ML17059C119
| ML17059C119 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/07/1998 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059C120 | List: |
| References | |
| NUDOCS 9807130116 | |
| Download: ML17059C119 (44) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHlNGTON, D.C. 2055&0001 NIAGARAMOHAWKPOWER CORPORATION DOCKET NO. 50-220 NINE MILEPOINT NUCLEAR STATION UNIT NO. 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No 1 62 License No. DPR-63
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 15, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-63 is hereby amended to read as follows'.
9807i30ii6 980707 PDR ADOCK 05000220 P
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 62 are hereby incorporated in the license.
The licensee shall operate the facilityin accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.'
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of issuance:
Quly 7, 1998 S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - I/II
'ffice of Nuclear Reactor Regulation
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ATTACHMENTTO LICENSE AMPNDMENT I
AMENDMENTNO.162I 0 FACILITYOPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 347 349 352 353 354 355 358 360
~Insert Pa es 347 349 352 353 354 355 358 360 4
6.0 ADMINISTRATIVECONTROLS 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 Station Shift Supervisor - Nuclear (or during his absence from the control room, a designated individual) shall responsible for the control room command function. A management directive to this effect, signed by the Chief Nuclear Officer shall be re-issued to station personnel on an annual basis.
6.2 OrcrDaniza ion Onsite and Offsi e Or anization 6.2.1
- An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsite and offsite organization shall include the position for activities affecting the safety of the nuclear power. plant.
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.
Those relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions or in equivalent forms of documentation.
The organization charts shall be documented in the Final Safety Analysis Report, and the functional descriptions of departmental responsibilities and relationships and job descriptions for key personnel positions are documented in procedures.
b.
The Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to assure 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 have responsibility for.overall unit operation and shall have control over those resources necessary for safe operation and maintenance of the plant.
AMENDMENT NO. QE, $6,162 347
I
g.
DELETED h.
Administrative procedures shall be developed and implemented to limitthe working hours of facility staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physicists, auxiliary operators and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work an 8 to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> day, nominal 40-hour week while the facility is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be-used, or durin~
extended periods of shutdown for refueling, major maintenance or major plant modifications on a temporary basis, the following guidelines shall be followed:
1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (excluding shift turnover time).
2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period (all excluding shift turnover time).
3)
A break of at least 8-hours should be allowed between work periods (including shift turnover time).
4)
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Vice President - Nuclear Generation or designee to assure that excessive hours have not been assigned.
I Routine deviation from the above guidelines is not authorized.
i.
As a rninirnum, either the Manager Operations or the General Supervisor Operations shall hold a senior reactor operator license.
The Station Shift Supervisor Nuclear and Assistant Station Shift Supervisor Nuclear shall hold senior reactor operator licenses.
Only licensed individuals may direct licensed activities.
AMENDMENTNO. A$, 6f, Qk. 7kb, 1<2 349
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~AIterne ee 6.5.1.3 Allalternate rnernbers shall be appointed in writing by the SORC Chairman or Vice-Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SORC activities at any one time.
Meetin Fre uenc 6.5.1 4
The SORC shall meet at least once per calendar month and as convened by the SORC Chairman, Vice-Chairman, a designated alternate.
Quorum 6.5.1.5 The quorum of the SORC necessary for the performance of the SORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, or a Vice-Chairman, and four members, including alternates.
Re onsibili i s 6.5.1.6 The SORC shall be responsible for:
a.
Review of all REPORTABLE EVENTS.
b.
Review of unit operations to detect potential safety hazards.
c.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Plant Manager or the Safety Review and Audit Board.
d.
Investigation of violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Generation and to the I
Safety Review and Audit Board.
AMENDMENTNO. iQE, 56, 162 352
0
~Au hori 6.5.1.7 The SORC shall:
a.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) throu h
.(d) above constitutes an unreviewed safety question.
e...
a roug b.
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 Vice Pres'd t - N I
G resi en uc ear Generation and the Safety Review and Audit Board of disagreement between the SORC and the Pl tM;h e
ant anager; however, the Plant Manager sh have the responsibility for resolution of such disagreements pursuant to 6.1.1 above Records 6.5.1.8 Th S
e ORC shall maintain written minutes of each meeting and copies sh ll b
'd d Nuclear Generation and the Safety Review and Audit Board.
i s s a
e provi e to the Vice President-6.5.2 Technical Review and Control
~Ac ivi iss 6.5.2.1 Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and there changes thereto, shall be prepared by a qualified individual/organization.
