ML20063Q003
| ML20063Q003 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/07/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063Q004 | List: |
| References | |
| NFP-07-A-118, NFP-7-A-118, NUDOCS 9008160183 | |
| Download: ML20063Q003 (27) | |
Text
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UNITED STATES y
NUCLEAR REGULATORY COMMISSION i g) e t jf e
wasmworow, o. c. 20 sos
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VIRGINIA ELECTRIC AND POWER COMPANY i
OLD DOMINION ELECTRIC COOPERATIVE t
DOCKET N0. 50-338 NORTH ANNA POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. NPF-4 1.
The< Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated February 1,1990, as supplemented July 30, 1990, complies with the standards and re EnergyActof1954,asamended(theAct)quirementsof=theAtomic
, 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 Connission; C.
There is reasonable assurance (1) 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 connon defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cosnission's regulations and all applicable requirements have been satisfied.
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0008160183 900807 ADOCK0500g8 DR.
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Accordingly, the license is amended by. changes to the Technical Spect-l fications as indicated in the attachment to this license amendment, I
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, 1
as revised through Amendment'No.135, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective at of the date of issuance and shall l
be implemented within 30 days, i
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l FOR THE NUCLEAR REGULATORY COMMISSION I
He art N. Berkow, Director P oject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
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I Date of Issuance: August 7, 1990 l
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1 ATTACHMENT TO LICENSE AMEN 0 MENT N0.135 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET N0. 50 338 Replace the following pages of the Appendix A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identiffeu by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document com9leteness.
M 6-1 6-5
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6-6 6-7 6-8 6-9 6-10 6-11 4
6-12
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6.0' AD+11MISTRATIVE CONTR01.S 6.1 RESPONS!BILITY i
6.1.1 The Station Manager shall be responsible for overall facility operation.
In his absence, the Assistant Station Manager (Operations and 'iaintenance) shall be responsible for overall facility operation. During the absence of both, the Station Manager shall delegate in writing the succession to this responsibility.
6.1.2 The Shift Supervisor (or during his absence from the Control Roon, a designated individual) shall be responsible for the Control Room command function and shall be the only individual that may dire:t the licensed activities of licensed operator 4.
A management directive to this effect, signed by the Senior Vice President - Nuclear, shall~ be reissued to all station personnel on l
an annual basis.
i 6.2 ORGANIZATION I
ONSITE AND OFFSITE ORGANIZATION 6.2.1 nsite and Offsite Organization a
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.
l.ines of authority, responsibility, and communication shall be a.
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, j
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 documented in the UFSAR.
b.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
The Vice President - Nuclear Operations shall have corporate c.
responsibility for overall plant nuclear safety and shall take l
any measures needed to ensure acceptable performance of tha staff in operating, maintaining, and providing technical support
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s 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 eost and schedule when opposed to safety considerations, i
NORTH ANilA - UtlIT I 6-1 gdmentflos. 3,78,79,39,78 J),
i ADriffilSTRATIVL CONTROLS t
The management position responsible.for health physics shall have e.
i 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 3
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.
i b.
A: least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while the unit is in-fiODES 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room, c.
A health physics technician # shall be onsite when full is in the reacto'.
d.
ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Sen or-Reactor Operator Limited to. Fuel Handling who has no other ancurrent N
responsibilities during this operation, e.
A Fire Brigade of at least 6 members shall be maintained onsite at all times #,
The Fire Crigade shall not include the minimum shift crew shown in Table 6.2-1 or any personnel required for other 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.
NORTH AtlNA - UNIT 1 6-la Amendment No. 39,78,87,99
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ADMINISTRATIVE CONTRLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each menber o# the unit staff shall meet or exceed the mininum qualifica-tions of ANS 3.1-(12/79 requirenents s Draft) for comparable positions and the supplenantal except for (1)pecified in the March 28, 1980 MRC letter to all licensees, the Superintendent - Radiological Protection who shall neet or l
exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a -
scientific'or engineering discipline with specific training in plant design, l
and response and analysis of the plant for transients and accidents.
