ML19331E218

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Proposed Tech Spec Changes to Section 6,transferring Independent Review Responsibility from Sys Safety & Operating Committee to Safety Evaluation & Control Staff & Audit Responsibility to QA Dept
ML19331E218
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 08/28/1980
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19331E217 List:
References
NUDOCS 8009090347
Download: ML19331E218 (35)


Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE NORTH ANNA UNIT NO. 1 i

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0 009 '90 SQ7 w.- _

I: 23 70 6.0 ADMINISTRATIVE CO*iTROLS 6.1 Resp 0NSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility

'- '-iti g th: tu ::: ien to +h4 operation.and :h:!' d:1:g:t:

r::;;n:ibi'it; i.r'n; H : :b::nce. E EE ATTAc.w13 PAG E 6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shovm on Figure 6.2-1.-

FACILITY STAFF 6.2.2 The Facility organization shall, be ts shown on Figure 6.2-2 and:

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 Operator shall be in the control room when fuel is in the reactor,
c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor,
e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilitias during this operation.
f. A Fire Brigaje of at least 5 members shall be maintained onsite at all times' . The Fire Brigade 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.

' Fire BrigaQ composition may be less than the minimum requirement 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 Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirement.

NORTH ANNA UNIT i 6-1 5::t ent " 15 l

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- In his absence, the Assistant Station Manager shall be responsible for overall facility operation. During the absence of both, the Station Manager shall delegate in writing the succession of tnis responsibility.

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E XECUTIVE a

VICE PRESIDENT POWER' EXECUTIVE MANAGE R MANAGER MANAGER LICEIBSBNG ANE NUCLEAR NUCLEAR OUALITY A$$URAbCE OPERAT101BS & MAlWT. TECildl4 CAL SE AVICES DIRECTOR 00ALITY ASSURANCE NUCLEAR DIRECTOR DIRE CTOR DIRECTOR EllRECTOR STATION OMRAfl0N AND SAF E TY EVALUATION TECNellCAL L: M ISTR'd40 MANAGERS isAINTEN ANCE SE RVICES AND CONTROL ANALYS8$ NE ALTM PHYS 8CS I

STATION SUMRVISOR SAffiY ENGs4EERING SECTION SECTION SUMRVISOR SECTION SUPERVISOR

! SUMRVISOR OMRATION AND ADettkl3TRATIVE T RAINING MAINTEN ANCE SUPPORT SERVICES

' RESPONSIBLE FOR CORPOR ATE FIRE PROTECTION PROGRAM Offsite Organization for Facility Manaennent and Technical Support j

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S ,a ,9 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.

OUORUM 6.5.1.5 A quorum of the SNSOC shall consist 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 Specification 6.8.1 and changes thereto, 2) 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.
c. Review of all proposed changes to A:pendix "A" Technical Specifications,
d. Review of all proposed changes or modifications to plant systems or equipment that a'fect nuclear safety.

-va~ c. Neeu- Cwanne <.me' N u~,cc

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

~*0f rc:ter, ";:10 r 0; :t on and to the Ch;i ::n of th +,

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D.nece, bieb, E 4 6::co ac3 C.cAed.

f. Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notificaticn to the Commission.

g.- Review of facility operations to detect potential nuclear safety hazards.

6 Am:ndment "c NORTH ANNA --UNIT 1 t - _

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5 10 30 ADMINISTRATIVE CONTROLS

h. Perfomance of special reviews, investigations or analyses and reports thereon as requested by the Chaiman of the Staticn Nuclear Safety and Operat,ing Cemittee,
i. Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Chairman of the Station Nuclear Safety and Operating Committee.
j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Chaiman of the Station Nuclear Safety and Operating Comittee.

AUTHORITY 6.5.1.7 The SNSOC shall:

a. Recomend to the Station Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b. Render deteminations 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 Manager, Nuclear Operations and Maintenance and the Ch:f mr Of th: !y:t r ""c'e r 4..., .....r..... ., _ .itt:: of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have respcnsibility for resolution of such disagreemencs pursuant to 6.1.1 above.

