESSEEVALLEYAUTHORIIY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT. UNIT NO. 2 AENDENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendments by Tennessee Valley Authority (the A*
licensee) dated May 15, 1981, as supplemented by letter dated July 13,1981, complies with the standards and requirements of the Atomic Erergy 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 application, the provisions of the Act, and the rules and regulations of the Commission; i
I 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 j
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 al.1 applicable 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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75, are hereby incorporated in the-license. The ifcensee shall operate the facility in accordance with the Technical Specifications.
t,m
s' 2
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i 3
3.
This license amendment is effective as of the date of its issuance.
3 FOR THE NUCLEAR REGULATORY COPNISSION l
3 M, s i
s Thomas /Ippolito, Chief Operating Reactors Branch #2 i
Division of Licensing I-
Attachment:
i-Changes to the Technical Specifications Date of Issuance:
December 2, 1.981 1
i i
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e
ATTACHMENT TO LICENSE AMENDT NT NO. 75 FACILITY OPERATING LICENSE N0? DPR-52 DOCKET N0. 50-260 Revise Appendix A as follows:
1.
Replace the following pages with the identically numbered pages:
332 335 336 337 346 358 359 361 362 363 364 Marginal lines on the above pages indicate the areas being revised.
2.
The overleaf pages are not being revised and should be retained.
ei-e 9
M
~
6.0 ADMINI0iENTtvr co.:Tnot.s i
s.1 QK132l1Lt_L m AI The plant superintendent has on-site responsibilities for ths safe operation of the facility and shall report to the Assistant Director of Nuclear Power (Operations).
In the absence of the plant superintendent, an assirtant superintendent will assu:ne him reannnnihilitie=,
5.
The portion of TVA management which relates to the operatier of the plant is shown in rigure 6.1-1.
C.
Th6 functional organization for the operation of the statioq,shall be as shown in Figure 6.1-2.
D.
shif t ranning requirements shall, as a minimum, be as described in section 6.8.
g.
Qualifications of the Browns Ferry Nuclear Plant management and operating staf f shall meet the minimum acceptable levels as described in A!IS? - N18.1, selection and Training of Nuclear Power Plant Personnel, dated March 8.
1971. The qualifications of the liesich Physics Supervisor vill ineet or exceed the mininum ac'ceptable levels an described in Reguistory Cuide 1.8, Revision 1, dated Sept.1975.
r.
Retraining and replacement training of station personnel shall be in accordance with ANSI - N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The minimum frequency of the retraining "E
program shall be every two years.
c.
An Industrial Security Program shall be maintained for the life of the plant.
H.
The Safety Engineer shall have the following qualifications:
- a..Must have a sound understanding and thorough technical know' edge of safety and fire protection practices, procedures, 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'and data analysis.
Must be able to co-municate well both orally and in l
writing and must be able to write investigative reports and prepare written procedures. Must have the ability to secure the cocoeration of ranagement, eccioyees and groups in the irnplementation of safety programs. Nust be able to conduct safety presentations for supervisors and ewoloyees.
b.. Should have experience in safety engineering work at this level or have J years esperience in safety and/or fire protectiun e.igineering. It is desirable that the incur.ctnt be a graduate of an accredited college or university wit's a degree in inductrial, :necnanical, electrica1, or safety engineering or fire protection engineering.
332 Amendment No, M 75
6.n NetlNITTRATIVC CONTROLS t
E.
Plant coer a t i on,t Iteview comeittee fPORC1 1.
Members hi p The PORC shall consist of the plant superintendent, or his representative, electr'.c maintenance section supervisori n.echanical maintenance section supervisor, inst;ument maintenance section supervisor, health physics supervisor, operations seedEn supervisor, engineering section supervisor, and quality assurance supervisor. An assistant plant supervisor may serve as an alternate co==ittee me=eber when his supervisor is absent.
Tne plant superintendent will serve as chairman of l
the PORC. His representative will serve as chairman in the absence of the plant superintendent.
2.
.= e c t i n er F-pouen g The PORC shall meet at regular monthly intervals anc for special meetings as called by the chairman or as requested by individual members.
3.
Quorum j
Superintendent or his representative, plus five of the =even other members, or their alternate, will constitute a quorum.
A member will be censidered present if he is in telephone communication with the committee.
335 Amendment No.[ 75
s' 6.0 3DMIUJSTRATIVE CONTROLS
^
S.
Dut1C2_40d_Respgngibiligigg
~
The l'OMC serves in an advisory capacity to the plant superintendent and as an investigating and reporting body to the Nuclear Safety Review Board in matters related to safety in plant operations.'
The plant superintendent has the final responsibility in determining the matters that should be referred to the Nuclear Safety Review Board.
The responsibility of the committee will include:
a.