6.4 TR AINING -
6.4.1 and replacenant training programs for the facility staff are maint such programs meet or exceed the requirenants and recomme.ndations of Section 5 of ANS 3.1-(12/79 requirements specified in the MarchDraft) and Appendix "A" of 10 CFR Part 55 and the supplemental g
28, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the NSE.
6.5 REVIEW AMD AUDIT 6.5.1 STATION m/ diar SAFETY AND OPERATING COMMITTEE (SNSOC)-
FUNCTION 6.5.1.1 The SNSOC snail function to advise the Station Manager on all matters related to nuclear safety.
COMPOSITION i
6.5.1.2 The SNSOC shall be composed of the :
Chairnian:
Assistant Station Manager (Nuclear Safety and Licensing)
Vice Chairman-and Member:
Assistant Station Manager (Operations'and Maintenance) l Member:
Superintendent-Operations Member: Superintendent-Maintenance Member:
Superintendent-Radiological Protection Member:
' Superintendent-Engineering l
ALTERNATES 6.5.1.3 All alternate members shall be appcinted in writing by the SNSOC Chairman to serve on a temporary basis; however, no more than c'e alternate shall participate as a voting member in SNSOC activities at any one time.
NORTH ANNA-UNIT 1 645 Amendment No. J, H, 77,37 74 M.
126 135, p
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ADMINISTRATIVE CONTROLS MEETING FREQUENCY 4
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.
QUORUM 6.5.1.5 A quorum of the SNSOC consists of the Chairman or Vice-Chairman and two members including alternates.
RESPONSIBILITIES 6.5.1.6 The SNSOC shall be responsible for:
a.
Review of 1) all procedures required by Specifications 6.6.1. 6.8.2 and 6.8.3 and changes thereto, 2) all programs required by Specifica s
-tion 6.8.4 and changes thereto, 3) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear
. safety.
Review of all proposed changes or modifications to plant systems c.
or equipment that 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 Station Manager, Investigation of all violations of the-Technical Specifications e.
including the preparation and forwarding of reports covering evalua-tion and recomendations to prevent recurrence to-the.Vice President-Nuclear Optrations and the MSRC.
1 f.
Review of all REPORTABLE EVENTS and Special Report:,.
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 i
Safety and Operating Comittee'or Station Manager.
1.
Review of the Plant Security Plan and implementing proceduret'and shall submit recommended changes to the Station Manager.
1
- j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Station Manager.
NORTH ANNA - UNIT l 6-6 Amendment No. JJ, 30, 43,6 7p,pp, 135,.
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ADMINISTRATIVE CONTROLS k.
Review of every unplanned onsite release S1 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.
AUTHORITY 6.5.1.7 The SNSOC shall:
(.s 's #.4) through (c) above.
Pv k written approval or disapproval of items considered under a.
SNSOC approval shall be certified I
in writing by an Assistant Station Manager.
2 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 L4 hours' to the Vice President-Nuclear Operations and the Management Safety Review Committee (MSRC)'
of disagreement between the SNSOC and the' Station Managei; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS i
6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies-shall be provided to the Station Manager, Vice President-Nuclear 0perations-and the MSRC.
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6.5.2 MANAGEMENT SAFETY REVIEW COMMITTEE DiSRC) i FUNCTION 4
6.5.2.1. The MSRC shall function to provide' independent review < of designated l
activities in the areas of:-
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.i a.
Station Operations :
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b.
Maintenance' c.
Reactivity Management.
1 d.
Engineering e.
Chemistry and Radiochemistry i
f.
Radiological Safety
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Quality Assurance Practices h.
Emergency Preparednes',
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NORTH ANNA - UNIT 1 b7 Amendment No. 77,38,#$he,'#).135,
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ADMINISTRATIVE CONTROLS' COMPOSITION 6.5.2.2 The MSRC shall be composed of the MSRC Chairman and a minimum of four MSRC members.
The Chairman and all members of the MSRC shall have qualifications that meet the requirements of Section 4.7 of ANSI /ANS 3.1-1979 Rev. 1 (Draft).