Each h
d i
ac suc proce ure, and changes h
ereto, shall be reviewed by an individual/group other than the individual/
h h
d ivi ua group w ic prepared the procedure, or c anges thereto, but who may be from the same organization as the nd' l/
h' or h
i ivi ua group w ic prepared the procedure or c anges thereto.
Approval of procedures and programs and changes thereto and their saf be controlled by administrative procedures, es ereto an t eir sa ety evaluations, shall ~
6.5.2.2 Proposed changes to the Technical Specifications shall be prepared by a qualified individual/organization.
The preparation of each proposed Technical Specifications change shall be reviewed by an individual/group other than the individual/group which prepared the proposed change but who m b
f th individual/group which prepared the proposed change.
Proposed changes to the Technical S ecifi approved by the Plant Manager.
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s o
e ec nica pecifications shall be AMENOMENT NO. Q$, Q$,
162 353
6.5.2.3 Proposed modifications to unit structures, systems and components that affect nuclear safety shall be designed by a qualified individual/organization.
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 structures, systems and components and the safety evaluations shall be approved prior to implementation by the Plant Manager; or the Manager Technical Support as previously designated by the Plant Manager.
6.5.2.4 Individuals responsible for reviews performed in accordance with Specifications 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the Plant Manager to perform such reviews.
Each such review shall include a determination of whether or not additional cross-disciplinary rev ew s n c eerne necessary such review shall be performed by the appropriate designated station review personnel.
6.5.2.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical.
Specifications and their safety evaluations shall be reviewed by the Plant Manager, or the Manager Technical Support as previously designated by the Plant Manager.
6.5.2.6 The Plant Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President - Nuclear Generation.
6.5.2.7 R
The. facility security program, and implementing procedures, shall be reviewed at least every 12 mo th:
s every mon s.'commended changes shall be approved by the Plant Manager and transmitted to the Vice President
- Nuclear Generation and to the Chairman of the Safety Review and Audit Board.
6.5.2.8 The facility emergency plan, and implementing procedures shall be reviewed at least every 12 months.
Recommended changes shall be approved by the Plant Manager and transmitted to the Vice President - Nuclear Generation and to the Chairman of the Safety Review and Audit Board.
AMENDMENTNO. Qg, k6, 162 354
"j
- 6.5.2.S The Plant Mana er shall assure the rf r g
t e performance of a review by a qualified individual/organization of changes to the Radiological Waste Treatment systems.
6.5.2.10 Review of an accidental un lann d
y ',
p a ed, or uncontrolled radioactive release including the preparation of reports
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covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President
- Nuclear Generation and to the Safety Review and,Audit Board.
I 6.5.2.11 Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
Approval of any changes shall be made by the Plant Manager or his designee before implementation of such changes.
6.5.2.12 Re orts d ports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained.
Copies shall be provided to the Vice President - Nuclear Generation and the Safety Review and Audit I
Board.
6.5.2.13 The Plant Manager shall assure the performance of a review by a qualified individual/organization of the Fire Protection Program and implementing procedures at least every 12 months and submitt I
f d d h
6.5.3 Safe Review and Audi Board SRAB
~Func ion 6.5.3.1 The Safety Review and Audit Board shall function to provi,independent review and audit of d i
d an au i
o esignate activities a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices i.
(other appropriate fields associated with the unique characteristics of the nuclear power plant)
AMENDMENT NO. rQE, 6k, 162 355
0
Audits 6.5.3.8 Audits of facility activities shall be performed under the cognizance of th SRAB. Th e
ese audits shall encompass:
a.
The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year c.
The results of actions taken to correct deficiencies occurring in facilit e
me ho i g in aci i y equipment, structures, systems or met od of operation that affect nuclear safety at least once per six months.
d.
The performance of all activities required by the Quality Assurance Program to meet the criteria of Ap endix "B", 10CFR50, at least once per two years.
ee e cri eria o ppen ix e.
The Facility Emergency Plan and implementing procedures at least once every 12 months f.
The Facility Security Plan and implementing procedures at least once every 12 months.
g.
The Facility Fire Protection Program and implementing procedures at least once per two years.
h.
Any other area of facility operation considered appropriate by the SRAB or the Vi P
Generation.
or e
ice resident - Nuclear i.
The radiological environmental monitoring program and the results th f t I s
ereo at east once per 12 months.
j, The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
k.