Review all standard and emergency operating and maintenance instructions and any proposed revisions thereto, with principal attention to provisions f or' saf e operation, b.
Review proposed changes to the Technical Specifications.
c.
Review proposed changes to equipment or systems having safety significance, or which may constitute Han unreviewed safety question," pursuant to 10 CFR 50.59.
r d.
Investigate reported or suspected incidents involving safety questions, violations of the Technical Specifications, and violations of plant instructions pertinent to nuclear safety.
. Review reportable occurences, unusual events, e.
operating anomalies. and abnorral performance of plant equipment.
f.
Maintain a general surveillance of plant activities to identify possible safety hazards.
Review plans for special fuel handling, plant 9
maintenance, operations, and tests or experiements which may involve special saf ety i
considerations, and the results thereof, where applicable.
h.
Review adequacy of quality assurance program and recommend any appropriate changes, i.
Review implementating procedures of the Radiological Emergency, Plan and the Industrial Security Program on an annual basis.
336 l
l i
Amendment No. 75
Z9 %II. 5.SDF.292 V
4 M ' I ?
i.
H etv ie:w ilequacy. of employee training progr ape
.inct ecommend change.
5.
A:thority 7ne TORC shall be advisory to the plant Fuperintendent.1 6.
Decords M.inutes shall be kept f or all PORC meetings with copies sent to Director, Nuclear Power; Assis' tan; Director of Nuclear Power (Operations); Chairman, NSRB l
7 Procedures Written administrative procedures for committee operation snall be prepared and maintained l
describing the method for submission and content of presentations to the committee, revtew and approval by members of committee actions, dissemination of minutes, agenda and scheduling of netings.
-f i
i I
337 l
l Amendment No. yf, 75 I
l
e i
AD!41tly;Tiv TIVE cot Ti<OLS a,
O Actions to be T511en in the Event of'a 3eportabic Occurrence 6.4 in Plant cueration (Ref. Section f.7)_
Any reportable occurrence shall be promptly reported to -
A.
the Assistan't Director, Nuclear Power (Ope ations) and shall be r
This committee sha11 prepare promptly reviewed by PORC.
This a sepa ratet. report. f 6r each reportabic occurrence. include an evaluat report shall occurrence and recommendations for appropriate action to or reduce the probability of a repetition of the prevent occu r r en ce.
copics of all such reports shall be submitted to the Assistant Director, Nuclear Power (Operations), the Manager of Power, B.
and tne Chairman of the NSRB for their review.-
The plant superintendent shall notify the NRC as specified in Specification 6.7 of the circumstances of C.
any reportable occurrence.
.-r-6.5 Action to be Taken in the Event a sa f ety Li,i i t is Exceeded If a na fety limit is exceeded, the reactor shall be shut down and reactor operation shall not be resumed until authorized shall be reade to the Assistant by the ' lJHC.
A pro.npt report Director, Nuclear Power (Operations), and the Chairman of the NSRB.
A co:rplete gnalysis of the circumstances Icading up to anutogether with recom resulting from the situation, This shall be prepared by the POFC.
to ptevent a recurrence, report shall be submitted to the Assistant Director, Nuclear Power (Operations),
l the Manager of Power, Notification est such occurrences and the NJRB.
within 24 will be made to the NRC by the plant spperintendent hours.
G.6 nt,it i on opera t i y:- 9.- cords Records and/or logo shall be k'ept in a manner convenient A.
for reeview as indicated below:
All normal plant oteration including such items or 1.
power level, fuel exposure, and chutdo ns PrincLpal maintenance activities 2.
3.
Re;iortable occurrences W'
1 Amendment No. 75 y
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6.0 6Ifi! W 'TP A.1.I.Vf.'.iM.iTE9 LII 1
a 6.8 Mi n,i mu m Pl ant Staffing The minimum plant staffing for monitoring and conduct of operations is as f ollows.
1.
A licensed senior operator shall be present at the site at all times when(there is fuel in the reactor.
2.
A licensed operator shall be 'in the control room whenever there is fuel in the reactor.
3.
A licensed senior operator shall be in direct charge of a reactor refueling operation; i.e.,
able to devote full time to the refueling operation.
A health physics technician shall be present at the 4
facility at all times there is fuel in the reactor.
5.
Two licensed operators shall be in the. control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.
~
l 6.
Either the plant suparintendent or an assistant pifn t.
superintendent shall have acquired the experience And training normally required for examination by the NRC for a Senior Reactor Operator's License, whether or not the examination is taken.
In addition, either the operations supervisor or the assis+ ant operations supervisor snall have an SRO licenJc.
~
358 Amendment No. fg, 75
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359 Amendment No. 75 e
Manager i
of Power
,' Manager of Power Operations Division of Nuclear Power
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Nuclear Plants
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BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TVA Office of Power Organization for Operation of Nuclear Plants i
FIGURE 6.1-1 l
i 361 l
Amendment No. 75 l
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Amendment No. 75 P3 36a.