ALTERNATES 4
6.5.2.3 All alternate members shall be appointed in writing by the MSRC t
Chairman to serve on a temporary basis; however,- no more than two alternates shall participate as voting members in MSRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants should be utilized as determined by the HSRC Chairman
.to provide expert advice to the MSRC.
1 MEETING FREQUENCY 6.5.2.5 The MSRC shall meet at least once per calendar quarter.
QUORUM 6.5.2.6 The minimum quorum of the MSRC necessary for the performance of the MSRC review and audit fur.ctions of these Technical Specifications shall consist of the Chairman or nis designated alternate and at least 50% of
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the MSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The MSRC shall be responsible for the review of:
The safety evaluations for 1) changes to procedures, equipment a.
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'unrev,iewed safety question.
b.
Proposed changes to procedures, equipment or systems'which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CFR.-
d.
Proposed changes to Technical Specifications or-this Operating License.
NORTH ANNA - UNIT 1 6-8 Amendment No. U,I7,39,77,135, t
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A'DMINISTRATIVE CONTROLS I
l-Violations of codes, regulations, orders, Technical Specifications,,
j e.
license requirements, or of internal proceoures.or instructions
,~
having nuclear safety significance, f.
Significant operating abnormalities or deviations from normal and; i'
expected performance of unit equipment that affect nuclear safety.
g.
Events requiring written notification to the Comission.
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, i.
Reports and meetings minutes of the SNSOC.
AUDITS 6.5.2.8 Audits of facility activities shall be performed unoer the cognizance of the MSRC.
These audits.shall encompass:
a.
The conformance of. facility operation to -
isions contained within the Technical Specifications and r - licable license conditions at least once per 12 months..
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l b.
The performance, training and qualifications of the entire facility.
l staff at least once per 12 months.
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- c.
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'The results of, actions taken to correct deficiencies occurring.in facility equipment, structures, systems or; method of operation
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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 50, at least once per 24 months.-
t The Emergency Plan and implementing procedures at least once e.
per 12 months.
f.
The Security Plan and. implementing procedures at least_once per I
12 months.
4 g.
Any other area of facility operation considered appropriate by the MSRC or the Vice President - Nuclear Operations.
h.
The Fire Protection Program and implementing procedures at-least once per 24 months.
h j
NORTH ANNA - UNIT 1 6-9 Amendment No. 19.53,75,99, 135, h ',
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ADMINISTRATIVE CONTR0t$-
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An independent fire protection and-loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an cutside 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.
j k.
The radiological environmental moni*' Ting program t d the results.
H
.thereof at least.once per 12 months.
1.
.The OFFSITE. DOSE CALCP(ATION MANUAL and implementing procedures
-l st least once per 12 months, i
LThe PROCESS CONTROL PROGRAM andLimplementing procedures for m.
. processing'and packaging of radioactive wastes at least.cnce per 12 months.
AUTHORITY 6.5.2.9 The-MSRC shall report to and advise the Senior Vice-President -
1 Nuclear on those areas of responsibility specified-in Sections 6.5.2.7 and 6.5.2.8.
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RECORDS 6.5.2.10 Records of PSRC activities shall be prepared, approved and distributed as indicated below:
1 r
Minutes of each NSRC meeting shall be prepared, approved and
.a.
i forwarded to the Senior Vice' President - Nuclear within'14 days i
of each meeting.
b.
Reports of reviews with safety significant findings encompassed 1'
by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President.- Nuclear-within 14 days 4
-following completion of the review.-
t Audit reports encompassed by Section 6.E.2.8 above, shall be c.
forwarded to the Senior Vice President - Nuclear andito the management ~ positions responsible for the areas audited within 30 days after completion of~the audit by the auditing crganization.
HORTH ANNA - UNIT 1 6-10 Amendment No. 19,39,47,45, m
79,99,135, i
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l NORTH ANNA - UNIT 1 6-11
- Amendment No. 3,5,77,39,43,73,7),
87,99,135,
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ADMINISTRATIVE CONTROLS 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 SNSOC.and the-results of this review shall be submitted to the Vice President-Nuclear' Operations and the MSRC.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is-violated:
The facility shall be placed in at least HOT STANDBY within a.
one hour, b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all' cases within one hour. The Vice Pres;ident-Nuclear Operattons and MSRC 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.
