ML20150D139
| ML20150D139 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-33-A-149, DPR-52-A-145, DPR-68-A-120) |
| Issue date: | 06/30/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20150D144 | List: |
| References | |
| NUDOCS 8807130332 | |
| Download: ML20150D139 (108) | |
Text
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8 UNITED STATES o
8 NUCLEAR REGULATORY COMMISSION o
- {
WASHINGTON. O. C. 20666 k
/
4....e TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.149 License No. OPR-33 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedJune 17, 1988 as supplemented June 23, and June 24, 1988, 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 conformity with the application, the provisians of the Act, and the rules and regulations of, the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering tt,a health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's resulttions; D.
The issuance of this amendment will not be inimical to
.e comon defense and security or to the health ed safety of the public; and E.
The issuance of this amendment is in'accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8807130332 880630 DR ADOCK 05000259 PDC
8 0
l 5
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-33 is hereby amended to read as follows:
l (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as f
revised through Amendment No.149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: June 30, 1988 t
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 149 FACILITY OPERATING LICENSE NO. OPR-33 DOCKET NO. 50-259 Revise 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 contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document. completeness.
REMOVE INSERT 6.0-1 6.0-1 6.0-2 6.0-2 6.0-3 6.0-3 6.0-4 6.0-4 6.0-5 6.0-5 6.0-6 6.0-6 6.0-7 6.0-7 6.0-8 6.0-8 6.0-9 6.0-9 6.0-10 6.0-10 6.0-11 6.0-11 6.0-12 6.0-12 6.0-13 6.0-13 6.0-14 6.0-14 6.0-15 6.0-15 6.0-16 6.0-16 6.0-17 6.0-17 1
6.0-18 6.0-18 6.0-19 6.0-19 6.0-20 6.0-20 6.0-21 6.0-21 6.0-22 6.0-22 6.0-23 6.0-23 6.0-24 6.0-24 6.0-25 6.0-25 6.0-26 6.0-26 6.0-27 6.0-27 6.0-28 6.0-28 6.0-29 6.0-29 6.0-30 6.0-30 6.0-31 6.0-31 6.0-32 6.0-32 6.0-33 6.0-33 6.0-34 6
i BFN TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Site Director shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 Offsite and Onsite Organizations An onsite and offsite organization shall be established for unit operation and corporate management. The onsite and 'offsite i
organization shall include the positions for activities affecting the cafety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be established and defined from the highest management l'evels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented'in the FSAR and will be updated in accordance with 10 CFR 50.71(e).
~BFN 6.0-1 Amendment No. 138 149 Unit 1 e---
6.2.1 (Cont'd)
- b. The Senior Vice President, Nuclear Power, shall have corporate responsibility for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant.so that continued nuclear safety is assured.
- c. The Plant Manager shall be responsible for overall unit safe operation, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- d. The individuals who train the operating staff and those who carry,
out health physics cnd quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independer.ce from operating pressures.
6.2.2 Plant Staff
- a. Shift manning requirements, shall as a minimum, be as described in Table 6.2.A and below.
- b. A licensed senior reactor operator shall be present at the site at all times when there is.ac, in the reactor.
- c. A licensed reactor operator shall be in the control room whenever there is fuel in the reactor.
BEN 6.0-2 Amendment No. %2B 149 Unit 1 9
y.-
i 6.2.0 (Cont.)
d.
Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.
In addition, a person holding a senior operator license shall be in the control t;Sm for that unit whenever it is in an operational mode other than cold shutdown or refueling.
e.
A Health Physics Technician
- shall be present at the facility at all times when there is fuel in the reactor.
- t" f.
A person holding a senior operator license or a senior operator license limited to fuel handling, shall be present during alteration of the core to directly supervise the activity and during this time shall not be assigned other duties.
g.
A site fire brigade of at least five members shall be maintained onsite at all times.* The fire brigt.de shall not include the Shif t Engineer and the other members of the minimum shift crew necessary for safe ahistdown of the unit, nor any personnel required for o*her essential functions during a fire emergency.
I
- The Health Physics Technician and fire brigade composition may be less than the minimum requirements' for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
l BFN 6.0-3 Amendment No. 135 149 Unit 1
Table 6.2 4 Minimum Shift Crew Recuirementab Position Units in Conration Tvoe of License Q
l 2d 2
Senior Operatora 1
1 1
1 SRO Senior Operator 0
1 2
2 SRO Licensed Operators 3
3 3
3 RO or SRO Additional Licensed Operatorse 0
1 2
2 R0 or SRO Assistant Unit Operators (AUO) 4 4
5 5
None Shift Technical Advisor (STA) 0 1
1 1
None Health Physics Technician 1
1 1
1 None Note for Table 6.2.A a.
A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit.
b.
Except for the senior operator discussed in note "a",
the shift crew composition may be one lesu than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shif t crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
c.
One of the Additional Licensed Operators must be assigned to dach control room with an operating unit.
d.
The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.
Amendment No. 138 149 BFN 6.0-4 Unit 1
6.3 PLART STAFF OUALIFI3ATIONS Qualifications of the Browns Ferry Nuclear Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI -
N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.
6.4 TRAINING A retraining and replacement training program for 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 program shall be every two years.
6.5 PLANT REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 a.
The PORC shall function to advise the Plant Manager in all matters related to nuclear safety, b.
This advisory function shall be performed by the PORC acting in a formal meeting or by members acting individually without a formal meeting.
BFN 6.0-5 Amendment No. 730 149 Unit 1
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COMPOSITION 6.5.1.2 The PORC shall be composed of the:
a.
Chairman:
Plant Manager Alternate Chairman:
Assistant to Plant Manager Alternate Chairman or Member: Technical Services Superintendent Member:
Unit Superintendents (3)
Member:
Maintenance Superintendent Member:
Quality Assurance Staff Supervisor Member:
Health F~aysica Suparvisor t
b.
Allalternatechairmenandalternatemembarb,shall.be appointed in writing by the P02C chairman, MEETING TREQUENCY 6.5.1.3 The PORC shall convene in a formal meeting at least once a month and as directed by the chairman.
Other PORC meetings may be requested by the chairmen or members as required.
BFN 6.0-6 Amendment No. I3B 149 Unit 1
O 6.5.1.4 For expedited meetings, when it is not practical to convene as a group, the chairman or alternace chairman may conduct committee business by polling the members individually (by telephone or in
. person) or via a serialized review.
QUORUM 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.
RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.
The PORC may delegate the performance of reviews, but will 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, cnd changes thereto, (2) any other procedures and chanses ghereto determined by the Plant Manager to affect nuclear safety, b.
Review of the administrative procedures required by.
Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and changes thereto.
c.
Review of emergency operating procedures and changes thereto.
d.
Review implementing procedures of the Radiological Ebener:- f Plan and the Industrial Security Program.
BFN 6.0-7 Amendment No. 135 149 Unit 1
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e.
Review of all proposed changes 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 I
I l
3 Review 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.
i.
Review changes to the radwaste treatment systems.
J.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation,
}
and disposition of the corrective action to prevent i
recurrence to the Senior Vice President, Nucler,r Power, and
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to the Nuclear Safety Review Board.
i k.
Review of all safety evaluations for rodificat,iens to structures, systems or components that affect nuclear safety to verify that such actions did not constitute an unreviewed safety question'as defined in 10 CFR 50.59, or requires a change to these Technical Specifications.
Amendment No. %35 149 BFN 6.0-8 Unit 1
.P 4
1.
Review of reportable events, unusual events, operating anomalies, and abnormal performance of plant equipment.
m.
Investigate reported or suspected incidents involving safety questions or violations of the Technical Specifications, n.
Review of unit operations to datect potential hazards to nuclear safety.
Items that may be included in this review are NRC inspection reports, QA audit, NSRB audit results, American Nuclear Insurer (ANI) inspection results, and significant. corrective action reports (CARS).
o.
Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the' Nuclear Safety Review Board.
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BFN 6.0-9 Amendment F.o. J38 1.49 Unit 1
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AUT50RITT 6.5.1.7 The PORC shall:
a.
Recommend to *,he Plant Manager in writing, approval, or disapproval of items considered under 6.5.1.6.a through i above.
1.
The recommendation shall be based on a majority vote of the PORC at a formal meeting.
2.
The recommendation shall be basei on a unanimous vote of the PORC when the PORC members ate acting individually.
3.
Each member or alternate member shall have one vote.
b.
Furnish for consideration a determination in writing with regard to whether or not each item considered under 6.5.1.6.f above constitutes an unreviewed safety question.
Make recommendations to the Plant Manager in w'riting that c.
ac.tton reviewed under 6.5.1.6.k above did not, constitute an unreviewed safety question.
d.
Provida written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Director and the Nuclear Safety Review Board of disagreements betwaen the PORC and the Plant Manager.
l However, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.
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Amendment No. 138 149 BFN 6.0-10 Unit 1 l
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N 6.5.1.8 Tht.t FMtc shall maintaizvritten minutes of each PORC meeting includiskexpeditedmeetingsthat,asaminimum,documentthe resul'l of all PORC rativities performed under the responsibility r
s anr1 uthority provianus of these technical specifications.
Copf p chall be provided to the Site Director and the Nuclear Safety Review Board.
i i
' E5. 2 N.tCLEAR SAK fY REV E BOARD (NSRB)
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' iN 3,
WNCTFM 3
1
,s 6.5.2.1 The NS?G aAnil function to provide. independent review and audit ch r..((zance of designated activities'in the areas of:
A. Nuclear power plant operations b.
Nuclear engineering c.
Chemistry i.nd radiochemistry d.
Metallurgy, e.
Instrumentation and control f.