TXcectoc, Safeq Evatuc6n and Cockrcl RECORDS 6.5.1.8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear Operations and Main-tenanc e a nd .. .. . . .... . . . . . . . . ~ . . . . . . . . . . . . , . . . . . , . . . . . . . , . ......

l 4.be. Direcbe , Sa,yeh EvduoMen ona Cc,4c.,\.

SWITY EVAluhTION AHD CONT 40L (SEC) 6.5.2 5!T'" '"JCLEA" S?? T "!O 0"E""I':C CC"""EE (!:c':5CC )

FUNCTION _ g.

6.5.2.1 The Sy" SOC shall function to provide independent review and l ated4 of designated activities in the areas of:

NORTH ANNA - UNIT 1 6-7  %;ni;nt .t."

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a. Nuclear power plant operations
b. fluclear engineering
c. Chemistry and radiochemistry
d. Metallurgy
e. Instrumentation and control
f. Radiological safety
g. Mechanical and electrical engineering
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CONSULTANTS D; e d ,, bVeq Evatua%n and Centre) 6.5.2.4 Consulta* t D' be utilized as determined by the Sj.::* C C hi 2.- to provisy u p 4d vice to the Sy"S^C.

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MORTH ANNA - UtlIT 1 6-8 f m:ndment "c. 17

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Composttion:

6.5.2.2' The SEC staff- shall be comp 5 sed of - the Director,- Safety Evaluation and Control and a minimum of.three staff _ specialists.

Each member of the SEC staff shall meet or exceed the minimum quall'Ications of ANSI' N 18.1-1971.

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2. Me : r: th:2 : *ncrity Of th: ;;crer :h:1' h:v: r: r::p:::f tf'ity fer Oper:tice Of th: :t:ti:n:.
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. REVIEW GEC staff:

6.5.2.7 The folicwing subjects shall be reviewed by the SYMS 00:

a. Written safety evaluations of changes in the stations as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report and tasts or experiments not described in the Safety Analysis Report which are completed without prior NRC approval 1 under the provisions of 10 CFR 50.59(a)(1). This review is to verify l that such changes, tests or experiments did not involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2) and is acccmplished by review of minutes of the Station Nuclear Safety and Operating Comnittda and the design change program.

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b. Proposed changes in procedures, proposed changes in the station, or proposed tests or experiments, any of which may involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2). Matters of this kind shall be referred  !

to the SyM500 by the Station Nuclear Safety and Operating Committee  !

f 11owing its(review prior to implementation. l SEC sbCf

c. Changes in the technical specifications or license amendments relating to nuclear safety prior to implementation except in those cases where the change is identical to a previously reviewed proposed change.
d. Violations and reportable occurrences such as:

NORTH ANNA - UNIT 1 6-9 i

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1 ADMINISTRATIVE CONTROLS REVIEW (Cont'd)

1. Violations of applicable codes, regulations, orders, Technical-Specifications, license requirements or internal procedures or instructions having safety significance;
2. .

Significant operating abnormalities or deviations from normal l or expected performance of station safety-related structures, systems, or components; and {

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3. Reportable occurrences as defined in the station Technical i Specificationf GM.t.e.

Review of events covered under this paragraph shall include the l results of any investigations made and reccmmendations resulting from such investigations to prevent or reduce the probability Of recurrence of the event.

e. Any other matter involving safe operation of the nuclear power s*,ations which ' ""'.," ',,a^'.*^A ""'-.~~4.'.'.'- ^ " . ^^-****^^ ~ ~ ~ ' ^ ... .-- ---- . - . . . . . . . . . -

d::r: :p r:prf:t: f:r ::r:fder:tte , or "'fch is referred to the

'jM'00 by the Station Nuclear Safety and Operating Cccuittee.

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  • l UORm SEC stdf Manager, NucleacTechrhal Ser&es 6.5.2.9 The SyNSOC shall report to and advise the Ex::uti;; Manager

' i::::ing and "u:lity * :ur:n: , who 'shall advise the Executive Vice d '

President - Pcwer on those areas of responsibility specified in Sectiong 6. 5.2.7. c.nd 5. 5. 2.S'. . I m kbe S.C t fJ.es and '

RECORDS SEC. and o Summo] shcll be 6.5.2.10 maintained -ad disseminated Records of Sy"50-C as indicated below activities

'ith' "shall  : ringbe preparedd:y: O (f :::.' ::t"n;-

cr f:l hwing :: ;'-ti:n Of th: rev h'.. Or audit. each calendae menth.

