ML20249C150
| ML20249C150 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/23/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20249C151 | List: |
| References | |
| NUDOCS 9806260123 | |
| Download: ML20249C150 (24) | |
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- a UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30seH001 o
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated March 25, 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 I:
B.
The facility will operate 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 will be mnducted 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.
E [D $ [ M e P
o 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in ths attachment to this license-amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No. 212 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 and shall l
be implemerited within 30 days.
]
FOR THE NUCLEAR REGULATORY COMMISSION 4
l 0'M P.
T.
Kuo. Acting Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation-
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 23,1998 -
I u
- - = - - -, - -. -
ATTACHMENT TO LICENSE AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Overleaf page 6-la is included for document completeness.
Remove Paaes Insert Paaes 6-1 6-1 6-lb 6-lb 6-5 6-5 6-Sa 6-Sa 6-6 6-6 6-7 6-7 6-25 6-25 6-26 6-26 i
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6.0 ADMINISTRATIVE CONTROLS l
(L1 RFSPONSIBII ITY 6.1.1 The Site Vice President shall be responsible for overall facility operation. In his absence, the Manager - Station Operations and Maintenance shall be responsible for overall facility operation. During the absence of both, the Site Vice President shall delegate in writing the succession to this responsibility.
6.1.2 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function and shall be the only individual that may direct the licensed activities oflicensed operators. A management directive to this effect, signed by the Senior Vice President - Nuclear, shall be reissued to r" station personnel on an annual basis.
fL2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 Onsite and Offsite Organi7ation An onsite and cc. effsite organization shall be established for facility 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 shall be established and defm' ed for the highest management levels through intermediate levels to and including all operating organization positions. These 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. These requirements shall be f
documented in the UFSAR.
- b. The Site Vice President shall be responsible for overall unit safe operation and shall l
have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. The Vice President - Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
- d. The management position responsible for training of the operating staff and the i
management position responsible for the quality assurance functions shall have sufficient organizational freedom including sufficient independence from cost and l
schedule when opposed to safety considerations.
l NORTH ANNA - UNIT 1 6-1 Amendrnent No. 3,!6,19,30,78, 99,135,212
(
ADMNSTRATTVE CONTROLS
- e. The management position responsible for health physics shall have direct access to that onsite individual having responsibility for overall facility management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown in the UFSAR.
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor. In addition, while the unit is in MODES 1,2, 3 or 4, at least one licensed l
Senior Reactor Operator shall be in the Control Room.
- c. A health physics technician # shall be onsite when fuel is in the reactor.
- d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Umited to Fuel Handling who has no other concurrent responsibilities during this operation.
I I
1 l
4 The health physics technician composition may be less than the minimum requirements for a l
l period of tima 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 Immedl&te action is taken to fill the requirec positions, NORTH ANNA-UNIT 1 61a Amendment No. 33,75,g7,97, 140
0 ADMINISTRATIVE CONTROLS 6.2.3 STATION NUCI F AR S AFFTY (SNS)
FUNCTION 6.2.3.1 SNS shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Repons, and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 SNS shall be composed of at least five dedicated, full-time engineers located onsite.
RFSPONSTRTI TTIES independent verification
- ponsible for maintaining surveillance of plant 6.2.3.3 SNS shall be res l
that these activities are performed correctly and that human errors are l
reduced as much as practical.
l 6.2.3.4 SNS shall disseminate relevant operational experience.
AUTHORITY 6.2.3.5 SNS shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Manager - Station Safety and I
Licensing.
6.2.4 SHIFT TECHNICAI ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to Shift Supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit.
Not responsible for sign-off function NORTH ANNA - UNIT 1 6-lb Amendment No. 99, !d2, 212
ADMINISTRATIVE CONTROLS (2.1 FACTI TTY STAFF OfIAI IFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANS 3.1 (1209 Draft)* for comparable positions, except for:
- 1. The Superintendent - Radiological Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
- 2. Incumbents in the positions of Shift Supervisor, Assistant Shift Supervisor (SRO),
Control Room Operator - Nuclear (RO), and Shift Technical Advisor, shall meet or exceed the requirements of 10 CFR 55.59(c) and 55.31(a)(4).
- 3. The Superintendent Operations shall hold (or have previously held) a Senior Reactor Operator License for North Anna Power Station or a similar design Pressurized Water Reactor plant.
- 4. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for Nonh Anna Power Station.
6A TRAINING 6.4.1 The Manager - Nuclear Training is responsible for ensuring that retraining and replacement training programs for the licensed facility staff meet or exceed the requirements of 10 CFR 55.59(c) and 55.31(a)(4). Also, a retraining and replacement training program for non-licensed facility staff shall meet or exceed the recommendations of Section 5 of ANS 3.1 (1209 Draft)*.
fi,,5 RFVIEW AND AtiDIT 6.5.1 STATION NIiCI F AR S AFETY AND OPER ATING COMMITTFF (SNSOC)
FIINCHON 6.5.1.1 The SNSOC shall function to advise the Site Vice President on all matters related to l
nuclear safety.