The Process Control Program and implementing procedures for processing and acka in of r d't least once per 24 months.
cessing an pac aging of radioactive wastes AMENDMENT NO. QE, fb9 358
0 1
6.6 Re ortable Occurrence 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 Sections 50.72 and 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be r be reviewed. by the SORC and the results of this review submitted to the SRAB and the Vice President - Nuclear Generation.
6.7 Safet Limit Violation 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.
b.
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 Vice President - Nuclear Generation and the SRAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.
A Safety LimitViolation Report shall be prepared.
The report shall be reviewed by th SORC.
Th 1
a
(
) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety LimitViolation Report shall be submitted to the Commission, within 30 days of the violation, and to the SRAB, and the Vice President
- Nuclear Generation within 14 days.
6.8 Procedures 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recornrnendations of Sections 5.1 and 5.3 of ANSl N18.7-1972 and Appendix "A" of USAEC Re ulator Guide 'l.33 except as provided in 6.8.2 and 6.8.3 below.
a.
Written procedures shall be established, implemented, and maintained for activities involvin the Fire Pr P
implementation i i s invoving t e ire rotection Program 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation by the branch manager for the functional area of the procedure or higher levels of rnanagernent as governed by administrative procedures.
Each procedure and administrative policy of 6.8.1 above shall be reviewed periodically as set forth in administrative procedures.
'MENDMENT NO. iQk, AE, 76.
162 360
gD,R RECT
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 NIAGARAMOHAWKPOWER CORPORATION DOCKET NO. 50-410 NINE MILEPOINT NUCLEAR STATION UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 83 License No. NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 15, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-69 is hereby amended to read as follows:
0 (2)
I Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 83are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGUlATORYCOMMISSION
Attachment:
Changes to the Technical Specifications Date of issuance:
July 7, 1998 S. Sing Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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ATTACHMENTTO LICE SE AMENDMENT AMENDMENTNO.83 TO FACILITYOPERATING LICENSE NO. NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
6-1 6-,3 6-8 6-9 6-10 6-11 6-14 6-15
~Insert Pa es 6-1 6-3 6-8 6-9 6-10 6-11 6-14 6-15
0
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'I 6.0 ADMINISTRA E CONTR L
.1 RESPQN IBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during the Plant Manager's absence.
6.1.2 The Station Shift Supervisor - Nuclear (or during the Supervisor's 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 Chief Nuclear Officer shall be reissued to,all station personnel annually.
6.2 ORGANIZATION 6.2.1 Onsi e and Off i Or anizati n
An onsite and an 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.
~ 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.
Those relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions or in equivalent forms of documentation.
The organization charts shall be documented in the Final Safety Analysis Report, and the functional descriptions of departmental responsibil-ities and relationships and job descriptions for key personnel positions are documented in procedures.
- b. 'he Chief Nuclear Officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to assure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
l C.
The Plant Manager shall have responsibility for overall unit operation and shall have control over those resources necessary for safe operation and maintenance of the plant.
The persons responsible for the training, health physics and quality assurance functions may report to an appropriate manager onsite, but shall have direct access to responsible corporate management at a level where action appropriate to" the mitigation of training, health physics and quality assurance concerns can be accomplished.
UNIT STAFF 6.2.2 The unit organization shall be subject to the following:
a.
Each on-duty shift shall be composed of at least the minimum shift crew shown in Table 6.2.2-1'INE MILE POINT - UNIT 2 6-1 Amendment No. 4, dE, Pk, 83
6.0 ADMINISTRATIVECONTROLS R
ANIZATI N NIT STAFF 6.2.2.i (Continued) 4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.'ontrols shall be included in the procedures so that individual overtime shall be reviewed monthly by the Vice President-Nuclear Generation or a designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
The General Supervisor Operations, Supervisor Operations, Station Shift Supervisor, Nuclear and Assistant Station Shift Supervisor Nuclear shall hold senior reactor operator licenses.
6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP FUNCTION 6.2.3.1 The Independent Safety Engineering Group (ISEG) shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety.
The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to the Vice President
- Nuclear Safety Assessment and Support.
0MP ITI N
6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a bachelor's degree in engineering or related science and at least 2 years of professional level experience in his/her field, at least 1 year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The principal function of the ISEG is to examine plant operating characteristics and the various NRC and industry licensing and service advisories, and to recommend areas for improving plant operations or safety.