1. Executive Vice President-Power
2. tiuclear Power Station Managers
3. Manager, fluelear Operations and Maintenance
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e.," ". c a " Monager, Nuetear Techntca1 $ervices i

6.g. .Others that th'e Ch:i m:n Of th; Sy" SCC may designate.

Dkedce, Safe (7 Evabakt.on anci Conkcoi

5. Execuue Enagee , Licens;ng onA Nattj Assurance j 1

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6.5.3- Quality Assurance Department

- Function 6.5.3.1 The Quality Assurance Department shall function to audit station activities. These audits shall encompass:

-a. The conformance of facility operation to provisions contained within tne Technical Specifications and applicable license conditions at least once. per calendar year.

b. The performance, training and qualifications of the entire facility staff at least once per calendar year.
c. The results of actions taken to correct deficiencies occurring in facility equipment, structuras, systems or method of operation that affect nuclear safety at least twice per calendar year.
d. The perfomance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two calendar years,
e. The Station Emergency Plan and implementing procedures at least once per two calendar years,
f. The Station Security Plan and implementing proceaures at least once per two calendar years.
g. Any other area of' facility operation considered appropriate by the

! Executive Manager-Licensing and Quality Assurance or tne Executive Vice President-Power.

h. The Station-Fire Protection Program and implementing procedures at least once per two calendar years.
i. An independent fire protection anc loss prevention program inspection 4 and audit shall be performed at least once per calendar year utilizing l either qualified offsite licensee personnel or an outsice fire pro- l tection firm. I
j. An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outsice fire consultant at least once per tnree calencar years.

Authority 6.5.3.2l Tne Quality Assurance Department shall report to and advise the i Executive Manager, Licensing and Quality Assurance, who shall aavise the l Executive Vice President-Power on those areas of responsibility specified in section 6.5.3.1.

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Recordsi f.5.3;3 Records.of-the' Quality-Assurance Department audits ~shall be prepared and maintained in ' t he' department files. Audit reports shall be. disseminated ~

as indicated-below:

1. Nuclear Power' Station Manager
2. Manager -. Nuclear Operations and Maintenance

-3. Manager,- Nuclear-Technical Services.

4. Supervisor 1 Quality Assurance, Operations and Maintenance
5. -Supervisor of area audited
6. Nuclear Power Station Resident' Quality Control Engineer-

5 M 20 ADMINISTRATIVE CONTROLS '

6.6 rep 0RTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report subnitted-pursuant to the requirements of Specification 6.9.
b. 'Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the SNSOC and submitted to

- the SA SCC and the Manager, Nuclear Operations and Maintenance. l SEC sWF

, 6.7 SAFETY LIMIT-VIOLATION

. 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: 5

a. The facility shall be placed in at least HOT STANDBY within one hour.
b. The Safety Limit violation shall be reported to the Commission,

' the Manager, Nuclear Operations and Maintenance and to the

/:C C within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l SEC. sk?f
c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by tne SNSOC. This report shall describe (1) applicable circumstances preceding the violation, (2)

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effects of the violation upon facility ccmoonents, systens or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be subnitted to the Comission, the Of::r and the Manager, Nuclear Operations and Maintenance within 14 days of the violation.

SEC. staff I

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6-12 Meneent 'M "

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l ADMINISTRATIVE CONTRC' S

a. Records and drawing changes reflecting facility design modiff-cations made to systems and equipment described in the Final i Safety Analysis Report.
b. Records of new and irradiated fuel inventory, fuel transfers

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and assembly burnup histories.

c. Records of facility radiation and contamination sr.rveys.
d. Records of radiation exposure for all individuals entering radiation control areas.
e. Records of gaseous and liquid radioactive material released to the environs.
f. Records of transient or operational cycles for those facility components identified in Table 5.9-1.
g. Records of reactor tests and experiments
h. Records of training and qualification for current members of the plant staff.
i. Records of in-service inspections performed pursuant to these Technical Specifications.