Exceptions to this requirement are specified in VEPCO's QA Topical Repon, VEP-1,
" Quality Assurance Program, Operational Phase."
NORTH ANNA - UNIT 1 6-5 Amendment No. 3, ! !, !?, 30,78 S?,124, ! ?5,112, !!?, 212
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The SNSOC shall be composed of:
Chairman: Manager - Station Safety and Licensing Vice Chairman and Member: Manager - Station Operations and Maintenance Member: Superintendent - Operations Member: Superintendent - Maintenance Member: Superintendent - Radiological Protection Member: Superintendent - Engineering AlTFRNATFS 6.5.1.3 All attemate members shall ba appointed in writing by the SNSOC Chairman to serve on a temporary basis; however, no more than one alteinate shall participate as a voting member in SNSOC activities at'any one time.
l l
NORTH ANNA - UNIT 1 6-Sa Amendment No. 443, 212
ADMINISTRATIVE CONTROLS MFFTING FRFOITENCY 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated alternate.
OITORIIM 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice-Chairman and two members including alternates.
RFRPONSIBII TITFR 6.5.1.6 The SNSOC shall be responsible for:
Review of 1) all new procedures required by Specifications 6.8.1 and 6.8.2,2) all a.
procedure changes that require a safety evaluation, 3) all programs required by Specification 6.8.4 and changes thereto, and 4) any other procedures or changes thereto as determined by the Site Vice President to affect nuclear safety.
l
- b. Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes or modifications to plant systems or equipment that c.
affect nuclear safety.
- d. Review of all proposed changes to Appendix "A" Technical Specifications and Appendix "B" Environmental Protection Plan. Recommended changes shall be submitted to the Site Vice President.
l Investigation of all violations of the Technical Specifications including the e.
preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Vice President - Nuclear Operations and the MSRC.
f.
Review of all REPORTABLE EVENTS and Special Reports.
- g. Review of facility operations to detect potential nuclear safety hazards.
- h. Performance of special reviews,in. estimations or analyses and reports thereon as requested by the Chairman of tk Station Nuclear Safety and Operating Committee or Site Vice President.
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- i. Deleted.
- j. Deleted.
)
l i
Amendment No. ! !, 30, i?,63, 212 NORTH ANNA - UNIT 1 6-6 78, M,135,180,19!,
ADMINISTRATIVE CONTROLS
- k. Review of every unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recunrence and the forwarding of these reports to the Vice President-Nuclear Operations and the Management Safety Review Committee.
1.
Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL
- m. Review of the Fire Protection Program and implementing procedures and shall submit recommended changes to the Site Vice President.
l AUTHORITY 6.5.1.7 The SNSOC shall:
Provide written approval or disapproval of items considered under 6.5.1.6(a) a.
through (c) above. SNSOC approval shall be certified in writing by either the Manager - Station Operations and Maintenance or the Manager - Station Safety and Licensing.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
- c. 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 Operations and the Management Safety Review Committee (MSRC) of disagreement between the SNSOC and the Site Vice President; however, the Site Vice President shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
)
RECORDS 6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Site Vice President, Vice President-Nuclear Operations and the MSRC.
l 6.5.2 MANAGEMENT S AFFTY REVIEW COMMITTEF (MSRC)
FUNCTION 6.5.2.1 The MSRC shall function to provide independcat review of designated activities in the areas of:
- a. Station Operations
- b. Maintenance
- c. Reactivity Management
- d. Engineering
- e. Chemistry and Radiochemistry
- f. Radiological Safety
- g. Quality Assurance Practices
. NORTH ANNA - UNIT I 6-7 Amendment No. ! !, 30, is,78, M,123,!ie,212
e ADMINISTRATIVE CONTROLS l
M DFIFTFD G
PROFFRM CONTRO1 PROGR AM (PCPj 6.14.1 Changes to the PCP:
- 1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.r. This documentation shall contain:
a)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Sha!! become effective after review and acceptance by the SNSOC and the approval of the Site Vice President.
l NORTH ANNA - UNIT 1 6-25 Amendment No. 4', !03, ! 30, 212
l ADMINISTRATIVE CONTROLS M
OFFSITF DORF CAT PIII_ATION MANIIAIJODCM Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.r. This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the SNSOC and the approval of the Site Vice President.