Radiological safety i,
pf hechanical anc'., electrical eng!,acering, and 3
u\\ Quality assurance practic n 1
f CCMPOSITION
- 6. 5. 2.2 The NSRB siisiil oc composed of at leact five members, including 1
s 6
th6 Chairmal..!. Members of the NSRB may be from the Nuclear Power j
<or othe 'pvi o.ganizations, or external to TVA.
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' 6. 6.- 11 Amendment No. 't38149 Unit 1 4
QUALIFICATIONS l
6.5.2.3 The Chairman, members, alternate members of the NSRB shall be appointed in writing by the Senior Vice President, Nuclear Power and shall have an academic degree in engineering or a physical sciance field, or the equivalent; and in addition, shall have a minimum of 5 years technical experience in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
}
CONSULTANTS
- t 6.5.2.4 Consultants shall be utilized to provide expert advice as determined by the NSRB.
MEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per six months.
QUORUM t
6.5.2.6 The minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shall consist of more than half of the NSRB membership or at least five members, whichever is greater. The quorum shall include the Chairman or his appointed alternate and the NSRB members including appointed alternate members meeting the requirements of 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
BFN 6.0-12 Amendment No.138 149 Unit 1 9
REVIEW 6.5.2.7 The NSRB shall review:
a.
The safety evaluations for:
(1) changes to procedures, equipment or systems, and (2) tests or experimi.tes completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes co 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.
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 safet'y significance.
f.
Significant operating abnormalities or deviations fron normal and expected performance of plant equipment that affect nuclear safety, g.
All Reportable Events h.
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 i.
Reports and meeting mir.utes of the PORC.
BFN 6.0-13 Amendment No. 138 149 Unit 1-
b e
AUDITS 6.5.2.8 Audits of unit activities shall be perforned under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of plant operation to provisions contained within the Technical Specifications-and applicable license conditions at least once per 12 months, b.
The performance, training and qualifications of the entire plant staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in site equipment, structures, systems or method
- of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
I e.
The Site Radiological Emergency Plan and implementing procedures at least once every 12 months.
f.
Ths 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.
The fire protection ' regrammatic controls including the h.
s implementing procedures at least once per 24 months.
BFN 6.0 14 Amendment No. 138 149 Unit 1
AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Senior Vice President, Nuclear Power on those a:eas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
REC 0kJS 6.5.2.10 Reports of activities shall be prepared, approved, and I
)
distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Senior Vice Prc=ident, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
l c.
Audit reports encompassed by Specification 6.5.2.8 aboveg l
shall be forwarded to the Senior Vice Presiden't, Nuclear Power and to the' management positions responsible for the areas audited within 30 days after completion of the audit.
)
BFN 6.0-16 Amendmeny No. 132, Z38 149 Unit 1
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- i. An independent fire protection and loss prevention program inspection and audit shall on performed annually utilizing either qualified offsite license personnel or an outside fire protection firm.
J.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The Radiological Environmental Monitoring program and the results thereof at least once per 12 months.
1.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, or Regulatory Guide 1.21, Rev. 1, 1974, and Regulatory Guide 4.1, 1975, at least once every 12 months.
m.
131e performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR'73.40(d)'at least once every 12 months.
n.
The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
o.
The Process Control Program and implementing procedures for solidification of wet radioactive vastes at least once per 24 months.
p.
The Radiological Effluent Manual and implementing procedures at least once per 12 months.
BFN 6.0-15 Amendment 132, 738 149 Unit 1
4 f
6.5.3 TECHNICAL REVIEW AND APPROVAL OF PROCEDURES ACTIVITIES 6.5.3.1 Procedures required by Technical Specification 6.8.1.1 and other procedures which affect plant nuclear safety, and changes (other than editorial or typographical changes) thereto, shall be prepared, reviewed and approved. Each procedure or procedure change shall be reviewed by an individual other than the preparer. The reviewer may be from the same organization or from a different organization. Procedures other than Site Director Standard Practices will be approved by the responsible Section Supervisor, or applicable Plant Superintendent.
6.5.3.2 Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.
Proposed modifications to plant nuclear safety-related structures, systems and components shall be approved by the Plant Manager, prior to implementation.
BFN 6.0-17 Amendment No. 132, 138 149 Unit 1 l
l i
6.5.3.3 Individuals responsible for reviews performed in accordance with 6.5.3.1 shall be members of the site supervisory staff previously designated by the Plant Manager. Each such review shall Anelude a determination of whether or not
, additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by review parsonnel of the appropriate discipline.
6.5.3.4 The Plant Manager shall approve all administrative procedures requiring PORC review prior to implementation.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPOETABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to th'e NSRB and the Site Director.
s BFN 6.0-18 Amendment tio. 732 135, 149 Unit 1
6.7 FAFETY LIMIT VIOLATIQH 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as
)
soon as possible and 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The
}
report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility 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 President, Nuclear Power within 14 days of the violation.
d.
Critical operation of the unit shall not be res'med until u
authorized by the Commission.
BFN 6.0-19
- Amendment No. 132, IJB, 149 Unit I l
l l
l
6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 PROCEDURES 6.8.1.1 Written procedures shall be established, implamented and maintained covering the activities referenced below:
b a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Limitaticas on the amount of overtime worked by individuals performing safety-related functions in accordance with NRC Policy statement on working hours,-
(Generic Letter No. 82-12).
c.
Surveillance and test activities of safety-celated equipment.
d.
Security plan implementation.
e.
Emergency plan implementation.
i f.
Fire Protection Program implementation.
g.
Radiological Effluent Manual implementing procedures.
h.
Process Control Program (PCP).
i.
Offette Dose Calculation Manual.
J.
Administrative procedures which control technical and cross-disciplinary review.
BFN 6.0-20 Amendment No.132/138, 149 Unit 1
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6.8.1.2 Each administrative procedure required by Section 6.8.1.1.a.
shall be reviewed by PORC and all other procedures required by Section 6.8.1.1.a. shall be reviewed in accordance with Section 6.5.3.
6.8.1.3 Temporary changes to procedures of Speelfication 6.8.1.1 may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator License on the unit affected; c.
The change is documented, reviewed by the PORC and approved by the Plant Marsger within 14 days of e
' implementation, for changes in administrative procedures requiring PORC review.
d.
The change is documented, reviewed per Specification 6.5.3, and approved by'the responsible. group section supervisor within 14 days of implementation, for changes to procedures other than administrative procedures.
a DRILLS 6.8.2 Drills on actions to be taken under emergency conditions involving release of radion.ctivity are specified.in the Radiological Emergency Plan and shall be conducted annually.
Annual drills shall also be conducted on the actions to be taken following failures of safety-related systems or components.
BFN 6.0-21 Amendment No. I32/ Z35, 149 Unit 1
O RADIATION CONTROL PROCEDURES 6.8.3 Radiation Control Procedures shall be maintained and made '
~
available to all station personnel. Tuese procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the "control device" or "alarm signal" required by paragraph 20.203 (c) of 10 CFR 20.
6.8.3.1 Each high radiation area in which the intensity of radiation is greater than 100 mrea/hr but less than or equal to 1000 arem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled
~
by requiring issuance of a Radiological Work Permit.* Any i individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followingt s.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
i b.
A radiation monitoring device which continuously integrates the radiation dose rate in the' area and alarms when a preset integrated dos,e is received.
Entry into
- h areas with this monitorins device may be made aft uhe dose rate level in the area has been' e_.aolished and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual chall be responsible l
BFN 6.0-22 Amend,nent No. I38,139 149 Unit 1
for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiological Work Permit.
6.8.3.2 Each high radiation area in which the intensity of radiation is greater than 1,000 area /hr shall be subject to the provisions of (1) above; and, in addition, access to the source and/or area shall be secured by lock (s).
The key (s) shall be under the administrative control of the shift engineer.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent uasuthorized entry may be substituted for permanent access control.
Health Physics personnel, or personnel escorted by Health Physics personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance j
requirement during'the performance of their assigned I
radiation protection duties, provided they comply with approved radiation protection procedures for entry into high I
radiation areas.
l QUALITY ASSURANCE PROCEDURES - EFFLUENT AND ENVIRDNMENTAL MONITORING 6.8.4 Quality Assurance procedures shall be established, impl'emented, and maintained for effitent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rey, 1, April 1975 or Regulatory Guide 4.15,'Dec. 1977.
l BFN 6.0-23
^ Amendment No. 132//138 149 Unit 1
6.9 REPORTING REQUIREMENTS I
l ROUTINE REPORTS f
6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal R Mulations, the following identified l
reports shall be suba tted to the Director of the Regional Office of NRC, unless otherwise noted.
6.9.1.1 STARTUP REPORT l
j a.
A summary report of plant startup and power escalation l
testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving ai
{
planned increase in power level, (3) installation of fuel l
that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating j
conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective' actions that were required to obtain satisfactory operation shall also be de, scribed. Any additional specific details required in j
license conditions based on other commitments shall be included in this report.
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BFN 6.0-24
. Amendment No. %32, Z35, %#
Unit 1
1 l
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-b.
Startup reports shall be submitted within (1) 90 days l
l following completion of the startup test program, (2) 90 days fo11'owing resumption or commencement of commercial power operation, or (3) 9 months following initial f
criticality, whichever is earliest.
If the Startup Report f
does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
6.9.1.2 ANNUAL OPERATING REPORT
- a.
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, **e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste _ processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20%
of the individual total dose need not be accodnted for.
In the aggregate, at least 80% of the total whole' body dose received from external sources shall be assigned to specific major work functions.
b.
Any mainsteam relief valve that opens in response to reaching its setpoint or due to operator action to control reactor pressure shall be reported.
- A single submittal may be made for a multiple unit station.
- This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
Amendment No./J32, 138, 149 BFN 6.0-25 Unit 1 l
\\
O 6.9.1.3 MONTNLY OPERATING REPORT Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20!55, with a copy to the Regional Office, to be su bitted no later than the fifteenth of each month following tha calendar month covered by the report. A narrative summary of operating exp6rience shall be submitted in the above schedule.