J. Records of Quality Assurance activities required by the QA Manual.

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k. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1. Records of meetings of the SNSOC.and the SyMSOC.
m. SEE ATTACHED SHEET' I c , m. Records.of secondary water sampling and water quality. I 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel . radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel ra-diation exposure.

NORTH ANNA - UNIT 1 6- 21 a cndment Mc. 15 1.

_7,- _ _

m. Records of meetings of the System Nuclear Safety ana Operating Committee held prior to issuance of Amendment No. _ .

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ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGE I! ORTH ANNA UNIT NO, 2-l b j

4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation.

nd :h i' d;i:g t: in writing th: ;;;;;;;i:n t; thi: r::;:n:ibity der ng 'f: d absence. SEE ATTtsC.HED PAGE 6.1.2 The Shift Supervisor (or during his absence from the Controi Room, a designated individual) sha'l be responsible for the Control Room command function and shall be the cnly individual that may direct the licensed activ-ities of licensed operator 3. A management directive to this effect, signed by the Executive Vice President, Power, shall be reissued to all station personnel on an annual basis.
6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

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 a.aition, while the unit is in MODES 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 on site 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 Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
- e. A site Fire Brigade of at least 5 members shall be maintained onsite at all times.# The Fire Brigade 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.

l #The health physics technician and Fire Brigade composition may be less than r the minimum requirement 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 arcer i

to accommodate unexpected absence provided immediate action is taken to fill the required positions. '

NORTH ANNA - UNIT 2 6-1 l

t

.,~._ . -

W r

-In~ his absence, the Assistant Station Manager shall .be responsible

.for overall facility operation. - During -the absence of both, the Station Manager shall delegate .in writing the succession of tnis

. responsibility.

i 1-

._._.__.___.____._ _ -._____ __ _ _ _ _ . __ _ . . _ . _ . _ . . - __ . _ . _ . . . _ . . . _ _ .._.. _m.. _.. ~_

< e EXECUTIVE VICE PRESIDENT P0wtR' EXECUTIVE MANAGER MANAGER LICENSING AND MANAGER NUCLEAR NUCLEAR QUALITY ASSURANCE OPERATIONS & MAlef.

TECHNICAL SERVICES DIRECTOR QUALITY ASSURANCE NUCLEAR OIRECTOR DIRECTOR DIRECT.

STATION SIRECTOR OPERATION AND SAFETY EVALU ATION TECHN...t CHEMISTRY AND MANAGERS MAINTENANCE SERVICES AN0 CONTROL ANALYSi$ HE ALTH PHYSICS w

STATION SUPERVISOR SAFETY ENGINEERING SECTION SEE TION SUPERVISCR SECTION SUPERVISOR SUPERVISOR f)PERATION AND ADMINISTRATIVE TRAINING MA',NTEN ANCE SUPPORT SERVICES

' RESPONSIBLE FOR CORPORATE FIRE PROTECTION PROGRAM 1

f Of fsite Organization for Facility Management and Technical Support 1

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ADMINISTRATIVE CONTROLS h

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of tne facility staff shall meet or exceed the minimum qualifications of ANS N18.1-1971 for comparable positions and the supplemental requirements specified in the March 28, 1980 NRC letter to all licenses, except for the Supervisor-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

4 6.4 TRAINING 6.4.1 The Station Manager is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in the March 28, 1980 NRC letter to all licensees, and shall include familiarization with relevent industry operational experience identified by the t9E9-

{

SES.

6.5 REVIEW AND AUDIT

5. 5.1 STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

FUNCTION 6.5.1.1 The SNSOC shall function to advise the Station Manager on all matters related to nuclear safety.

COMPOSITION 4

6.5.1.2 The~SNSOC shall be ccuposed of the:

Chai rman:

babt Sterkn Nb =pe Station Manager Vice-Chairman: --> S r:r-* -tr-de-t ^;r r*

  • r ns l

. Member: Superintendent Maintenance Member: Superintendent - Technical Services Memoce : Lparinkerdenk - OperAkn3 l ALTERNATES 1

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 alternates shall participate as a voting member in SNSOC ' activities at any one time.