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Manager of Power Quality Assurance Nuclear Safety Audit taff Manager 5
of Power Operations Division of Nuclear Power
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i Nuclear Plant Superintendent Plant Operations Review Comitte REVIEW AND AUDIT 71JNCTION FIGURE 6.2-1 Amendment No. 75
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f Assistant Power Plant lias been delegated the responsibility Superintendent for overall administration of the plant fire protection and pre-vention program in accor' dance with approved standards and practices as adopted for pl~ ant needs.
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>.s 36/s-Amendment No. 75
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.,k, UNITED STATES y
NUCLEAR REGULATORY COMMISSION 3
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, ASHi%1 TON, D. C. 20555 W
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t TENNESSEE VA'. LEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 3 AMENDMENT TO. FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendments-by Tennessee Valley Authority (the licensee)datedMay 15, 1981, as supplemented by letter dated July 13,1981, 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 conformity with the application, the provisions of the Act, and the rules and regulations ofTthe Commission; 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) 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applic.able 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 Facili.ty License No. DPR-68 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
eg i
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2
~
l This license amendment is effective as of the date of its' issuance.
3.
a FOR THE NUCLEAR REGULATORY COMISSION 3
J n
Thomas. Ippolito, Chief Operating Reactors Branch #2 i
Division of Licensing
Attachment:
- r Changes to the Technical Specifications Date of Issuance: December 2, 1981 i
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ATTACHMENT TO LICENSE ~ AMENDMENT NO. 48 1
l FACILITY OPERATING LICENSE NO. DPR-68 t
DOCKET NO. 50-296-Revise Appendix A as follows:
1.
Remove the following pages and replace with the identically' numbered pages:
362 1
L 365 366 367 376 388 389 391 392 393 394 2.
Marginal lines on the above pages indicate the areas being change'd.
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ADMINISTRATIVE CO.:TDCt S 4.0 to.1 os an} p jyn The plant superintendent has on-site responsibilities for i
ths safe operation of the facility and shall report to the Assistant A.
In the absence of the Director of Nuclear Power (Operations).
plant superihtendent, an assistant superintendent will assume hi.= rasnnnsthilities.
The portion of TvA manacement which relates to the operatica of.the plant is shown in Figure 6. t-1.
3 The functional crganizatien for the operation of the station shall be as shewn in Figure 6.1-2.
C.
shif t manning requirements shall, as a minimum, be as D.
described in section 6. 8.
Plant Qualifications of the Brewns Ferry Nuclec i i um management and cperating staf f shall meet the m n m E.
acceptable ~ levels as described in A11SI - N18.1, l
Selection and Training of Nuclear Power Plant Persenne.1971. The Supervisor vill meet 'or exceed the minints acceptable levels as dated March 8, 1975.
described in Regulatory Cuide 1.8 Revision 1, da'ted Sept.
training of station persennel Retraining and replacement Selec. ion and shall be in accordance with ANSI - N18.1, T.
Training of Nuclear Fower Plant persennel,' dated Much The minimun f requency of the retraining 1971.
8,program shall be every two years.
2~
An Industrial Security Program shall be maintained for c.
the life of the plant.
The Safety Engineer shall have the fo11 ewing qualifications:
H.
Must have a sound understanding and thorough technical kncwledge of safety and fire protection practices, a.
procedures, standards, and other codes relating toMust te able to read elettrical utility operations.
and understand enginaering drawings.
t I
I Amendment No. /, 48 362 4
I I
6.n NdtNITTRATIVCCONTROLS b
E.
Plant Operations Review Committee fPORC1 1.
Membership The PORC shall consist of the plant superintendent, or his representative, electric maintenance section supervisors mechanical maintenance section supervisor, instrument maintenance section supervisor, health physics supervisor, operations secti-6n supervisor, engineering section supervisor, and quality assurance supervisor. An assistant plant supervisor may serve as an alternate co=mittee memeber when his supervisor is absent.
Tne plant superintendent will serve as chairman of the pOAC. His representative will l
serve as chairman in the absence of the plant superintendent.
2.
Meetina Y'eauen g The PORC snall meet at regular monthly intervals and for special meetings as called by the chairman or as requested by individual mer.bers.
3.
Quorum Superintendent or his representative, plus -
l five of the seven other members, or their alternate, will constitute a quorum. A member will be censidered present if he is in telephone communication with the committee.
3G5 Amendment No. /, 48
~
s' 6.0 ADMItIISTRATIVE CONTROLS l
S.