The report c.
shall be reviewed by the SNSOC.. 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.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the Vice President-Nuclear Operations and the t
MSRC within 14 days of the violation.
6.8-PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities raferenced below, The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
1 NORTH ANNA - UNIT 1 6-12 Amendment No. 3, 5,17, 30, 48,46 77 l pp,135,
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k UNITED STATES
.a NUCLEAR AEGULATORY COMMISSION i
'. i wAsmwatow, o. c. rosse :
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9 VIRGINIA ELECTRIC AND POWER COMPANY j
7 li' OLD DOMINION ELECTRIC COOPERATIVE i
D0CKET NO. 50-339 i
. NORTH ANNA POWER STATION. UNIT N0. 2-1j
~ AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No. 118 License No. NPF-7' I
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 February 1,1990, as: supplemented July 30, 1990, 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 r" %s and regulations of.
)
the Commission; C.
There is reasonable assurance (1)..Jat'the activities-authorized
.by this amendment can be conducted without endangering the. health and safety of the public, an? (ii) 'that such activities will be-conducted in compliance with the Connission's regulations;;
i D.
Theissuanceof,thisamendmentwillnotbetinimicalt0thecommon L
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 ll, 51 of.tMe Cunnission's regulations and.all applicable requirements j
have been satisfied.
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'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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B,-
as revised through Amendment No.1g
,;are hereby incorporated in the license.
The licensee sha 1 operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance and shall be implem..nted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 2
/
rbert N. Berkow, Director roject Directorate II-2
)
Division of Reactor Projects - I/II Office of Nuclea: eactor' Regulation
Attachment:
i Changes to the Technical Specifications Date of Issuance:
August 7,'1990
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- ATTACHMENT TO LICENSE AMENDMENT N0. ' 118-
-TO FACILITY OPERATING LICENSE'NO. NPF-7:
DOCKET-NO. 50-339 Replace the following pages of the Appendix."A" Technical' Specifications with the enclosed pages.as indicated.- The revised pages are identified by.
i amendment number and contain vertical lines indicating the area'of. change..
The corresponding overleaf pages are also provided to maintain document.
completeness.
P, age j
.6-1 6-6 6-7 6-E-6-9 6-10 6-11 6-12 i
6-13 l
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_6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation In his absence, the Assistant Station Manager-(Operations and Maintena be responsible for overall facility operation.
a Station Manager shall. ielegate in writing the succession to this respons y.
6.1.2 designated individuall shall be responsible for the Conhol
,a function and shall be the only individual that may direc the licensed activities of licensed operators.
A management directive to this effect, signed by the tenior Vir.e President - Nuclear, shall be reissued to all sta personnel on an annual basis.
6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 Onsite and Offsite Organization and corporate management.An onsite and an offsite organization shall b positions for activities affecting the safety of the nuclear power pla ration Lines of authority, responsibility a.
and defined for the highest managem,ent levels through intermediate to and including all operating organization positions.
shall be documented and updated, as appropriate, in the form of organ These relationships charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
in the UFSAR.-
These requirements shall be documented b.
and shall have control over those onsite activities nec n
operation and maintenance of the plant.
The Vice President-Nuclear Operations shal1~ have corporate responsibilit c.
overall plant nuclear safety and shall take any. measures needed to ensure y for 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 functio shall have sufficient organizational freedom including sufficient indepen from cost and schedule when opposed to safety considerations NORTH ANNA - UNIT 2 6-1 Amendment No. 77,67, gg,ll8,
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TABLE 6.2-1 (Continued)
- Shif t Supervisor with a Senior Reactor Operators License on Unit 2.
1 SRO - Individual with a Senior Reactor Operators License on Unit 2.
R0
- Individual with a Reactor Operators License on Unit 2.
-1 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 shit't 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.