' NORTH ANNA - UNIT 2 6-6

~

I l

1

. 1 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. l QUORUM

6. 5.1. 5 A quorum of the SNSOC shall consist 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 Specification 6.8.1 and changes thereto, 2) all programs required by Specification 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.
c. Review of all proposed changes to Appendix "A" Technical Specifications.
d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Monaqer , Ndwe OcarcE.% and %mtenance_

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 Ofr::t:r, "u !::P

+ Op;r;tf:n: and to the Ch;frz:n :f th; Sy:te- "u !::r Safety and Op;r tin;; C:--itt::. Direche, $cSek Evejao y

u n and CeMeo).

- f, Review of eve.7ts requiring 24-hour written notification to the Commission.

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.

NORTH ANNA - UNIT 2 6-7

__ _ . _ _ _ .~. . - .

ADMINISTRATIVE CONTROLS -

1. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety ar;' Operating Committee.
j. Review :c the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operathg Committee.

AUTHORITY

6. 5.1. 7 The SNSOC shall:
a. Recommend to the Station Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
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 Manager, Nuclear Operations and Maintenance and the Chair;;n Of th Sj:te- "uclear

--+- 5;f;ty ;nd 0;.;r; ting C:--itte: of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

Dtredce, $c8eky Evab dien cmd Conic t RECORDS

6. 5.1. 8 The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear Operations and Maintenance and Ehe+t--
  • a-ef--tAe--Syst: "u:!::- 5:fety :nd Operit"g Cc-f ttee. Ene grace, hVeky E valuskien and b led. I SAFETY EVAtuATtc4 AND CcNTRot LSEC)

C. 5. 2 5" TE" NUCLEAR SAT C" ANO Or "AT NC COM" m EE (SSNSCC) l l FUNCTION SEC wtasF 6.5.2.1 The 6yN606 shall function to provide independent review and audit of I designated activities in the areas of: l

a. Nuclear power plant operations
b. Nuclear engineering NORTH ANNA - UNIT 2 6-8 1

ADMINISTRATIVE CONTROLS

c. Chemistry and radiochemistry
d. Metallurgy
e. Instrumentation and control
f. Radiological safety
g. Mechanical and electrical engineering
h. "s." . ' . ' . ' . , " _ - - - " . _ . . _ - -_...-+.#_-.

.. ~- . _ h n,,, W w e can'.ce'n uns' yuy l

ass.urance ories I

i. Other approp'riate fields associated with the unique characteristics l of the nuclear power plant.

l 1

COMPOSITION '

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I CONSULTANTS _  !

D;cector, $atig udeuen and Cc. Ace 4 6.5.2.4 Consultants shall be utilized as determined by the Sy" SOC C'-i-.- to provide expert advice to the Sy'.500.

SEC staW.

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NORTH ANNA'- UllIT 2 6-9

Composition 6.5.2.2 The SEC staff shall be composed of the Director, Safety Evaluation and Control and a minimum of three staff specialists.

Each member of the SEC staff shall meet or exceed the minimum qualifications of ANSI N 18.1-1971.

ADMINISTRATIVE CONTROLS

-0UO"UM

--676t?. 5 ^ queru Of th: Sy"5CC :h:!' cen:1 t cf not 100 th:n a majority of-th: tr.?:re er du!y ppc -ted :! tern:te: nd th " he subject te the fce'4ng i

constr:!-ts:

The Chri r:n :- "ic: Ch:f e:n ch:" be present f r  !' tecti ge.

2. We =^re than -i ne-i ty 04-ttk. querer cha!' 52'fe 'i"e espensib4'ity fer Oper:tien of the station:.
3. ^ :tien-::.rrying '/ te :::t cen:i:t of ne ! :: than thre: (3)'/eter.

u d

e mere th:n : i nerity of : queru :y bc :! tern:tes.