I l
6.9.1.4 REPORTABLE EVENTS Reportable events, including corrective actions and measures to' prevent re-occurrence, shall be reported to the NRC'in accordance with Section 50.73 to 10 CFR 50.
6.9.1.5 RADI0 ACTIVE EFFLUENT RELEASE REPORT Deleted (See REM section F-2) i 6.9.1.6 SOURCE TESTS l
Results of required leak tests performed on sources if the tests reveal the presence of 0.005 alcrocurie or more of removable contamination.
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BFN 6.0-26
' Amendment No./I32, 138, 149 Unit 1 I
,c 6.9.2 SPECIAL REPORTS Reports on the following areas shall be submitted in writing to the Director of Regional Office of Inspection and Enforcement:
1-Fatigue Usage 6.10.1.q Annual Operating Report 2.
Relief Valve Tailpipe 3.2.F Within 30 days after ino~per-ability of thermocouple r
and acoustic monitor on one valve.
3.
Seismic Instrumentation 3.2.J.3 Within 10 days Inoperability after 30 days of inoperability.
I 4.
Meteorological Monitoring 3.2.I.2 Within 10 days Instrumentation after 7 days of Inoperability inoperability.
5.
Primary Containment 4.7.A.2 Within 9U days Integrated Leak Rate of completion of Testing each test.
6.
Data shall be retrieved from all seismic instruments actuated during a seismic event and analyzed to determine the magnitude of the vibratorf ground motion. A Special
' Amendment No. 132, I38, 149 BFN 6.0-27 Unit 1
Report shall be submitted within 10 days after the event describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.
7.
Secondary Containment 4.7.C.
Within 90 days Leak Rate Testing
- of completion of each test.
t
- Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report should. include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergen'cy ventilation flow rate. The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limita.
Amendment No. Z32, 135, 149 l
BFN 6.0-28 Unit 1 l
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6.10 STATION OPERATING RECORDS AND RETENTIQN 6.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated below:
a.
All normal plant operation including such items as power level, fuel exposure, and shutdowns b.
Principal maintenance activities c.
Reportable Events d.
Cbecks, inspections, tests, and calibrations of components and systems, including such diverse items as source leakage' e.
Reviews of changes made to the procedttres or equipment or reviews of tests and experiments to comply with 10 CFR 50.59 f.
Radioactive shipments s.
Test results in units of microcuries for leak tests i
~
performed pursuant to Specification 3.8.D Amendment No. I32/ I28, 149 BFN 6.0-29 Unit 1
i
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h.
Record of annual physical inventory verifying accountability of sources on record
- i. Gaseous and liquid radioactive waste released to the environs J.
Offsite environmental monitoring surveys k.
Fuel inventories and transfers 1.
Plant radiation and contamination surveys m.
Radiation arposures for all plant personnel n.
Updated, corrected, and as-built drawings of the plant o.
Reactor coolant system inservice inspection p.
Minutes of meetings of the NSRB P
q, Design fatigue usage evaluation Monitoring and recording requirements below will be met for various portions of the reactor coolant pressure boundary (RCPB) for which detailed fatigue usage evaluktion per the ASMEBoilerandPressureVesselCodeSection[IIwas performed for the conditions defined in the design specification.
In this plant, the applicable codes require fatigue usage evaluation for the reactor pressure vessel only. The locations to be monitored shall be:
1.
The feedwater nozzles 2.
The shell at or near the waterline 3.
The flange studs BFN 6.0-30 Amendment No.
132/ 138, 149 Unit 1
4 4
0 Transients that occur during plant operations vill be '
reviewed and a cumulative fatigue usage factor determined.
For transients which are more severe than the transients evaluated in the stress report, code fatigue usage calculations will be made and tabulated separately.
In the annual operating report, the fatigue usage factor determined for the sransients defined above shall be added and a cumulative fatigue usage factor to date shall be reported. When the cumulative usage factor reaches a value of 1.0, an inservice inspection shall be included for the specific location at the next scheduled inspection (3-1/3-year interval) period and 3-1/3-year intervals thereafter, and a subsequent evaluation performed in accordance with the rules of ASME Section XI Code if any flaw indications are detected. The
+
results of the evaluation shall be submitted in a Special Report for review by the Commission.
4 6.10.2 Except where covered by applicable regulations, items a through h above shall be retained for a period of at least 5 y' ears and item i through q shall be retained for the life of the plant. A complete inventory of radioactive materials in possession shall be maintained current at all times.
1.
See paragraph N-415.2, ASME Section III, 1965 Edition.
Amendment No. 132, 138,149 BFN 6.0-31 Unit 1
1 I
l 6.11 PROCESS CONTROL PROGRAM (PCP) i
- 1. The PCP shall be approved by the Commission prior to implementation.
- 2. Changes to the PCP shall be submitted to the Commission in the snai-annual Radioactive Effluent Release Report for the period in which the change (s) was asde. This submittal shall contains a.
Sufficiently detailed information to totally support the change.
i L.
A determination that the change did not change the overall conformance of the solidified product to existing criteria.
6.12 0FFSITE DOSE CALCULATIONAL MANUAL (ODCM)
- 1. The ODCM shall be approved by the Commission prior to implemantation.
j
- 2. Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for'the period in which the change (s) was made. This submittal shall contain:
.\\
a.
Sufficiently detailed information to totally support the change.
I l
- 3. Changes to the ODCM shall become effective upon review and acceptance by P02C.
l I
BFN 6.0-32 Amendment No. 132, 138, 149 i
Unit 1 I
6.13 RADIOLOGICAL EFFLUENT MANUAL (REM)
- 1. The REM shall be approved by the Connaission prior to implementation.
- 3. Changes to the REM shall be approved by the Comunission prior to implementation.
I 3
l BFN 6.0-33 Amendment No. 132, 138, 149 Unit 1
Sa at:ty.
'o,,
UNITED STATES 8
NUCLEAR REGULATORY CC#MMISSION e
{
l WASHINGTON, D. C. 20068
%,...../
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.145 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedJune 17, 1988 as supplemented June 23, and June 24, 1988, comnlies 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 conformity with the application, the provisions of the Act, and the rules and regulations of,the Comission; 1
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 wil'1 be conducted in compliance with the Comission's regulations; i
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l l
l
s.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-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.145, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
)
I FOR THE NUCLEAR REGULATORY COMMISSION Sdu/C
~1 Suzanne istant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: June 30, 1988 t
e l
1
ATTACHkENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise 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 contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 6.0-1 6.0-1 6.0-2 6.0-2 6.0-3 6.0-3 6.0-4 6.0-4 f.0-5 6.0-5
- 6. 0- 6 6.0-6 0.0-7 6.0-7 6.0-8 6.0-8 6.0-9 6.0-9 6.0-10 6.0-10 6.0-11 6.0-11 6.0-12 6.0-12 I
6.0-13 6.0-13 6.0-14 6.0-14 6.0-15 6.0-15 6.0-16 6.0-16 6.0-17 6.0-17 6.0-18
- 6. 0. D' t
6.0-19 6.0-19 6.0-20 6.0-20 6.0-21 6.0-21 6.0-22 6.0-22 l
6.0-23 6.0-23 1
6.0-24 6.0-24 6.0-25 6.0-25 6.0-26 6.0-26 6.0-27 6.0-27 6.0-28 6.0-28 6.0-29 6.0-29 6.0-30 6.0-30 6.0-31 6.0-31 f
6.0-32 6.0-32 6.0-33 6.0-33 6.0-34 e
BrN TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responribility during his absence.
6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function.
A management directive to this effect, signed by the Site Director shall be reissued to all station -
personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 affsite and Onsite Oraanizations i
An onsite and offsite organization shall be established for unit operation and corporate management,.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication chall be j
established and defined from the highest managhment levels l
through intermediate levels to and including all operating I
organization positions. These ridatianships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities ana relationships, and job descriptior s for key personnti positions, or in equivalent forms of documentation. These j
requirements shall be documented in the rtAR and vill b9 updated in accordance with 10 CTR 50.71(e).
BrN 6.0-1 Amendment No. I34, 145 Unit 2
,-n-
.--.m-
6.2.1 (Cont'd)
- b. The Senior Vice President, Nuclear Power, shall have corporate responsibility for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the etaff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
- c. The Plant Manager shall be responsible for overall unit safe operation, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- d. The individuals who train the operating staff and those who carry '
out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 Plant Staff
- a. Shift manning requirements, shall as a minimum, be at described in Table 6.2.A and below.
- b. A licensed senior reactor operator shall be present at the site at l
all times when there is fuel in the reactor.
- c. A licensed reactor operater shall be J~ the control room whenever there is fuel in the reactor.
BFN 6.0-2 Amendment No. 134, 145 Unit 2 1
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6.2.2 (Cont.)
I s
d.
Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.
In addition, a person holding a senior F
/
operator license shall be in the pontrol room for that unit whenever I
it is in an operational mode other than cold shutdown or refueling.
4(
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3 A Health Physic.d Technician
- s'?p1ij be present at the facility at all
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timed when there is fuel in the reattord h
j f,
A ptdem holding a sentor operetor licente or a senior cperator
'!n i
license limirdd to fuel,'tandling, shall be pre,sent during alteration
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I of the core to directly supervise the activity and during this time shall not be assigned other nuties.
i s
g.
I site fire brigade or at least five munbek shall be taititained i
onsite at all tim s:.* 'The fire bricade shall not inclu'le the Shift t
, u FW ineer and the other members of the minimum shift crew necessary for safe shutdown of' the' unit, nor any p'ersonnel reqtsired for other essentialfunctionsduhingafireemergency.
