ML20070K045
| ML20070K045 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/06/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K046 | List: |
| References | |
| GL-86-10, NUDOCS 9103180283 | |
| Download: ML20070K045 (13) | |
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TENHFS3EE VA! LEY AUTHORITY DOCKET NO. 50-260 tsROWNS FERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.192 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Commission) has found u.at:
A.
The opplication for amendment by Tennessee Valley Authority (the licensee) dated April 14, 1989, as supplemented by April 14, 1989 January 30, 1990, and Decer.ber 11, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as an.e.'ded (the Act), and the Comission's rules and. regulations set forth in 10 CFR Chapter I; B.
The facility will operate ir conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby
'his amendment can be conducted without endangering the health,ad 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 common defense and security or to the health and safety of the public; and E.
The issuance of this amenoment is in accordance with 10 CFR Part 51 of the Commission's regulations and all Applicable requirements have been satisfied.
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l 9103180283 910306 DR ALOCK 05000260 PDR
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2.
Accordingly, Facility Operating License No. DPp-52 is amended by changes to Appendix A (i.t. Technical Specifications) as indicated in the attachment to 111s license amendment; paragraph 2.C.(2) is amended and paragraph 2.C.(5)(a)*isaddedtothelicensetoreadasfollows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.192, are hereby incorporated in the license. The licensee shall operate the facility in accordance witle the Technical Specifications.
(5)(a)
Brown Ferry i;uclear Plant shall implement and maintain all
.previsions of the Appendix R Safe Shutdewn Program as described in the subtrittal dated April 14, 1989, as suppitmented by December 11,1990, and as approved in the NRC Safety Evaluation dated March 6, 1991, subject to the following provision:
The licensee raay make chantes to the approved Appendix R Safe Shutdown Program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
l 3.
This license amendment is effective as of its date of issuance, and shall be implemented within 60 days from the date of issuance but no later than restart of Unit 2.
FOR THE NUCLEAR REGULATORY COMMISSION Y
- lbdon, Director -
Frederick J.
e Project Directrrate !!-4, NRR Divistor, of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
- . Pages 4 and 4a of license 2.
Changes to the Tectinical Specifications Date of Issuance: March 6, 1991
- Pages 4 and 46 of the License are attached, for convenience, for the composite License to reflect this change.
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(3)
In the operation of the faellity, the licensee shall, pursuant to the Federal Water Pollution Control Act Amendments of 1972 (Public Law 92-500), comply with all applicable thermal water quality standards of the State of Alabama and the United States.
(4)
The licensee is hereby granted an exemption from the requirements of General Design Criterion 4 with respect to high energy pipes outside containment in accordance with the condition set forth in the Technical Specifications, Section 3.6.G.2 which requires completion of those items listed in ' Concluding Report on the Effects of Postulated Pipe Tailure Outside of Containment for the Browns Terry Nuclear Plant Units 2 and 3' and related to Unit 2 prior to startup of Unit 2 following the first refueling outage."
(5)
The facility may be modified as dascribed in Section X of ' Plan f or Evaluation, Repair, and Return to Service of Browns Terry Units 1 and 2 (March 22, 1975 Fire)' dated April 13, 1975, and
- evisions thereto.
The facility mey be modified by plugging the bypass flow holes in the lower core support plate as described in Browns Terry Nuclear Plant Units 1 and 2 Safety Analysis Report for Plant Modifications to Eliminate Significant in-Core Vibrations (NEDC-21091), October 1975. The reactor shall not be operated with the plugs installed in the lower core support plate bypass flow holes without further authorization by the NRC."
(5)(a)
Browns Terry Nuclear Plant shall implement and maintain in effect all provisions of the appreveo Appendix R Safe Shutdown Program as described in l
submittal dated April 14, 1989, and as revised in i
submittal dated December 11, 1990, ard as approved in NRC Safety Evaluation dated March 6. 1991
, subject to the following provision:
The licensee may make changes to the approved Appendix R Shutdown Program with'out prior approval of the Commission only if those changes would not adversely affect the abtifty to achieve and maintain safe shutdown in the event of a fire.