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- c. Shall be submitted to the Commission in the form of a complete, legible copy of the l
entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
M DELETED l
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1 1
- NORTH ANNA - UNIT 1-6-26 Amendment No. 4S, !?^,' !?!, 212
- o l
y UNITED STATES l
s j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON D.C. - M
%4.....
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.193 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al.. (the licensee) dated March 25, 1998, 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 provisions of the Act, and the rules and regulations of the Comission:
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public. and (ii) that such activities will be conducted in compliance with the Comission's regulations:
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.
1 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
t (2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No.193. 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION y
P.
T.
Kuo. Acting irector Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 23,1998 l
l L
ATTACHMENT TO LICENSE AMENDMENT NO.193 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Rep.' ace the following pages of the Appendix "A" Technical-Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Over'eaf page 6-5 is included for document completeness.
Remove Paaes Insert Paaes 6-1 6-1 6-lb 6-lb 6-6 6-6 6-6a 6-6a 6-7 6-7 6-8 6-8 6-25 6-25
fi.0 ADMINISTRATIVE CONTROIJi fi,1 RESPONSIBILITY 6.1.1 The Site Vice President shall be responsible for overall facility operation. In his absence, the Manager - Station Operations and Maintenance shall be responsible for overall facility -
operation. During the absence of both, the Site Vice President shall delegate in writing the succession to this responsibility 6.1.2 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function and shall be the only l
individual that may direct the licensed activities oflicensed operators. A management directive to j
this effect, signed by the Senior Vice President - Nuclear, shall be reissued to all station personnel on an annual basis.
fi2 ORGANIZATION ONSITE AND Oeesn E ORGANI7ATION 6.2.1 Oneir, nna offcite organineinn l
An onsite and an offsite organization shall be established for facility 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 shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and Relationships, andjob descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the UFSAR.
- b. The Site Vice President shall be responsible for overall unit safe operation and shall l
have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. The Vice President - Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety, d, The management position responsible for training of the operating staff and the management position responsible for the quality assurance functions shall have sufficient organizational freedom including sufficient independence from cost and schedule when opposed to safety considerations.
NORTH ANNA - UNIT 2 -
6-1 Amendment No. ! !, 67, 86, ! !S,193
1 ADMINISTRATIVE CONTROLS 6.2.3 STATION NUCI F AR S AFFTY (SNS)
FUNCTION 6.2.3.1 SNS shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources which may indicate areas for improving plmt safety.
COMPOSITION 6.2.3.2 SNS shall be composed of at least five dedicated, full-time engineers located onsite.
RESPONSIBILITIES 6.2.3.3 SNS shall be responsible for maintaining surveillance of plant activities to provide independent verification" that these activities are performed correctly and that human errors are reduced as much as practical.
6.2.3.4 SNS shall disseminate relevant operational experience.
AUTHORITY 6.2.3.5 SNS shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Manager - Station Safety and Licensing.
6,2,4 SHIFT TECHNICAI ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit.
I I
i Not responsible for sign-off function NORTH ANNA - UNIT 2 6-lb Amendment No. S6, !25,193
TABLE 6.2-1 (Continued)
SS - Shift Supervisor with a Senior Reactor Operators License on Unit 2.
SRO - Individual with a Senior Reactor Operators License on Unit 2.
R0 - Individual with a Reactor Operators License on Unit 2.
AO - Auxiliary Operator STA - Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2-1.
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.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function.
During any absence of the Shift Supervisor from the Control Room while the unit is in MODE 5 or 6, an individual with a valid R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room command function.
Procedures will be established to insure that NRC policy statement guidelines l
regarding working hours established for employees are followed.
In addition, I
procedures will provide for documentation of authorized ~ deviations from these I
guidelines and that the documentation is available for NRC review.
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NORTH ANNA-UNIT 2 6-5 Amendment No. 34 l
ADMINISTRATIVE CONTROLS f2.3 FACTI ITY STAFF OUAf TFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANS 3.1 (1269 Draft)* for comparable positions, except for:
- 1. The Superintendent - Radiological Protection shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
- 2. Incumbents in the positions of Shift Supervisor, Assistant Shift Supervisor (SRO),
Control Room Operator - Nuclear (RO), and Shift Technical Advisor, shall meet or exceed the requirements cf 10 CFR 55.59(c) and 55.31(a)(4).
- 3. The Superintendent Operations shall hold (or have previously held) a Senior Reactor Operator License for North Anna Power Station or a similar design Pressurized Water Reactor plant.
- 4. The Supervisor Shift Operations shall hold an active Senior Reactor Operator License for North Anna Power Station.
(2.4 TR AINING 6.4.1 The Manager - Nuclear Training is responsible for ensuring that retraining and replacement training programs for the licensed facility staff meet or exceed the requirements of 10 CFR 55.59(c) and 55.31(a)(4). Also, a retrainig ar.J replacement training program for non-licensed facility staff shall meet or exceed the recommendations of Section 5 of ANS 3.1 (12n9 Draft)*.