\\
/
i AThe Health Ph si rechnicianandfirebrigadecomposItionmaybe less than the minimum requirements for a,detiod of tim'e not to
'[ exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided
'sim diate action is taken to fill the required positions.
s
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I 6.0-3 Amendment No. 734, 145 BFN Unit 2
/
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k
.i 4.
1 Table 6.2.A Minimum Shift Crew ReauirementsD Position Units in Operation Tyne of License L
l Q
l 2
3 d
l l
Senior Operr. tor
- 1 1
1 1
SRO i
Senior Operator 0
1 2
2 SRO l
Licensed Operators 3
3 3
3 RO or SRO Additions 1 Licensed Operatorse 0
1 2
2 kJ or SRO Assistant Unit Operators (AUO) 4 4
5 5
None I
1 Shift Technical Advisor (STA) 0 1
1 1
None Health Physics Technician 1
1 1
1 None Note for Table 6.2.A.
l
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l
(
i n.
A senior operator will be aosigned responsibility for overall plant operation at all times there is fuel in any unit.
b.
Except for the senior operator discussed in note "a",
the shift crew composition may be one less than the minimum requirements of Table 6.2. A t
for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate i
action is taken to restore the shift crew composition to v'i. thin'the minimum requirements of Table 6.2.A.
This provision does - t permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent, c.
One of the Additional Licensed Operators must be assigned to each control room vish an operating unit.
d.
The numbt:.! required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.
BFN 6.0-4 Amendment No. %34, 145 Unit 2
~
6.3 PLANT STAFF OUALIFICATIONS l
Qualifications of the Browns Ferry Nuclear Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI -
J N18.1, Selection and Training of Nuclear Power Plant Personnel, dated
)
March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.
=
6.4 TRAINING A retraining and replacement training program for 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 program shall be every two years.
6.5 PLANT REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITIEE (PORC) 1 l
FUNCTION The PORC shall function to advise the Plant Manager in all 6.5.1.1 a.
matters related to nuclear safety.
b.
This advisory function shall be performed by the PORC acting 1
in a formal meeting or by members acting individually without a formal meeting.
Amendment No. 134, 145 BFN 6.0-5 Unit 2
~
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
a.
Chairman:
Plant Manager Alternate Chairman:
Assistant to Plant Manager Alternate Chairman or Member: Technical Services Superintendent Member:
Unit Superintendents (3)
Member:
Maintenance Superintendent Member:
Quality Assurance Staff Supervisor Member:
Health Physics Supervisor b.
All alternate chairmen and alternate memberis shall be appointed in writing by the PORC chairman.
MEETING FREQUENCY 6.5.1.3 The PORC shall convene in a formal meeting at least once a month and as directed by the chairmen. Other PORC meetings may be requested by the chairmen or members as required.
BFN 6.0-6 Amendment No. IM,145 l
Unit 2 j
-n-
i 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 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.
- f' RESPONSIBILITIES l
6.5.1.6 The PORC shall be responsible for the activities listed below.
The PORC may delegate the performance of reviews, but will maintain cognizance over and responsibility for them, e.g.,
subcommittees.
l a.
Review of administrative procedures for che control of the technical and cross-disciplinary review of (1)'all
/
procedures required by Specification 6.8.1.1,',and changes thereto, (2) any other procedures and changes thereto determined by the Plant Manager to affect nuclear safety.
I b.
Review of the administrative procedures required by-Appendix A of Regulatory Guide 1.33, Revision 2,,
February 1978 and changes thereto.
c.
Review of emergency operating procedures and changes thereto.
1 I
d.
Review implementing procedures of the Radiological Emergency Plan and the Industrial Security Program.
Amendment No. %34, 14S BFN 6.0-7 i
Unit 2 l
l 1
~ - -
Review of'all proposed changes to the Technical e.
Specifications.
f.
Review of safety evaluation for proposed tests or experiments to be completed under the provisions of 10 CFR 50.59 9
3 Review 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.
- t i.
Review changes to the radwaste treatment systems.
J.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and disposition of the corrective action to prevent recurrence to the. Senior Vice President, Nuclear Powar, and to the Nuclear Safety Review Board.
I k.
Review of all safety evaluations for modifications to structures, systems or components that affect nuclear safety to verify that such actions did not conatitute aut unreviewed safety question as defined in 10 CFR 50.59, or requires a change to these Technical Specifications.
Amendment No. %34, 145 BFN 6.0-8 Unit 2 I
~
~
1.
Review of reportable events, unusual events, operating anomalies, and abnormal performance of plant equipment.
m.
Investigate reported or suspected incidents involving safety questions or violations of the Technical Specifications, n.
Review of unit operations to detect potential hazards to nuclear safety.
Items that may be included in this review are NRC inspection reports, QA audit, NSRB audit results, American Nuclear Insurer (ANI) inspection results, and significant carrective action reports (CARS).
o.
Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the.
Nuclear Safety Review Board.
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BFN 6.0-9 Amendment No. %34, 145 Unit 2
AUTHORITY 6.5.1.7 The PORC shall a.
Recommend to the Plant Manager in writing, approval, or disapproval of items considered under 6.5.1.6.a through i above.
1.
The recommendation shall be based on a majority vote of the PORC at a formal meeting.
2.
The recommendation shall be based on a unanimous vote of the PORC when the PORC members are acting individually.
3.
Edch member or alternate member shall have one vote.
b.
Purnish for consideracion a determination in writing with regard to whether or not each item considered under 6.5.1.6.f above constitutes an unreviewed safety question.
c.
Make recommendations to the Plant Manager in writing that action reviewed under 6.5.1.6.k above did not' constitute an unreviewed safety question.
d.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Director and the Nuclear SaTety Review Board of disagreements between the PORC and the Plant Manager.
However, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.
BFN 6.0-10 Amendment No. 134, 145 Unit 2
~
B i
RECORDS i
6.5.1.8 The PORC shall maintain written minutes of each PORC meeting including expedited meetings that, as a minimum, document the result of all PORC activities-performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Director and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION 6.5.2.1 The NSRB shall function to provide independant review and audit cognizance of designated activities in the areas of:
e.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy t
e.
Instrumentation and control j
f.
Radiological safety g.
Mechanical and electrical engineering, and h.
Quality assurancs practices COMPOSITION l
6.5.2.2 The NSRB shall be composed of at least five members, including the Chairman. Members of the NSRB may be from the Nuclear Power 1
(
or other TVA organizations, or external to TVA.
l 1
l Amendment No. Z34, 145 BFN 6.0-11 Unit 2
,, w W
QifALIFICATIONS 6.5.2.3 The Chairman, members, alternate members of the NSRB shall be appointed in writing by the Senior Vice President, Nuclear Power and shall have an academic degree in engineering or a physical science field, or ths equivalent; and in addition, shall have a minimum of 5 years technical experience in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized to provide expert advice as determined by the NstB.
KEETING FREQUENCY 6.5.2.5 The NSRB shall meet at least once per six months.
QUORUM I
6.5.2.6 The minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these techn'ical
~
specifications shall consist of more than half of the NSRB membership or at least five members, whichever is greater. The quorum shall include the Chairman or his appointed alternate and the NSRB members including appointed alternate members meeting the requirements of 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
Amendment No. %34, 145 BFN 6.0-12 Unit 2
~~ --
REVIEW 6.5.2.7 The NSRB shall review:
a.
The' safety evaluations for:
(1) changes to procedures, equipment or systems, ano (2) tests or experiments compler.ed under the provision of Section 50.59, 10 CFR,ltoverifythat such actions did not constitute an unreviewed safety 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.
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.
/
l f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect noclear safety.
g.
All Reportable Events h.
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 i.
Reports and meeting minutes of'the PORC.
BFN 6.0-13 Amendment No. 134, 145 Unit 2
-r
. -.,, -.. = - -.,
-e
a AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The nerformance, training and qualifications of the entire plant staff at least once per'12 months.
c.
The results of actions taken to correct deficiencies occurring in site equipment, structures, systems or method
- of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria' of Appendix B, 10 CFR Part 50, at least once per 24 months.
i e.
The Site Radiological Emergency Plan and impismenting procedures at least once every 12 months.
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.
i h.
The fire protection programmatic controls including the implementing procedures at least once per 24 months.
BFN 6.0-14 Amendment No. /ygg//724,145 Unit 2
1.
An independent fire protection and loss prevention program' inspection and audit shall be performed annually utilizing either qualified offsite license personnel or an outside fire protection firm.
J.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outsida -
qualified fire consultant at intervals no greater than 3 years.
k.
The Radiological Environmental Monitoring program and the results thereof at least once per 12 months.
1.
The performance of activities required by the Quality i
Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977, or Regulatory Guide 1.21, Rev.1,1974, and Regulatory Guide 4.1, 1975, at least once every 12 months.
i i
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The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CFR 73.40(d); at least once every 12 months.
l n.
The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
o.
The Process Control Program and implementing procedures for solidification of wet radioactive wastes at least once per 24 months.
p.
The Radiological Effluent Manual and implementing procedures at least once per 12 months.
BFN 6.0-15 Amendment No. 228//%34, 145 Unit 2
AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Senior Vice President, Nuclear Power on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Reports of activities shall be prepared, approved, and distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
c.
Audit reports encompassed by Specification 6.5.'2.8 abovev shall be forwarded to the Senior Vice President, Nuclear Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.
i BFN 6.0-16 Amendment No. 12$//135, 145 j
Unit 2
6.5.3 TECHNICAL REVIEW AND APPROVAL OF PROCEDURES ACTIVITIES i
6.5.3.1 Procedures required by Technical Specification 6.8.1.1 and other procedures which affect plant nuclear safety, and changes (other than editorial or typographical changes) therer', shall be prepared, reviewed and approved. Each procedure or procedure change shall be reviewed by an individual other than the preparer.
The reviewer may be from the same organization or from a different organization.