BTN Amendment 192 Unit 2
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The facility may be modified by drilling bypass flow holes in Type 2 and Type 3 fuel assemblies as described in NED0-21091,
" Browns Terry Muclear Plant, Units 1 & 2 Safety Analysis Report for Plant Modifications to Eliminate Significant In-Core Vibrationr; and NEDE-21156, " Supplemental Information for Plant Modification to Eliminate Significant In-Core Vibrations,"
dated January 1976.
(7)
The facility may be modified as described in ' Browns Terry Nuchar Plant Units 1 and 2 Emergency Core Cooling Systems Low Pressure Coolant Injection Modifications for Performance Improvement (December 197$)' submitted by application dated December 1, 1975 and supplements dated February 12, 1976, 4 arch 24, 1976, March 30,1976, May 21,1976, June 11,1976, and July 21, 1976."
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BFN Mendment 192 Unit 2
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o ATT/CHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. DPR-5?
DOCKET NO. 50-260 P,evise the Appendix A Technical specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and crntain marginal lines indicating the area of change. Overleaf
- pages are provided to maintain document completeness.
l REMOVE INSERT 1.0.12a 1.0-12b 6.0-7 6. 0 -7 '
6.0-8 6.0-0 6.0-13 6.G 43*
6.0-14 6.0-14 6.0-19 s.0 19*
6.0-20 6.0-20 l
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prrINITIONS (Cont'el NN.
ADDendir R Safe Shutdown Prozram BrN has developed an Appendia R Sade Shutdown Program. This Program is to ensure that the equilment required by the Appendix R Safe Shutdown Analysis is maintaleed and demonstrated functional as follows:
1.
The functional requirements of the Safe Shutdown systems and equipment, as well as appropriate compensatory measures should these systems / components be unable to perform their intended function are outlined in Section III of the Program.
2, Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.
3.
Changes made co the BrN Appendix R Safe Shutdown Program will be processed in accordance with License Condition 2.C.5.(a).
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DFN 1.0-12a Amdt. 192 Unit 2 l
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e THIS PAGE INTENTIONALLY LEFT BLANK 1
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l BFil 1.0-12b Amdt. 192 Unit 2 e +
6.5.1.4 For expedited meetings, when it is not practical to-convene as a group, the chairman or alternate chairman may conduct committee business by polling the members individually (by telephone or in person) or via a serialized review.
QUORUM 4
6.5.1.5 - The quorum necessary for the PORC to act in a formal meeting shall consist of the chairman or alternate chairman and at least five members or their alternates. Members shall be considered present if they are in telephone communication with the committee.
RESc NS!b!LITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.
The PORC may delegate the performance of reviews, but vill maintain cognizance over and responsibility for them, e.g.,
subcommittees.
-a.
Review of administrative' procedures for the control of the technical-and cross-disciplinary review of (1) all procedures-required by Specification 6.8.1.1, and changta thereto, (2) any other procedures and changes thereto determined by the Plant-Manager-to affect nuclear safery.
- b. -Review of the administrative procedures. required by l
Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and changes thereto, i
Review of emergency operating' procedures and changes thereto, c.
d.
Review implementing procedures of the Radiological Emergency Plan and the Industrial Security Program.
j 0,145 BFN 6.0-7 Unit 2-
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e.
Review of all ptsp: sed chtnges to the Technical Specifications.
f, Review of safety evaluation for proposed tests or experiments to be completed under the provisions of 10 CFR 50.59 3
Reviev proposed changes to the Radiological Effluent Manual.
h.
Review adequacy of the Process Control Program and Offsite Dose Calculation Manual at least once every 24 months.
1.
Review changes to the radwaste t
'ent systems.
J.
Review of every unplanned onsite release of radioar,sve material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and disposition of the cerrective action to prevent recurrence to the Senior Vice President, Nuclear Power, and to the Nuclear Safety Revies Board, k.
Review of all safety evaluations for modifications to strut:ures, systems or components that affect nuclear safety to verity thet such actions did not constitute an unreviewed safety question as defined in 10 CFR 50.59, or requires a change to these T9chnical Specifications.
l 1.