Ouring 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 regarding working hours established for employees are followed.
In addition, procedures will provide for documentation of authorized deviations from these guidelines and that the documentation is'available for NRCireview.
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l NORTH ANNA-UNIT 2 6 Amendment No. 34
l ADMINISTRATIVE CONTRLS 6.3' FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of. the unit staff shall meet or exceed the minimum qualifica-tions of ANS 3.1-(12/79 Draft) for comparable positions and the supplemental requirements s except for (1)pecified in the March 28, 1980 NRC letter to all licensees, the-Superintendent - Radiological Protection who'shall meet or exceed the qualifications-of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent-in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
L 6.4 TRAINING 6.4.1 The Manager - Huclear. Training is responsible for ensuring that retraining l
and replacement training programs for the facility staff are maintained and that 3
such programs meet or exceed the requirements and recomendations of Section 5 i
ofANS3.1-(12/79 Oraft) and Appendix "A" of 10 CFR Part 55 and the supplemental s
requirements specified in the March 28, 1980 NRC letter to all; licensees, and
(
shall include familiarization with relevant industry operational experience identified by the NSE.
6.5 REVIEW AND AUDIT 6.5.1 STA? ION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)
FUNCTION 6.5.1.1 The CNSOC shall function to. advise the Station Manager on all matters related to nuclear safety.
COMPOSITION a
6.5.1.2 The SNSOC shall be composed of the :-
- r Chairman:
Assistant Station Manager (Nuclear Safety and' Licensin Assistant Station Manager (Operations: and Maintenance)g) l Vice Cha~irman and Member:
Member: Superintendent-Operations Member: Superintendent. Maintenance Member: Superintendent-Radiological Protection.
l.
Member: Suoerintendent-Engineering ALTERNATES i
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 alternate shall participate as a voting member in SNSOC activities at any one time..
NORTH ANNA-UNIT 2 6-6 Amendment No.M 67, /A, 7)$, '118,
i ADMINISTRATIVE CONTROLS MEETING FREQUENCY 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.
i QUORUM
- 6. 5. l '. 5 A quorum of the SNSOC consists of the Chairman'or Vice-Chairman and two members including alternates.
RESPONSIBILITIES 6 ! 1.6 The SNS00 shall be responsible for:-
2 Review of 1) all procedures required by Specifications 6.8.1, 6.8.2 and 6.8.3 and changes hereto, 2) all programs required by. Specifica-tion 6.8.4 and changes thereto, 3) any other proposed procedures or t
changes thereto as determined by the Station Manager to affect nuclear. safety.
b.
Review of all proposed tests and experiments _ that affect nuclear
- safety, Review of all proposed changes or modifications to. plant systems c.
or equipment that 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 Station Manager, Investigation _of-.all violations of the Technical Specifications-e.
including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the Vice President-Nuclear-Operations a'nd the MSRC.
f.
Review of all REPORTABLE EVENTS and-Special Reports.
Review of facility operations to detect potential nuclear safety, g.
- hazards, h.
Performance of special reviews, investigations or analyses and J
reports thereon as requested by the Chairman of the Station Nuclear Safety and Operating Committee or Station Manager; i.
Review of_ the Plant Security Plan -and implementing procedures and shall submit recommended changes to the Station-Manager j.
Review of the Emergency Plan and implementing procedures and shall submit reconnended changes to the Station Manager.
HORTH ANNA - UNIT 2 6-7 l
Amendment No. JJ, p J7, pp,
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ADMINISTRATIVE CONTROLS-t t
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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 ti.s forwarding of these reports to the Vice President.
~
Nuclear Operations and the Management Safety Review Committee.
i 1
Revf': changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
3 AUTHORITY 6.5.1.7 The $NSOC shall:
f a.
Provide' written approval or disapproval of. items considered under 6.5.1.6(a) through (c) ~ above.
SNSOC approvalLshall be certifled T
in writing by an Assistant. Station Manager.
b.