Procedures other than Site Director Standard Practices will be approved by the responsible Section Supervisor, or applicable Plant Superintendent.
6.5.3.2 Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.
Proposed I
modifications to plant nuclear safety-related tructurec, systems and components shall be approved by the Plant Manager, prior to implementation.
BFN 6.0-17 Amendment NO. %25//Z34,145 i
l Unit 2 1
6.5.3.3 Individuals responsible for reviews performed in accordance' l
with 6.5.3.1 shall be members of the site supervisory staff previously designated by the Plant Manager.
Each such review shall include a determination of whether or not' additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by review personnel of the appropriate discipline.
6.5.3.4 The Plant Manager shall approve all administrative procedures requiring PORC review prior to implementation.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.' The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Site Director.
Amendment No. 125//134, 145 BFN 6.0-18 Unit 2 9
9
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
i a.
The NRC Operations Center shall be notified by telephone as soon as possible and 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 VicePresident,NuclearPowerandtheNSRNshallbenotified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit Violation Report shall be prepared.
The l
report shall be reviewed by the PORC.
This report shall l
describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, syst'ms, or structures, and (3) corr,ective e
action taken to prevent recurrence.
1 c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB, and the Senior Vice Presid'nt, Nuclear e
Power within 14 days of the violation.
d.
Critical operation of the unit shall not be res'uned until j
authorized by the Commission.
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. Amendment No./y28//134, 145 l
BFN 6.0-19 l
Unit 2 l
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6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 PROCEDURES 6.8.1.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978, b.
Limitations on the amount of overtime worked by individuals performing safety-related functions in accordance with NRC Policy statement on working hours (Generic Letter No. 82-12).
c.
Surveillance and test activities of safety-related equipment.
d.
Security pJan implementation.
e.
Emergency plan implementation.
f.
Fire Protection Program implementation. ',
g.
Radiological Effluent Manual implementing procedures.
h.
Process Control Program (PCP).
i.
Offsite Dose Calculation Manual.
J.
Administrative procedures which control technical and cross-disciplinary review.
BFN 6.0-20 Amendment No. 125//134, 145 Unit 2 4
U 6.8.1.2 Each administrative procedure required by Section 6.8.1.1.a.
shall be reviewed by PORC and all other procedures required by Section 6.8.1.1.a. shall be reviewed in accordance with Section 6.5.3.
6.8.1.3 Temporary changes to procedures of Specification 6.8.1.1 may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator License on the unit affected; c.
The change is documented, reviewed by the PORC and approved by the Plant Manager within 14 days of implementation, for changes in administrative procedures requiring PORC review.
d.
The change 10 documented, reviewed per, Specification 6.5.3, and approved by the responsible group section supervisor within 14 days of implementation, for changes to procedures other than administrative procedures.
O DRILLS 6.8.2 Drills on actions to be taken under emergency conditions involving release of radioactivity are specified in the Radiological Emergency Plan and shall be conducted annually.
Annual drills shall also be conducted on the actions to be taken following failures of safety-related systens or components.
Amendment No. 728//734, 145 BFN 6.0-21 Unit 2
u RADIATION C0KIROL PROCEDURES 6.8.3 Radiation Control Procedures shall be maintained and made available to all station personnel.
These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the "control device" or "alarm signal" required by paragraph 20.203 (c) of 10 CFR 20.
6.8.3.1 Each high radiation area in which the intensity of radiation is greater than 100 mrea/hr but less than or equal to 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlleg by requiring issuance of a Radiological Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more
~
of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
I b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made, after the dose rate level in the area has been establishad and personnel have been made knowledgeable of them, c.
An individual qualified in radiation protection precedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing BFN 60-22 Amendment No 128, %34, 145 Unit 2 j
t pcsitive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by,the facility Health Physicist in the Radiological Work Permit.
6.8.3.2 Each high radiation area in which the intensity of radiation is greater than 1,000 aren/hr shall be subject to the provisions of (1) above; and, in addition, access *.o the source and/or area shall be secured by lock (s). The key (s) shall be under the administrative control of the shift engineer.
In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for permanent access control.
e
- Health Physics personnel, or personnel escorted by Health Physics personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation' protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
QUALITY ASSURANCE PROCEDURES - EFFIMENT AND ENVIRONMENTAL MONITORING 6.8.4 Quality Assurance procedures shall be established, implemented, and maintained for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, June 1974 and Regulatory Guide 4.1, Rev.1, April 1975 or Regulatory Guide 4.15, Dec. 1977.
BFN 6.0-23 Amendment tio. 128//134, 145 Unit 2
,m~-
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the Regional Office of NRC, unless otherwise noted.
6.9.1.1 STARTUP REPORT
~
a.
A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with d'esign predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
BFN 6.0-24 Amendment No. %35//%34, 145 Unit 2
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b.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
IfIthe Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and ; resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
6.9.1.2 ANNUAL OPERATING REPORT
- a.
A tabulation o'n an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associaced man rem exposure according to' work and job functions, **e.g., reactor operations and surv'eillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), vaste processing, and refueling.
The dose assignment to various duty' functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling l'ess than 20%
of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific o
major work functions.
b.
Any mainsteam relief valve that opens in response to reaching its setpoint or due to operator action to control reactor pressure shall be reported.
- A single submittal may be made for a multiple unit station.
- This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
BFN 6.0-25 Amendment No. I25//IJ4, 145 Unit 2, i
E 6.9.1.3 MONTHLY OPERATING REPORT Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, to be submitted no later than the fifteenth of each month following the calendar month covered by the report. A narrative summary of operating experience shall be submitted in the above schedule.
6.9.1.4 REPORTABLE EVENTS Reportable events, including corrective actions and measures to prevent re-occurrence, shall be reported to the NRC in accordance with Section 50.73 to 10 CFR 50.
6.9.1.5 RADI0 ACTIVE EFFLUENT RELEASE REPORT Delet xi (See REM section F-2) 6.9.1.6 SOURCE TESTS Results of required leak tests performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
BFN 6.0-26 Amendment No. %25//134, 145 Unit 2
6.9.2 SPECIAL REPORTS Reports on the following areas shall be submitted in writing to the Director of Regional Office of Inspection and Enforceme.nt:
1.
Fatigue Usage 6.10.1.q Annual Operating Report 2.
Relief Valve Tailpipe 3.2.F Within 30 days after inoper-ability of thermocouple and acoustic monitor on l
one valve.
3.
Seismic Instrumentation 3.2.J.3
.Within 10 days; Inoperability after 30 days of inoperability.
4.
Meteorological Monitoring 3.2.I.2 Within 10 days Instrumentation after 7 days of Incperability inope'rability.
5.
Primary Containment 4.7.A.2 Within 90 days Integrated Leak Rate of completion of Testing each test.
6.
Data shall be retrieved from all seismic instruments actuated during a seismic event and. analyzed to determine the magnitude of the vibratory. ground motion. A Special BFN 6.0-27 Amendment No./I28//IJ4, 145 Unit 2
,.---____.,e
Report shall be submitted within 10 dcyo efter th3 Gv::nt describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.
7.
Secondary Containment 4.7.C.
Within 90 days Leak Rate Testing
- of completion of each test.
P Uigh 3ange Primary 3.2.F Within 7 days after 7 days of coatainment Radiation inoperability.
Monitors 9.
High-Range Gasesous 3.2.F Within 7 days after 7 days of Effluent Radiation inoperability.
Monitors i
- Each integrated leak rate test of the secondary containment shall be the subject of.a summary technical report. This report should includs data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor buildins pressure, and emergency ventilation The report shall also include analyses and interpretations of flow rate.
these date.which demonstrate compliance with the specified leak ' rate limits.
6.0-28 Amendment No.I28//I34, 145 BTN Unit 2
6.10 STATION OPERATING RECORDS AND RETENTION 6.10.1 Records and/or logs shall be kept in a manner convenient for review an indicated below:
All normal plant operation including such items as power a.
level, fuel expcsure, and shutdowns b.
Principal maintenance activities c.
Reportable Events d.
Checks, inspections, tests, and cal.tbrets'.ons of components and systems, including such diverse items as source leakage i e.
Reviews of changes made to the procedures or equipment or reviews of tests and expericents to comply with 10 CFR 50.59 f.
Radioactive shipments g.
Test results in units of microcuries for lear tests performed pursuant to Specification 3.8.D Amendment No//120//134, 145 BFN 6.0-29 Unit 2
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.l h.
Record of ann'tal physical inventory verifying accountability of sources on record 1.
Gaseous and liquid radioactive vaste released to the environs
- j. Offsite environmental monitoring surveys k.
Fuel inventories and transfers 1.
Plant radiation and contamination surveys m.
Radiation exposures for all plant personnel n.
Updat*v, :of
.cted, and as-built drawings of the plant 9.
Reactor coolant system inservice inspection p.
Minutes of meetings of the NSRB q.
Design fatigue usat.e evaluation Monitoring and recording requirements below will be met for various portions of the reactor coolant pressure boundary (RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section III was performed for the conditions defined in the des'ign specificacion.
In this plant, the applicable codes require fatigue usage evaluation for the reactor pressure vessel only. The locations to be monitored shall be:
1.
The feedvater nozzles 2.
The shell at or near the waterline 3.
';he flange studs Amendment No. %28//134, 145 BFN 6.0-30 Unit 2
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Transients that oedt duriryr pir.se operationd will he
+
1 reviewed and a cumulative fatigue, usa;ie factor
\\.i determined.