The ISEG will perform independent review of plant activities, including maintenance, modifications, operational concerns, and analysis and make recommendations to the Vice President
- Nuclear Safety Assessment and Support.
NINE MILE POINT - UNIT 2 6-3 Amendment No. 3, Ek, lk~ 83
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b ADMINISTRATIVEC NTR LS b
6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS REVIEW COMMITTEE FUNCTION 6.5.1.1 The Station Operations Review Committee (SORC) shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The SORC shall be composed of the Chairman:
Vice-Chairman/Member:
Vice-Chairman/Member:
Member:
Member:
Member:
Member:
Plant Manager Manager Operations-Manager Technical Support Manager QA Operations Manager Maintenance Manager Chemistry Manager Radiation Protection LTERNATE 6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman or Vice-Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SORC activities at any one time.
MEETING FREQ EN Y
6.5.1.4 The SORC shall meet at least once every calendar month and as convened by the SORC Chairman, Vice-Chairman, or a designated alternate.
QUUQR IM 6.5.1.5 The quorum of the SORC necessary for the performance of the SORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman, or a Vice-'hairman and four members including alternates.
6.5.1.6 The SORC shall be responsible for:
a.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence. to the Vice President
- Nuclear Generation and to the Safety Review and Audit Board; NINE MILE POINT - UNIT 2 6-8 Amendment No. III, dE, 'dE, 8E, P7 83
ADMINISTRATIVECONTROLS R VI WANDA DI S.
.1 STATI N
PERATI N
REVIEW C MITTEE 6.5.1.6 (Continued) b.
Review of all REPORTABI E EVENTS; c.
Review of unit operations to detect potential hazards to nuclear safety; d.
Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Safety Review and Audit Board; e.
Safety evaluations and analyses resulting from technical review and control activities 6.5.2.1, 6.5.2.2, 6.5.2.3, and 6.5.2.5.
DUTIES 6.5.1.7 The SORC shall:
a.
Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6.a through e constitutes an unreviewed safety question.
b.
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 Vice President - Nuclear Generation and t
the Safety Review and Audit Board of disagreement between the SORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
~RECORD 6.5.1.8 The SORC shall maintain written minutes of each SORC meeting that at a minimum, document the result of all SORC activities performed under the responsibilities and authority provisions of these Technical Specifications.
Copies shall be provided to the Vice President-Nuclear Generation and the Safety Review and Audit Board.
.5.2 TE HNI L REVIEW AND NTR L
TIVITIE 6.5.2.1 Each procedure and program required by Specification 6.8 and other procedures that affect nuclear safety, and changes thereto, shall be prepared by a qualified individual/organization.
Each such procedure, and changes thereto, shall be reviewed by an individual/group other than the individual/group that prepared the procedure, or changes thereto,,but who may be from the same organization as the individual/group that prepared the procedure, or changes thereto.
Approval of procedures and programs and changes thereto and their safety evaluations, shall be
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controlled by administrative procedures.
6.5.2.2 Proposed changes to the Technical Specifications shall be prepared by a qualified individual/organization.
The preparation of each proposed Technical Specifications change shall be reviewed by an individual/group other than the individual/group that prepared the proposed
- change, but who may be from the same organization as the individual/group that prepared the proposed change.
NINE MlLE POINT - UNIT 2 6-9 Amendment No. 5, kk, /kE 83
DMINI TR TIVE NTROL REVIEW AND AUDIT TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.2.2 (Continued)
Proposed changes to the Technical Specifications shall be approved by the Plant Manager.
6.5.2.3 Proposed modifications to unit structures, systems, and components that affect nuclear safety shall be designed by a qualified individual/organization.
Each such modification shall be reviewed by an individual/group other than the individual/group that designed the modification, but who may be from the same organization as the individual/group that designed the modifica-tion.
Proposed modifications to structures, systems, and components and the safety evaluations shall be approved before implementation by the Plant Manager, or the Manager Technical Support, as previously designated by the Plant Manager.
6.5.2.4 Individuals responsible for reviews performed in accordance with Specifications 6.5.2.1, 6.5.2.2, and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the Plant Manager to perform such reviews.
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 the appropriate designated station review personnel
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6.5.2.5 Proposed tests and experiments that affect station nuclear safety and are not addressed in the FSAR or Technical Specifications and their safety evaluations shall be reviewed by the Plant Manager, or the Manager Technical Support, as previously designated by the Plant Manager.