A review of the Appendix R Safe Shutdown Program and implementing procedures.
Submit all PORC approved changes to NSRB.
EFN 6.0-8 Amdt. 192 Unit 2
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4 REVIEW s
6.5.2.7 The NSRB shall revievt a.
The safety evaluattons for
_(1) changes to _ procedures, equipment or systeam, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify thet auch actions did not constitute an unreviewed safety I
question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50,59, 10 CFR.
c.
Proposed tests or experiments-which involve an unreviewed-safety question as defined in Section 50.59, 10 CFR.
t.
Proposed changes to Technical Specifications or this.
Operating License.
e.
Violations of Codes, regulations, orders, Technical.
Specifications, license requirements, or of. internal-procedures or instructiona-having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal andiexpected performance af plant equipment _that t.
affect nuclear sarsty.
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All Reportable Events
- b. _All recognized indications of an' unanticipated deficiency in
~
- some aspect of design or; operation-of structures, systems, or components that could affect nuclear safety; and 1
i 1.
Reports and meeting minutes of the-PORC.
AMENOMENT NO.14 5 BFN 6.0-13 Unit 2
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AUDITS t
6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB.
These audith shall encompass s.
The conformance of plant operation to provisions cor,tained-within the Technical Specifications and applicable license conditions at least once per 12 axaths.
b.
The performance, training and qualifications of the entita plant staff at least once per 12 months.
i c.
The results of actions taken to correct deficiencies occurring in site equipment, structures, systems or method ei c'jeratian that affect nuclear safety at least once per 6 mor.chs.
d.
The performance of activities required by the Operatioaal Quality Assurance Program to meet the criteria or Appendix
'B, 10 CFR Part 50, at least once per 24 eanths.
e.
The Site Radiological Emergency Plan and implementing procedures at least once every 12 nonths'.
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f.
The Plant Physical Security Plan and implementing procedures at least once every 12 months.
g.
Any other area of site operation considered appropriate by the NSRB or the Senior Vice President, Nuclear Power, h.
The fire protection programmatic controls and Appendiz R Safe Shutdown Program including the implementing procedures sr. least once per 24 months.
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Amdt. 192 nt2
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d 6.7 SAFETY LIMIT VIOI.ATIDE 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operaticna Center shall be notified by tuephone as soon as possible a:ad in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Senior Vice President, Nuclear Power and the NSRB shall be notified within 24 tours.
b.
A Safety Limit Violation 3teport shall be preparea the report shall be reviewed b;r the POTC. This report t, hall describe (1) applicable cirete 'ances pr
- ceding th9 violation, (2) effects of the viohtion upo. 5 111ty components, systems, or structures, and (3) corrective action taken to prevent recurrence, c.
The Safety Limit Violation Report shall be submitted to the commission, the NSRB, and the Senior Vice 1 resident, Nuclear Power within 14 days of the violatior..
d.
Critical operation of the unit shall not be resumed until authorized by the Cosatssion.
I 145 BFN 6.0-19 Unit 2
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6.8 - PROCEDURES / INSTRUCTIONS AND PROGRAMS t
6.0.1 PROCEDURES 6.8.1.1 Written procedures shall be established, implemented and maintained covering the activities reterenced below:
j a.
The applicable procedures recomm nded in Appendix A of Regulatory Cuide 1.33, Revision 2, February 1978.
b.
Limitations on the amount of overtime worked by individuals performing safety-related functions in accordane:. witt NRC Policy statement on working hours (Generic Letter No. 32-12).
c.
Surveillance and test activities of safety-related equipment.
d.
Sea.urity plan implementatfo~n.
e.
Emergency plan impismantation-f.
Fire Protection Progre.m and Appendix R Safe Shutdown Program implementation.
l g.
Radiological Effluent Manual implementing procedures.
h.
Process Control Prograr: (PCP).
1.
Offsite Dose Calculaticn Manual.
- j. Administrative procedures which control technical and cross-disciplinary review.
BFN 6.0-20 Amdt. 152 Uni' 2 v-
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