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,j For transients which are more seveth han t1Meransients'
/
i evaluated in the stre.$ report, cou WEtigue unge calculations will Le made and tabulated separately.
i 4
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/3 In the annual operating rerot.t, the retigue u%ge fae::or s
s determined for the transiegts idefMed above shal.1 be s
added and a cumulative fttigue usage factor to drite i
/-
shall be reported. When, the cur:lativ,d usage factor reaches a value of 1.0, au bmeYvice inadection shall be f
included.for the specific location at the next schedu1 4 inspection (3-1/3-year interval) period and 3-1/3-year intervals thereatter, and a subsequent evalv'ation performed in'acrordance with the rules of ASME Section XI Code if ar.y flaw indications are detected. The results of the evaluation call be submitted in a
/
Special Report for reviev' hy the Comunission.
i 5.10.2 Except where covered by applicable regulations, items a~through h above shall be retained for a period of M least. 5 ye'ars and item i through q shall be retained for the life of the plast. A complete inventory or radioactive materials in ponsession shall be maintained current at eil times.
- 1.. See paragraph N-415.lJ, ASME Section III, 1965 Edition.
BrN 6.0-31 Amendment No./125//134, 145 Unit 2 4
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6.11 PROCEMS C0!rfROL PROGRAM (PCP)
- 1. The PCP shall be approved by the Commission prior to implementation.
- 2. Changes to the PCP shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
a.
Sufficiently detailed information to totally support the change.
b.
A determination that the change did not change the overall conformance of the rolidified prodret to existing criteria.
6.12 0FFSITE DOSE CALCULATIONAL MANUAL (ODCM)
- 1. The ODCM shall be cpproved by the Commission prior to implementation.
- 2. Changes to the ODCM shall be submitted to the Comunis'sion in the semi-annual Radioactiva Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
a.,
Sufficiently detailed information to totally support the change.
BFN 6.0-32 Amendment No. 128//J3,4, 145 Unit 2
6.13 RADIOLOGICAL EITLffENT MANUAL (REM)
- 1. The REM shall be approved by the Consiission prior to implementation.
- 3. Changes to the REM shall be approved by the Commission prior to implementation.
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BFN 6.0-33 Amendment tb.128//JM,145 Unit 2 l
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- - - -, - - - - - - -, - - - -., -,,,,, - ~ -
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o UNITED ST TES g
8 NUCLEAR REGULATORY COMMISSION o
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wAsmNGTON. D. C. 20665
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TEjNESSEEVALLEYAUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. OPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 17, 1988 as supplemented June 23, and June 24, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1988, complies with the standards and re
~
, and the Comission'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 of the Comission; f
l C.
There is reasonable assurance (1) that the activities "cuthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wil'1 be conducted in compliance with the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in,accordence with 10 C'FR Part 51 c mission's regulations and all applicable requirements have of the o
been satisfied.
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2, Accordingly, the license is amended by change: to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C (2) of Facility Operating License No. OPR-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.120, are hereey incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzanne Black, Assistant Director for Projects TVA Projects Division :
Office of Special Projects Attachment.
Changes to the Technical Specifications Date of Issuance:
June 30, 1988 i
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ATTACHMENT TO LICENSE AMENOMENT NO. 145 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 Revise 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 contain marginal lines indicating the area of change. Overleaf.pages* are provided to maintain document completeness.
REMOVE.
INSERT 6.0-1 6.0-1 6.0-2 6.0-2 s
6.0-3 6.0-3 6.0-4 6.0-4 6.0-5 6.0-5 6.0-6 6.0-6 6.0-7 6.0-7 6.0-8 6.0-8 6.0-9 6.0-9 6.0-10 6.0-10 6.0-11 6.0-11 6.0-12 6.0-12 6.0-13 6.0-13 6.0-14 6.0-14 6.0-15 6.0-15 6.0-16 6.0-16 6.0-17 6.0-17 6.0-18 6.0-18 6.0-19 6.0-19 6.0-20 6.0-20 6.0-21 6.0-21 6.0-22 6.0-22 6.0-23 6.0-23 6.0-24 6.0-24 6.0-25 6.0-25 6.0-26 6.0-26 6.0-27 6.0-27 6.0-28 6.0-28 l
6.0-29 6.0-29 6.0-30 6.0-30 l
6.0-31 6.0-31 l
6.0-32 6.0-32 6.0-33 6.0-33 6.0-34 t
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i BFN TECHNICAL SPECIFICATIONS 6.0 ADMINISTRATIVE CONTROLS 6.0 ADMINISTRATIV3 CONTROLS 6.1 RESPONSIBILITY l
t 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate'in writing the succession to this responsibility during his absence.
6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function. A management directive to this effect, signed by the Site Director shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 Offsite and Onsite Oraanizations An onsite and offsite organization shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
I
- a. Lines of authority, responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented I
and updated, as appropriate, in the form of organizational charts, functicnal descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR and will be updated in accordance with 10 CFR 50.71(e).
Amendment No. 109, 120 BFN 6.0-1 Unit 3
6.2.1 (Cont'd)
~
- b. The Senior Vice President, Nuclear Power, shall have corporate responsibility for overall plant nuclear safety.' This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
- c. The Plant Manager shall be responsible for overa'11 unit safe operation, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- d. The individuals who train the operating staff and those who carry '
out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure cheir independence from operating pressures.
6.2.2 Plant Staff
- a. Shift manning requirements, shall as a minimum, be as described in Table 6.2.A and below.
- b. A licensed senior reactor operator shall be present at the site at al3 times when there is fuel in the reactor.
- c. A licensed reactor operator shall be in the control room whenever there is fuel in the reactor.
BFN-Unit 3 6.0-2 Amendment No. 109, 120 o
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6.2.2 (Cont.)
d.
Twolicensedreactoroperatorsshallbejinthecontrolroomduring any cold startups, while shutting down the reactor, and during recovery from unit trip.
In addition, a person holding a senior operator license shall be in the control room for that unit whenever it is in an operational mode other than cold shutdown or refueling.
e.
A Health Physics Technician
- shall be present at the facility at all times when there is fuel in the reactor.
f.
A person holding a senior operator license or a senior operator license limited to fuel handling, shall be pre'sent during alteration of the core to directly supervise tIhe activity and during this time shall net be assigned other duties.
s.
A site fire brigado of at least five members shall be maintained onsite at all times.* The fire brigade shall not include the Shift Engineer and the other members of the minimum shift crew I necessary for safe shutdown of the unit, nor any per'sonnel required for other essential functions during a fire, emergency, e
- The Health Physics Technician and fir'e brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
BFN 6.0-3 Amendment No. 109, 120 Unit 3 i
Table 6.2.A Minintan Shift Crew ReauirementaD Position Units in Operation Tyne of License Q
1 ad 2
Senior Operator
- 1 1
1 1
SRO Senior Operator 0
1 2
2 SR0 Licensed Operators 3
3 3
3 RO or SRO Additional Licensed Operatorse 0
1 2
2 RO or SRO Assistant Unit Operators (AUO) 4 4
5 5
None Shift Technical Advisor (STA) 0 1
1 1
None Health Physics Technician 1-1 1
1 None Note for Table 6.2.A t
a.
A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit.
b.
Except for the senior operator discussed in note "a",
the shift crew composition may be one less than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided im' ediate m
netion is taken to restore the shift crew composition to vithin the minimum requirements of Table 6.2.A.
This provision does no,t permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
c.
One of the Additional Licensed Operators must be assigned to each control room with an operating unit.
1 d.
The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.
BFN 6.0-4 Amendment No. 109, 120 Unit 3
h.
6.3 PLANT STAFF OUALIFICATIONS Qualifications of the Browns Ferry Nuclear Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI -
N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.
6.4 TRAINING i
A retraining and replacement training program for 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 program shall be every two yeare.
6.5 ELANT REVIEW AND AUDIT j
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6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC) l FUNCTION l
6.5.1.1 a.
The PORC shall function to advise the Plant Manager.in all matters related to nuclear safety.
(
b.
This advisory function shall be performed by the PORC acP.ing in s. formal meeting or by members acting individually without a formal meeting.
BFN 6.0-5 Amendment No. 109, 120 Unit 3
\\
COMPCSITION 6.5.1.2 The PORC shall be composed of the:
a.
Chairman:
Plant Manager Alternate Chairman:
Assistant to Plant Manager Alternate Chairman or Member: Technical Services Superintendent Member:
Unit Superintendents (3)
Member:
Maintenance Superintendent Member:
Quality Assurance Staff Supervisor Member:
Health Physics Supervisor b.
All alternate chairmen and alternate members'shall be P
appointed in writing by the PORC chairman.
MEETINC FREQUENCY a
6.5.1.3 T'e PORC shall convene in a formal meeting at least,once a a
month and as directed by the chairman.
Other PORC meetings may be requested by the chairmen or members as required.
bFN 6.0-6 Amendment No. 109, 120 1
Unit 3
--___.m..,
~-
6.5.1.4 For expeditsd 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 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.
-e RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.
The PORC may delegate the performance of reviews, but will maintain cognizance over and responsibility for them, e.g.,
subcommittees.
l, a.
Review of administrative procedures for the control of the technical and cross-disciplinary review of (1) all l
procedures required by Specification 6.8.1.1, and changes f
thereto, (2) any other procedures and changes thereto l
determined by the Plant Manager to affect nucle'ar safety.
b.
Review of the administrative procedures required by
[
Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and changes thereto.
I c.
Review of emergency operating procedures and changes thereto.
i d.
Review implementing procedures of the Radiological Emergency i
Plan and the Industrial Security Program.
l BFN 6.0-7 Amendment No. 109, 120 Unit 3
~
e a
e.
Review of all proposed changes to the Technical Specifications.
f.
Review of safety evaluation for proposed tests or experiments to be completed undet the provisions of 10 CFR 50.59 g.
Review proposed changes to the Radiological Effluent Manual.
h.
Review adequacy of the Process Control Program and 0"faite Lume Calculation Manual at least once every 24 months.
1.
Review changes to the radweste treatment systems.