6.5.2.6 The Plant Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President - Nuclear Generation.
6.5.2.7 The facility security program and implementing procedures shall be reviewed at least every 12 months.
Recommended changes shall be approved by the Plant Manager and transmitted to the Vice President
- Nuclear Generation, and to the Chairman of the Safety Review
)
and Audit Board.
6.5.2.8 The facility emergency plan and implementing procedures shall be reviewed at least every 12 months.
Recommended changes shall be approved by the Plant Manager and transmitted to the Vice President - Nuclear Generation and to the Chairman of the Safety Review and Audit Board.
NINE MILE POINT - UNIT 2 6-10 Amendment No. 5, kk, P7, 83
~ ADMINISTRATIVEC TROLS REVIEW AND AUDIT TE N
L EVIEW A D
NT IV 6.5.2.9 The Plant Manager shall assure the performance of a review by a qualified individual/
organization of changes to the Radiological Waste Treatment systems.
6.5.2.10 Review of any accidental, unplanned, or uncontrolled radioactive release, including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Nuclear Generation and to the Safety Review and Audit Board.
6.5.2.11 Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATIONMANUAL. Approval of any changes shall be made by the Plant Manager or a designee before implementation of such changes.
6.5.2.12 Reports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained.
Copies shall be provided to the Vice President - Nuclear Generation and the Safety Review and Audit Board.
AFETY REVIEW AND A DIT BOARD FQN¹~N 6.5.3.1 The Safety Review and Audit Board (SRAB) shall function to provide independent review and audit of designated activities in the areas of:
a.
b.
C.
d.
e.
f.
g.
h.
Nuclear power plant operations Nuclear engineering Chemistry and radiochemistry Metallurgy Instrumentation and control Radiological safety Mechanical and electrical engineering Quality assurance practices and Other appropriate fields associated with the unique characteristics of the nuclear power plant;-
The SRAB shall report to and advise the Chief Nuclear Officer on those areas of responsibility in Specifications 6.5.3.7 and 6.5.3.8.
M ITI N
6.5.3.2 The SRAB shall be composed of the:
Chairman:
Member:
Member:
Member:,
Member:
Vice President, Manager or Staff Engineer Plant Manager or Designee Staff Engineer - Nuclear Staff Engineer - Mechanical or Electrical Consultant (Specification 6.5.3.4)
NINE MILE POINT - UNIT 2 6-11 Amendment No. 4, kk, fP
1
DMI I T VE NT L
REVIEW AND AUDIT SAFETY REVIEW AND AUDIT BOARD AUDITS 6.5.3.8 (Continued) j.
Any other area of unit operation considered appropriate by the SRAB or the Vice President
- Nuclear Generation.
I k.
The Fire Protection Program and implementing procedures at least once per 24 months.
I, An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
m.
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 36 months.
THORIT 6.5.3.9 The SRAB shall report to and advise the Chief Nuclear Officer on those areas of responsibility specified in Sections 6.5.3.7 and 6.5.3.8.
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)~RD 6.5.3.10 Records of SRAB activities shall be prepared,
- approved, and distributed as indicated below:
at Minutes of each SRAB meeting shall be prepared, approved, and forwarded to the Chief Nuclear Officer within 14 days following each meeting.
b.
Reports of reviews encompassed by Specification 6.5.3.7b, e, g, h shall be prepared,
- approved, and forwarded to the Chief Nuclear Officer within 14 days following completion of the review.
c.
Audit reports encompassed by Specification 6.5.3.8 shall be forwarded to the Chief Nuclear Officer and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
NINE MILE POINT - UNIT 2 6-14 Amendment No. 9, 9k, 6~
83
P
R P
RTABLE EVENT A TION The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.72 and 10 CFR 50.73, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC, and the results of this review shall be submitted to the SRAB and the Vice President
- Nuclear Generation.
I 6.7 AFETY LIMITVIOLATION 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 Vice President - Nuclear Generation and the SRAB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety Limit Violation Report shall be prepared in accordance with 10 CFR 50.73.
The report. shall be reviewed by the SORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit components,
- systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
The Safety LimitViolation Report shall be submitted to the Commission within 30 days of the violation, and to the SRAB, and the Vice President - Nuclear Generation within 14 days.
d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
I 6.8 PRO EDURES AND PROGRAM PROCEDURES 6.8.1 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 t
b.
The applicable procedures required to implement the requirements of NUREG-0737 c.
Refueling operations NINE MILE POINT - UNIT 2 6-1 5 Amendment No. 5, k5, 6
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