(z.5 REVIEW AND AIIDIT (2.51 STATION NUCI F AR S AFETY AND OPERATING COMMITTFF (SNSOC)
FUNCTlOS 6.5.1.1 The SNSOC shall function to advise the Site Vice President on all matters related to l
nuclear safety.
1 Exceptions to this requirement are specified in VEPCO's QA Topical Repon, VEP-1,
" Quality Assurance Program, Operational Phase."
NORTH ANNA - UNIT 2 6-6 Amendment No. !!,67,73,108,
!!S,125,139,193 i
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ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The SNSOC shall be composed of:
Chairman: Manager Station Safety and Licensing Vice Chairman and Member: Manager - Station Operations and Maintenance Member: Superintendent - Operations Member: Superintendent - Maintenance Member: Superintendent - Radiological Protection Member: Superintendent - Engineering l
ALTFRNATES 6.5.1.3 All alternate members shall be appointed in writing by the SNSOC Chairman to serve on a temporary basis: however, no more than one attemate shall panicipate as a voting member in SNSOC activities at any one time.
NORTH ANNA - UNIT 2 6-6a Amendment No. 435.193
o ADMINISTRATIVE CONTROLS MFFTING FREOlIENCY 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the SNSOC Chairman or his designated altemate.
OllORIIM 4
6.5.1.5 A quorum of the SNSOC consists of the Chainnan or Vice-Chairman and two members including alternates.
RFRPONSTRif TN9 6.5.1.6 The SNSOC shall be responsible for:
- a. Review of 1) all new procedures required by Specifications 6.8.1 and 6.8.2,2) all procedure changes that require a safety evaluation,3) all programs required by Specification 6.8.4 and changes thereto, and 4) any other procedures or changes thereto as determined by the Site Vice President to affect nuclear safety.
l
- b. Review of all proposed tests and experiments that affect nuclear safety,
- c. Review of all proposed changes or modifications to plant systems or equipment that l
I affect nuclear safety.
- d. Review of all proposed changes to Appendix "A" Technical Specifications and Appendix "B" Environmental Protection Plan. Recommended changes shall be submitted to the Site Vice President.
l
- e. 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 Operations and the MSRC.
- f. Review of all REPORTABLE EVENTS and Special Reports.
- g. Review of facility operations to detect potential nuclear safety hazards.
- h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee or Site Vice President.
l
- i. Deleted.
- j. Deleted.
1 Amendment No. ! !, ", 67, 86,193 NORTH ANNA - UNIT 2 6-7
!!8,!6!,!?2,
ADMINISTRATIVE CONTROLS
- k. Review of every unplanned onsite release of radioactive material to the environs 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 Operations and the Management Safety Review Committee.
1.
Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
- m. Review of the Fire Protection Program and implementing procedures and shall submit recommended changes to the Site Vice President.
l AUTHORITY 6.5.1.7 The SNSOC shall:
Provide written approval or disapproval of items considered under 6.5.1.6(a) through a.
(c) above. SNSOC approval shall be certified in writing by either the Manager -
Station Operations and Maintenance or the Manager - Station Safety and Licensing.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
- c. 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 Operations and the Management Safety Review Committee (MSRC) of disagreement between the SNSOC and the Site Vice President; however, the Site Vice President l
shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Site Vice President, Vice President-Nuclear Operations and the MSRC.
l fL5 2 M ANAGEMENT S AFETY REVIEW COMMI~TTEF (MSRC)
FUNCTION 6.5.2.1 The MSRC shall function to provide independent review of designated activities in the areas of:
- a. Station Operations
- b. Maintenance
- c. Reactivity Management
)
- d. Engineering
- e. Chemistry and Radiochemistry
- f. Radiological Safety
- g. Quality Assurance Practices
- h. Emergency Preparedness NORTH ANNA - UNIT 2 6-8 Amendment No. !!,3!,67, S6,
!!S,123,193 l
j
l
. ADMINISTRATIVE CONTROLS Q PROFFRR CONTROI PROGR AM (PCP)
Changes to the PCP:
Shall be documented and records of reviews performed shall be retained as required a.
by Specification 6.10.2.r. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the overall confonnance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the SNSOC and the approval of the Site Vice President.
l Q OFFSITF DORF CAT Clil ATION MANIIAI_ (ODCM)
Changes to the ODCM:
Shall be documented and records of reviews performed shall be retained as required a.
by Specification 6.10.2.r. This documentraion shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the SNSOC and the approval of the Site Vice President.
l c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month / year) the change was implemented.
NORTH ANNA - UNIT 2 6-25 Amendment No. ?!, ! !4,159,193
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