Render determinations in writing with regard to whether or not.
each item considered under 6.5.1.6(a) through1(e) above constitutes an unreviewed safety question, i
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 Orerations and the Management Safety Review Committee (MSRC)
(,
of disagreement between the SNSOC and the Station Manager; however.
the Station Manager shall have' responsibility-for. resolution of-such disagreements--. pursuant to 6.1.l'above.
+
RECORDS' 1
6.5.1.8 The, SNSOC shall maintain written minutes of each meeting and copies-shall be provided to the Station Manager, the Vice President-Nuclear Operations 4
and the MSRC.
6.5.2 MANAGEMENT SAFETY REVIEW COMMITTEE (MSRC)
FUNC TION 6.5.2.1 The MSRC shal'1 function to provide independent review of designated activities in the' areas of:
a.
Station Operations f
b.
Maintenance c.
Reactivity Management d.
Engineering l-e.
Chemistry and Radiochemistry f.
Radiological Safety l
g.
Quality Assurance Practices l
h.
Emergency Preparedness NORTH ANNA - UNIT 2 6-8 Amendment No. JJ JJ N/*86,118,
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J ADMINISTRATIVE CONTR01.S l
COMPOSITION 6.5.2.2 The MSRC'shall be composed of the MSRC Chairman and a minimum of four MSRC membet3 The Chairman and all members of the MSRC shall have qualifications that meet the requirements of Section 4.7 of ANS!/ANS 3.1-1979 Rev. 1 (Draft).
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the MSRC Chairman to serve on a temporary basis; however, no more than two alternates j
shall participate as voting members in MSRC activities at any.one time.
i CONSULTANTS 6.5.2.4 Consultants should be utilized as determined by the MSRC Chairman to provide expert advice to the MSRC.
s MEETING-FREQUENCY 6.5.2.5 The MSRC shall meet at least once per calendar quarter.
QUORUM i
6.5.2.6 The minimum quorum of the MSRC _necessary for the performance of the MSRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least 50% of the MSRC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The MSRC shall be responsible for the review of:
The safety evaluations for 1) changes to procedures, equipment a.
or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did nnt 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.
Proposed tests or experiments which involve an unreviewed c.
safety question as defined.in Section 50.59, 10 CFR..
d.
Proposed changes to Technical Specifications or this Operating License.
NORTH ANNA - UNIT 2 6-9 Amendment No. II,8f,118, 1
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o ADMINISTRATIVE, CONTROLS f
Violations of codes,. regulations, orders, Technical Specifications, e.
license requirements, or of internal-procedures or instructions having nuclear safety significance.
~
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-f.
Significant operating abnormalities or deviations from normal and I
expected performance of unit equipment that affect nuclear safety, g.
Events requiring written _ notification to the Commission.
i 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, i.
Reports and meetings minutes of the SNSOC.
~
AUDITS i
6.5.2.8 Audits of facility activities shall be performed under the-cognizance of the MSRC. These audits shall encompass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable. license conditions at least once per 12 months'.-
l b.
The performance, training: ant qualifications of the entire facility staff at least once per 12 n nths.
The results of actions taken to correct deficiencies occurring-in c.
facility equipment, structures.. systems or method of operation that affect! nuclear safety at'least once per 6 months.
L d.
The performance of-activities required by:the Operation'al! Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
t e.
The Emergency plan and implementing procedures,at least once per 12 months.
f.
The. Security Plan and implementing procedures at least once per 12 months.
4 g.
Any other area-'of facility. operation considered appropriate by.
4
[
the MSRC or the Vice President - Nuclear Operations.
h.
The Fire Protection Program and implementing procedures at least once per 24 months.
HORTH ANNA - UNIT 2 6-10 Amendment No. U,$7,67,85,118,
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p ADMINISTRATIVE CONTROLS l
1' A'n independent fire protection'and loss prevention inspection and-e audit shall be performed annually. utilizing etther qualified i
offsite licensee personnel or an outside fire protection firm, j
d
- 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.
[k
'1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures
[i at least once per 12 months.
i The PROCESS CONTROL PROGRAM and implementing procedures for-m.
. processing and packaging of radioactive wastes at least once i
per 12 months.