J.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendation, and disposition of the corrective action to prevent recurrence to the Senior Vice President, Nuclear Power, and to the Nuclear Safety Review Board.
k.
Review of all safety evaluations for modifications to structures, systems or components that affect duelear safety to verify that such actions did not constitute an unreviewed safety question as defined in 10 CPR 50.59, or requires a change to these Technical Specifications.
BFN 6.0-8 Amendment No. 109, 120 Unit 3
=
1.
Review of reportable events, unusual events, ope. rating anomalies, and abnormal performance of plant equipment.
Investigate reported or suspected incidents involving safety m.
questions or violations of the Technical Specifications.
n.
Review of unit operations to detect potential hazards to nuclear safety.
Items that may be included in this review are NRC inspection reports, QA audit, NSRB audit results, American Nuclear Insurer (ANI) inspection results, and significant corrective action reports (CARS).
o.
Performance of special reviews, investigations, or analysis, and report thereon as requested by the Plant Manager or the '
Nuclear Safety Review Board.
t t
4 f
A**^ #*"
BFN 6.0-9 Unit 3 l
_y
_,_m.-.
O AUTHORITY 6.5.1.7 The PORC shall:
Recommend to the Plant Manager in writing, approval, or a.
disapproval of items considered under 6.5.1.6.a through I
i above.
1.
The recommendation shall be based on a majority vote of the PORC at a formal meeting.
2.
The recommendation shall be based on a unanimous vote of the PORC when the PORC members are acting individually.
3.
Each member or alternate member shall have one vote, b.
Purnish for consideration a determination in writing with regerd to whether or not each item considered under 6.5.1.6.f above constitutes an unreviewed safety question.
c.
Make recommendations to the Plant Manager in wr'iting that action reviewed under 6.5.1.6.k above did not' constitute an unreviewed safety question.
d.
Provide written notification within 24 hour: to the Site Dircctor and the Nuclear Safety Review Board of disagreements betysea the PORC and the Plant Manager.
However, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.
BFN 6.0-10 Amendment No. 709, 120 l
Unit 3 9
n
4 RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting including expedited meetings that, as a minimum, document the result of all PORC activities performed under the ' esponsibility r
and authority provisions of these technical specifications.
Copies shall be provided to the Site Director and the Nuclear Safety Review Board.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
NNCTION 6.5.2.1 The NSRB shall function to provide independent review and audit cognizance of designated activities in the areas of:
i a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrumentation and control f.
Radiological safety s.
Mechanical and electrical engineering, and
~
h.
Quality assurance practices COMPOSITION 6.5.2.2 The NSRB shall be composed of at least five members, including the Chairman. Members of the NSRB may be from the Nuclear Power or other TVA organizations, or external to TVA.
BFN 6.0-11 Amendment No.109, 120 Unit 3
..m.
QUALIFICATIONS 6.5.2.3 The Chairman, members, alternate members of the NSRB shall be appointed in writing by the Senior Vice President, Nuclear Power and shall have an academic degree in engineering or a physical science field, or the equivalent; and in addition, shall have a minimum of 5 years technical experience in one or more areas given in 6.5.2.1.
No more than two alternates shall participate as voting members in NSRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized to provide expert advice as determined by the NSRB.
MEETING TREQUENCY 6.5.2.5 The NSRB shall meet at least once per six months.
QUORUM 6.5.2.6 The minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shall consist of more than half of the NSRB membership or at least five members, whichever is greater.
The quorum shall include the Chairman or his appointed alternate and the NSRB members including appointed alternate members meeting the requirements of 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
BFN 6.0-12 Amendment No. 109, 120 Unit 3 9
4 REVIEW 6.5.2.7 The NSRB shall reviews a.
The safety evaluations fort (1) changes to procedures, equipment or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
- b., Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Cection 50.59, 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.
P e.
Violations of Codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Sagnificant oparating abnormalitics cr deviations from normal and expected performance of plant equipe'nt that e
affect nuclear safety.
g.
All Reportable Events h.
All Je:ognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or couponents that could affect nuclear safety; r.nd 1.
Reports and meeting minutes of the PORC.
'l 6.0-13 Amendment 109/ 120 p_
yn
,,g g
en---
AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass a.
The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire plant staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in site equipment, structures, systems or method
- of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months.
I e.
The Site Radiological Emergency Plan and implementing procedures at least once every 12 months.
/
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 including the implementing procedures at least once per 24 months.
l
]
BFN 6.0-14 Amendment No. 109, 120 i
Unit 3
1.
An independent fire protection and loss prevention program
- inspection and audit shall be performed annually utilizing either qualified offsite license personnel or an outside fire protection firm.
I
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
l k.
The Radiological Environmental Monitoring program and the results thereof at least once per 12 months.
1.
The performance of activities required by the Quality Assurance Program to meet the critehia of Regulatory Guide j
4.15, December 1977, or Regulatory Guide 1.21, Rev.1,1974, and Regulatory Guide 4.1, 1975, at least once'every 12 months.
m.
The performance of activities required by the Safeguards Contingency Plan to meet the criteria of 10 CTR 73.40(d) at least once every 12 months.
The Offsite Dose Calculation Manual and implene'nting n.
procedures at least once per 24 months.
o.
The Process Control Program and implementing procedures for solidification of wet radioactive vastes at least once per 24 months.
p.
The Radiological Effluent Manual and implementing procedures l
at least once per 12 months.
l I
BFN 6.0-15 Amendment No. 109/ 120 Unit 3
AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Senior Vice President, Nuclear Power on those areas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Reports of activities shall be prepared, approved, and distributed as indicated below:
Minutes of each NSRB meeting shall be prepared, approved and a.
forwarded to the Senior Vice President, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
Audit reports encompassed by Specification 6.5.2.8 above,.
c.
shall be forwarded to the Senior Vice President, Nuclear Power and to the management positions responsib'le for the areas audited within 30 days after completion of the audit.
BFN 6.0-16 Amendment No. 109, 120 Unit 3
6.5.3 TECHNICAL REVIEW AND APPROVAL OF PROCEDURES ACTIVITIES 6.5.3.1 Procedures required by Technical Specification 6.8.1.1 and other procedares which affect plant nuclear safety, and
. changes (other than editorial or typographica'l changes) thereto, shall be prepared, reviewed and approved.
Each
' procedure or procedure change shall be reviewed by an individual other than the preparer. The reviewer may be from the same organization or from a different organization. Procedures other than Site Director Standard Practices will be approved by the responsible Section:
Supervisor, or applicable Plant Superintendent.
6.5.3.2 Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Plant Manager.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who say be from the same organization as the individual / group which designed the modification.
Proposed modifications to plant nuclear safety-related s'tructures, systems and components shall be approved by the Plant Manager, prior to implementation.
703//I09, 120 BFN 6.0-17 Unit 3 n.,
~
,_n.,n,
6.5.3.3 Individuals responsible for reviews performed in accordance' with 6.5.3.1 shall be members of the site supervisory staff previously designated by the Plant Manager. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed neccesary, such review shall be perfermed by review f
personnel of the apprcpriate discipline.
6.5.3.4 The Plant Manager shall approve all adminictrative procedures requiring PORC review prior to implementation.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Site Director.
4 LFN 6.0-18 Amendment No. 103//I09, 120 Unit 3 l
e
o 6.7 SAFETT LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Limit VTolation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) Sffects of the violation upon facility components, systems, or structures, and (3) corrective 6
action taken to preient recurrence.
c.
The Safety Limit Violation Report shall be submitted to the Commission, the NSRB, and the Senior Vice President, Nuclear Power within 14 days of the violation, j
d.
Critical operation of the unit shall not be resume'd until authorized by the Commission.
i Amendment No. 1g3//109, 120 BFN 6.0-19 Unit 3
...----.c c--
g 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS 6.8.1 PROCEDURES 6.8.1.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Limitations un the amount of overtime worked by
~
individuals performing safety-related functions in accordaace with NRC Policy statement on working hours (Generic Letter No. 82-12).
c.
Surveillance and test activities of safety-related equipment.
d.
Security plan implementation.
e.
Emergency plan implementation.
f.
Fire Protection Program implementation.
g.
Radiological Effluent Manual implementing procedures, h.
Process Control Program (PCP).
i.
Offsite Dose Calculation Manual.
J.
Administrative procedures which control technical and cross-disciplinary review.
BFN 6.0-20 Amendment 103//IO9, 120 Unit 3
6.8.1.2 Each administrative procedure required by Section 6.6.1.1.a.
shall be reviewed by PORC and all other procedtres required by Section 6.8.1.1.a. shall be reviewed in accordance with' Section 6.5.3.
6.8.1.3 Temporary changes to procedures of Specificatf on 6.8.1.1 eay be made provided:
a.
The intent of the original procedure is not altered; b.
The change As approved by two membera of the plant management staff, at least one of whom holds a Senior Operator License sn the unit affected; sg-c.
The change is documented, reviewed by the PORC and approved by the Plant Manager within 14 days of implementation, for changes in administrative procedures requiring PORC review.
d.
The change is documented, revi'eved per Specificacion 6.5.3, and approved by the responsible group section l
superviser within 14 days of impiecentation, for changes to procedures other ths.n administrative probedures.
f i
D2 ILLS 6.8.2 Drills on actions to be takta ander emergency conditionn involving release of radioactivity are specified in the Radiological Emergency Plan and shall be conducted annually. Annur.1 d;.* ills shall also be conducted on the j
actions to be taken following failures of safety-related systems or components.
l l
l BFN 6.0-21 crendment No. 203/209, 120 Unit 3 l
l l
RADIATION CONTROL PROCEDURES I
6.8.3 Radiation Control Procedures shall be maintained and made available to all station personnel. These procedures shall show permissible radiation exposure and shall be consistent 1
with the requirements of 10 CFR 20.