Dutien_and Beausnuibilitisu 5
The PO'HC serves in an advisory capacity to the plant superintendent and as an investigating and i
reporting body to the Nuclear Safety Review Board in matters related to saf ety in plant operations.'
j The plant superintendent has the final responsibility in determining the matters that.
should be referred to the Nuclear Safety Review j
Board.
The responsibility of the 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.
Review proposed changes to the Technical 3pecificat' ions.
c.
Review proposed changes to equipment or systems having safety significance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.59.
g d.
Investigate reported or suspected incidents involving safety questions, violations of the Technical Specifications, and violatiens 'of plant instructions pertinent to nuclear
- safety, e.
Review reportable occurences, unusual events, operating anomalies and abnormal perf ormance of plant equipment.
f.
Maintain a general surveillance of plant activicies to identify possible safety 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 thereof, where applicable.
h.
Review adequacy of quality assurance program and recommend any appropriate changes, i.
Review implementating procedures of the Radiological Emergency Plan and the Industrial Security Program on an annual basis.
366 Amendment No. / 48 m
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.inct r ecommend change.
5.
Aut hor it y Tne PORC shall be advisory to the plant stuperintendent.,
6.
Records Minutes shall be kept for all PORC meetings with copies sent to Director, Nuclear Power; Assis' tant Director of Nuclear Power (Operationsl; Chair =an, NSRB 7
P rocedur es
'a'ritten administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of committee actions, dissemination of
~
minutes, acenda and scheduling of meetings.
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l 367 f
l AmendmentNo.JT,48 l
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AD11tJIMTW,TIVE Cot;TkOLS t,
O
.e Event of a 99 portable Occurrence-6.4 Acti>ns to be Taken in Pl an t Coeration N f. Section 6.7)
Any reportable occurrence shall be prompt'ly re' ported to A.
the' Assistant Director, Nuclear Power (Operations) and shall be This committee shall prepare promptly reviewed t [PORC.fo each reportable occurrenCo.
This sepa rate report shall include an evaluation of the cause of the a
report occurrence and recommendations for appropriate action to or reduce the probability of a repetition of the prevent occurrence.
Copies of all such reports shall be submitted to the Assistant Director, Nuclear Power (Operations), the Manager of Power, B.
and tne Chairman of the NSRB for their revicw.
- The plant superintendent shall notify ti.- NRC as specified in specification 6.7 of the circamstances of C.
any reportable occurrence.
_r 6.5 Action to be Taken in the Event a sa f etv Limit is Exceeded If a sa fety limit is exceeded, the reactor shall be shut.down be resumed until authorized and reactor operatiori shall notshall bc :-ade to the Assistant by the NBC.
A prompt report Director, Nuclear Power (Operations), and the Chairman of the NSRB.
A
! caning up to anu cc: plete analysis of the circumstancestogether with recommendations resulting from the situation,shall be prepared by the PoRC.
This to prevent a recurrence, report shall be submitted to the Assistant Director, Nuclear Power (Operations),
_l the Manager of Power, and the NORB.
Notification of such occurrences will be made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.6 Etation_oparating F+, cords Records and/or logs shall he kept in a manner conveni'nt A.
for review as indicated belew:
1.
All normal plant ot.cration including such iter as power level, fuel exposure, and chut.de ins 2.
Princi, pal maintenance activities
~
3.
F.eportable occutren:cs 376 Amendment No./," 48
6.0 AD'if f 31 ?;TPA1IVE CONTROLS a
I 6.8 Minimum Plant Staffinq The minimum plant staffing for monitoring and conduct of operations is as follows.
1.
A licensed' senior' operator shall be present at the site at all times when there is fuel in the reactor.
t 2.
A licensed operator shall be in the control room whenever there is fuel in the reactor.
3.
A licensed seni6r operator shall be in direct charge of a reactor refueling operation; i. e., able to devote f ull time to the refue?.ing operation.
4 A health physics technician shall be present at the facility at all times there is fuel in the reactor.-
5.
Two licensed operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from. unit trip.
~
l 6.
Either the plant superintendent or an assistant pldnt superintendent shall have acquired the experience and training normally required for examination by the NRC for a Senior Reactor Operator's License, whether or not the examination is taken.
In addition, either the operations supervisor or the assistant operations supe rvisor shall have an SRO license.
G e
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388 -
Amendment No. /, JVI, 48 T
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389 Amendment No. 48 O
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Manager i
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Power s
. Manager of Power Operations Division of Nuclear Power 4-Nuclear Plants BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TVA Office of Power Organization for Operation of Nuclear Plants FICURE 6.1-1 391 Amendment No. 48
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Manager of 1
Power Quality Assurance Nuclear Safety Audit Staff-
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Nuclear Power
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Nuclear Plant Superintendent Plant Operations Review Cot =nitte REVIEW AND AUDIT FUNCTION FIGURE 6.2-1 393 Amendment No. 48
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