1 1
AUTHORITY l
6.5.2.9 The MSRC shall report to and advise the Senior Vice President -
Nuclear on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
L RECORDS 6.5.2.10 Records of MSRC activities shall be prepared, approved and distributed as indicated below:
Minutes of each MSRC meeting'shall'be prepared, approved and.
a.
forwarded to the Senior Vice President - Nuclear within 14 days of each meeting.
l b.
Reports of reviews with safety significant' findings encompassed
- 4 by Section 6.5.2.7 above, shall be prepared, approved and fonvarded to the Senior Vice President ' Nuclear within 14 days following completion of the-review.
Audit reports encompassed by Section 6.5.2.8 above, shall be-c.
forwarded to the Senior-Vice-President - Nuclear and-to the management positions responsible-for.the-areas audited within 30 days after completion of the audit by the auditing-i organization.
j NORTH ANNA - UNIT 2 6-11 Amendment No. II,39,67,8#,ll8, t
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NORTH ANNA-- UNIT 2 6-12 Amendment 'No. 77,37g,85,73,-
-85,
a.
ADMINISTRATIVE CONTROLS 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 SNSOC and the results of this review shall be submitted to the Vice President-Nuclear Operations-and the MSRC.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be-taken in the event a Safety Limit is violated:
i The facility shall be placed in at least HOT STANDBY within a.
one hour.
b; The NRC Operations Center shall be notified by telephone as soon-as possible and in all cases'within one hour..The Vice President-Nuclear Operations'and the HSRC 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 Vio'.ation Report shall be' prepared. The report c.
shall be reviewed by the SNSOC.
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, d.
The Safety Limit Violation Report shall be submitted to the Cnmmission, the Vice President-Nuclear Operations'and the-MSRC within 14 days of the violation.
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1 6.8 PROCEDURES -AND PROGRAMS 6.8.1 Written procedures shall' be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in. Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling o:erations.
NORTH ANNA - UNIT 2 6-13 Amendment No. JJ, 4157, 56,
- 118, i
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ADMINISTRATIVE CONTROLS c.
Surveillance and test activities of safety related equipment.
d.
Security P1an implementation.
e.
Emergency Plan implementation.
f.-
Fire Protection Program implementation.
g.
PROCESS CONTROL. PROGRAM implementation.
- h.. OFFSITE DOSE CALCULATION MANUAL implementation.
1.
Quality Assurance Program for effluent and environmental-monitoring, using the. guidance in Regulatory Guide 1.21, Revision' 1,. June 1974 and Regulatory Guide 4.1, Revision 1,-
4 April'1975.
- 6.8.2: Each procedure of 6.8.1 above, except 6.8.1.d and 6.8;1.e and changes thereto, shall be reviewed and approved by the $NSOC: prior to implettentation and reviewed periodically as set forth in administrative procedures.
Procedures of 6.8.1.d-and 6.8.1.e shall be reviewed and approved as per 6.5.1.6.1-and-6.5.1.6.J.
SNSOC approval shall be certified in writing by an Assistant j
i -
Station Manager, i
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1 6.8.3 Temporary changes.to procedures' of. 6.8'.1 {above may be made-provided:'
-l i
l a.
The.-intent of the original procedure is not altered..
l b.
The change is. approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's~ _
i 1
License on the unit affected, t
c.
The change is documented. reviewed a'nd approved by the SNSOC-within 14-days of-implementation. SNSOC approval.shall be j
certified in writing by an Assistant Station Manager.-
6.8.4 The following programs shall be established, implemented, and
' maintained:
a.
Primary Coolant Sources Outside Containment-3
~ A program to reduce leakage from those portions-of systems-3 outside containment that could contain-highly ' radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the recirculation.
spray,: safety injection, chemical and; volume control, gas'.
stripper, and hydrogen recombiners.. The program'shall l
include the following:
' (i)
Preventive maintenance and periodic visual inspection s
requirements and (ii)' Integrated leak test requirements for each system at i
refueling cycle intervals or less.
f NORTH. ANNA - UNIT 2 6-14 Amendment No. 31,67 o
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