This radiation i
protection program shall be organized to meet the requirements of 10 CFR 20 except in lie
,f the "control device" or "alarm signal" required by paragraph'20.203 (c) of 10 CFR 20.
l 6.8.3.1 Each high radiation area in which the intensity of radiation is greater than 100 mrea/hr but lese than or equal to 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiological Work Permit.* Any ;
indivfdual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation r.onitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the Area and
.larms when a preset integrated dose is rec'cived.
Entry sto such areas with this monitoring device may be made after the dose rate level in the area has been established and personne1 have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities BFN 6.0-22 Amendment No. Ip9//II0, 120 Unit 3 L
7
,l
/
i g
i 1
)
within the area and shall perform pedodic radiation I
aurvaillance at the frequency specified by tha facility i(ealth Physicist.in the Radiological Work Permit.
1
/
6.8.3.2 Each high radiation area in which the intensity of radiation is greater than 1,000 mrea/hr shall be subjget ito the provisions of (1)above;and,inadd'ition,accesstothesourceand/brarea 9
shall be secured by lock (s). The key (s) shall be under the administrative control oI the shift engineer.
In the case cf a bigh radiation ares established for c. period of 30 days or less, directsurveillancetopreventunauthorizedentrymaybe
/
substituted for permanent access contro7.,
Health Physics personnaik or personnel escorted by Health 6
Thysics personnel.,in actrordance with approved emergeticy I
r p;ocedures, shall be errapt from the RWP issuance requirement'
./
dur;5ng the performanca of their assigned radiati'on protection dutier, provided they comply with. approved radiation protection precedt.res for entry into high radiatiote areas.
/
l
,)
i QUALITY ASSURANCE PROGEDdRFS - EFFLUENT AND ENVIRONMENTAL MONITORING l
ll l
6.8.4 Quality Asw eance procedures shall be established, imp 1'emented, and maintained for effluent and environmental monitoring, using tue guidance in Regulatory Guide 1.21, Rev. 1, June 1974 and Regulatory Guide 4.1, Rev. 1, April 1975 or Regulatory Guide 4.15, Dec. 1977..
/
/
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/
/
1 l
r l
BFh 6.0-23 Amendment No. 103//109, 120 Unit 3 s'
i 1
l
,..~..,[
e 6.9 REPORTING REQUIRENINTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the Regional Office of NRC, unless otherwise noted, l
6.9.1.1 STARTUP REPORT a.
A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a =
l planned increase in power level, (3) installation of fuel l
that has a different dasign or has been manufactured by a l
different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall. address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test Program and a comparison of these values with d' sign e
predictions and specifications. Any corrective' actions that were required to obtain satisfactory operation shall also be i
described: Any additional specific details required in license conditions based on other commitments shall be included in this report.
l l
BFN 6.0-24 Amendment No. Ig3//109, 120 Unit 3
O b.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months followirg initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at lesst every three months until all three events have been completed.
6.9.1.2 ANNUAL OPERATING REPORT
- a.
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) i receiving exposures greater than 100 mrem /yr and their associated man rem arposure according to work and job functions, **e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), vaste processing, and l
refueling.
The dose assignment to various duty functions
(
may be estimates based on pocket dosimeter, TLD, or film; I
badge measurements.
Small exposures totaling *1ess than 20%
of the individual total dose need not be accounted fer.
In the aggregate, at least 80% of the total whole ' body dose received from external sources shall be assigned to specific major work functions.
b.
Any mainsteam relief valve that opens in response to reaching its setpoint or due to operator action to control reactor pressure shall be reported.
l
- A single submittal may be made for a multiple unit station.
l l
- This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
BFN 6.0-25
- mendment No. 103//709, 120 Unit 3
e 6.9.1.3 MONTHLY f /ERATING REPORT Routine reports of operating statictics and shutdown experience shall be submitted on a monthly basis to'the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission,
-Washington, D.C. 20555, with a copy to the Regional Office, to be submitted no later than the fifteenth of each month following the calendar month c' wared by the report.
A narrative summary of operating experience shcIl be submitte'd in the above schedule.
6.9.1.4 REPORTABLE EVENTS Reportable events, including corrective actions and measures to=
prevent re-occurrence, shall be reported to the NRC in accordance with Section 50.73 to 10 CFR 50.
6.9.1.5 RADIOACTIVE ErFLUENT RELEASE REPORT Deleted (See REM section F-2)
E 6.9.1.6 SOURCE TESTS Results of required leak testa performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
BFN 6.0-26 Amendment No. IQ3//JO9, 120 Unit 3 e
v--
3 e
6.9.2 SPECIAL REPORTS Reports on the following areas shall be submitted in writing to the Director of Regional Offi'ce of Inspection and Enforcement:
1.
Fatigue Usage l
6.10.1.q Annual Operating Report 2.
Relief Valve Tailpipe 3.2.F Within 30 days after inoper-ability of thermocouple and acoustic i
monitor on one valve.
3.
Seismic Instrumentation 3.2.J.3 Within.10 days Inoperability after 30 days of inoperability.
i 4.
Meteorological Monitoring 3.2.I.2 Within'10 days I
Instrumentation afte'r 7 days of Inoperability inoperability.
5.
Primary Containment 4.7.A.2 Within 90 days i
Integrated Leak Rate of completion of Testing each test.
l 6.
Data shall be retrieved from all seismic instruments actuated during a seismic event and analyzed to determine the magnitude of the vibratory ground motion.
A Specia1 Amendment 103//109, 120 BFN 6.0-27 Unit 3
Report shall be submitted within 10 days after the event describing the magnitude, frequency spectrum, and resultant effect upon plant features important to safety.
7.
Secondary Containment 4.7.C.
Within 90 days Leak Rate Testing
- of completion of each test.
e
- Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report. This report should include data on the wind speed, wind direction, outside and inside temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.
The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.
BTU 6.0-28 Amendment No. 103//209, 120 Unit 3.
e
I 6.10 STATION OPERATING RECORDS AD RETENTION 6.10.1 Records and/or logs shall be kept in a manner convenient for review as indicated below:
a.
All normal plant operation including such items as power level, fuel exposure, and shutdowns
. b.
Principal maintenance activities c.
Reportable Events d.
Checks, inspections, tests, and calibrations of components and systems, including such diverse items as source leakagee e.
Reviews of changes made to the procedures or equipment or reviewsoftestsandexperimentstocomply;with10CFR50.59 1
f.
Radioactive shipmente g.
Test results in units of microcuries for leak tests performed pursuant to Specification 3.8.P Amendment No. IQ3//109, 120 BFN 6.0-29 Unit 3 s
a h.
Record of annual physical inventory verifying accountability of sources on record l
1.
Gaseous and liquid radioactive vaste released to the environs J.
Offsite environmental monitoring surveys l
k.
Fuel inventories and transfers 1.
Plant radiation and contamination surveys l
m.
Radiation arposures for all plant
,-sonnel n.
Updated, corrected, and as-built drawings of the plant o.
Reactor coolant system inservice inspection
(
l p.
Minutes of meetings of the NSRB
{
q.
Design fatigue usage evaluation l
l Menitoring and recording requirements below will be met for various portions of the reactor coolant pressuge boundary 1
1 i
(RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section III was performed for the conditions defined in the design specification.
In this plant, the applicable codes require fatigue usage evaluation for the reactor pressure vessel only.
The locations to be monitored shall be:
1.
The feedwater nozzles 2.
The shell at or near the waterline 3.
The flange studs Amendment No. %Q3//109, 120 BFN 6.0-30 Unit 3 l
Transients that occur during plant operations will be reviewed and a cumulative fatigue usage factor determined.
For transients which are more severe than the transients j
evaluated in the stress report, code fatigue usage criculations will be made and tabulated separately.
in the annual operating report, the fatigue usage factor Cetermined for the transients defined above shall De j
l rdded and a cumulative fatigue usage factor to date shall be reported. When the cumulative usage factor reaches a value of 1.0, an inservice inspection shall be included for the specific location at the next scheduled inspection (3-1/3-year interval) period and 3-1/3-year intervals thereafter, and a subsequent evaluation performed in accordance with the rules of ASME Section KI Code if any flaw indications are detected.
The I
results of the evaluation shall be submitted in a i
Special Report for review by the Commission.
6.10.2 Except where covered by applicable regulations, items a throug'h h above shall be retained for a period of at least 5 years and item i through q shall bs retained for the life of the pitnt. A complete inventory of radioactive materials in possession shall be maintained current at all times.
l
(
1.
See paragraph N-415.2, ASME Section III, 1965 Edition.
BFN 6.0-31
. Amendment No. 203//709, 120 Unit 3 I
4 6.11 PROCESS CONTROL PROGRAM (PCP)
I
- 1. The PCP shall be approved by the Commission prior to implementation.
- 2. Changes to the PCP shall be submitted to the. Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain; a.
Sufficiently detailed information to totally support the change.
b.
A determination that the change did not change the overall conformance of the solidified product to existing criteria.
l
6.12 0FFSITE DOSE CALCULATIONAL MANUAL (ODCM)
- 1. The ODCM shall be approved by the Commission prior to l
implementation.
l l
- 2. Changes to the ODCM shall be submitted to the Commission in the semi-annual Radioactive Effluent Release Report for the period in which the change (s) vac made.
This submittal shall contain:
a.
Sufficiently detailed information to totally support the l
l change.
i
Amendment No. %03//fd9, 120 BFN 6.0-32 Unit 3
l l
6.13 RADIOLOGICAL EFFLUENT MANUAL (REM) l
}
- 1. The REM shall be approvrd by the Commission prior to implementation.
- 3. Changes to the REM shall be approved by the Commission prior to implementation.
i e
6 BFN 6.0-33 Amendme ' No. 7 J//IO9, 120 Unit 3
_ _ _ _ _ - - - - _ - - -