REVIEW 6.5.2.7 The following subjects shall be reviewed by the CyNCCC; SEC Mi'

a. Written safety evaluations of changes in the stations as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report and tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1). This review is to verify that such changes, tests or experiments did not involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2) and is accomplished by review of minutes of the Station Nuclear Safety and Operating Committee and the design change program.
b. Proposed changes in procedures, proposed changes in the station, or proposed tests or experiments, any of which may involve a change in the technical specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2). Matters of this' kind shall be referred to the SyNCCC by the Station Nuclear Safety and Operating Committee \

following itsVreview prior to implementation.

k SEC d4 -

c. Changes in the technical specifications or license amendments relating to nuclear safety prior to implementation except in those cases where the change is identical to a previously reviewed proposed change.

NORTH ANNA - UNIT 2 6-10

ADMINISTRATIVE CONTROLS REVIEW (Cont'd)

d. Violations and reportable occurrences such as:
1. Violations of applicable codes, regulations, orders, Technical Specifications, license requirements or internal procedures or instructions having safety significance;
2. Significant operating abnormalities or deviations from normal or expected performance of station safety-related structures, systems, or components; and
3. Reportable occurrences as defined in the station Technical Specificationfg 6.9.t.8. l Review of events covered under this paragraph shall include the results of any investigations made and recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
e. Any other matter involving safe operation of the nuclear power stations which a duly 2ppefated cubec--ittee c Oct.4ttee 0-be-der 2?preprist f r con:ider: tion, er which is referred to the syn CC by the Station Nuclear Safety and Operating Committee.

SEC itMC

f. Reports and meeting minutes of the Station Nuclear Safety and Operating Committee.

At!MTPF nVwesw

. . . . ww w w w w v w bh ww hb ca w b I w asw Of th: SyMSOC. Th::: :udit: :h:!' :n:cep::::

. The : nf:r::n : Of f: f'ity :p:r: tion t: previ:icn: :ntained within th; T;;hai;;l Sp;;ification; and appli;;bi; 'icen:: : ndition: :t le :t One: per 12 : nth:.
5. The p -f:re:n :, tr:f-ing nd ;uclification: of th: :ntir f: ility-5t:f# ?.t 1 ::t :n:: p r 12 centh .
c. The rece!t: ef ::ti:n: t:ker t correct deficiencie: eccur i"; ia-f::ility :q;ip;:nt, :tr; t r ;, :y:t ;; Or ::th:d Of Operati:n that
ffect ucl::r ::f:ty :t 1:::t On:: per 5 :: nth:.

NORTH ANNA - UNIT 2 6-11 1

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.4 O ADMINISTRATIVE CONTROLS a.

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AUTHORITY SEC ste Mager, Nadece te&nhd Sece 6.5.2.9 The Sy"S0" shall report to and advise the R:: tin ": .:ger - Licen:f g d 2nd ^u:1?ty ^.::ur ce, who shall advise the Executive Vice President - Power

, on those areas of responsibility specified in Section$ 6.5.2.7. 2nd S.S.2.3

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RECORDS 6 Ene $2C 6 .mcl a wmmcw #- al ce -

EC and 6.5.2.10 Records of syn 60G activities shall be preparedgmaintained and. &

disseminated as indicated below within ' .: r ing d:y: :.  :-' :--ti.g r

< m i. ,. m. . 4 .,._,.+4.,. ., .. + u. . ...4...... '.24+

.. --- .. each calendar mc.nih.

1. Executive Vice President-Power
2. Nuclear Power Station Managers
3. Manager . Nuclear Operations and Maintenance
4. ":-'er- ^' th: Sy""dC Mancyc-Nudeoc Technlcai brexs 6./. Others that the Ch:i- .:n Of th: Sy" SOC may designate.

hJter, %%k Eval.e b n and Cc.ntret S-Execu'd* Manaye - Licenang and Chuatt7 Asucc.nce NORTH ANNA - UNIT 2 6-12

1

~

6.5.3 Quality Assurance Department Function J

6.5.3.1 The Quality Assurance Department shall function to aucit station activities. These audits shall encompass:

a. The conformance of facility operation to provisions contained within tne Technical Specifications and applicable license conditions 'at

. least once per calendar. year.

1 ..

b. The performance, training and qualifications of the entire facility-staff at least once per calendar year.
c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least twice per calendar year.

, d. The perfonnance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, j at least once per two calendar years.

e. The Station Emergency Plan and implementing procedures at least once per. two calendar years.

l' f. The Station Security Plan and implementing procecures at least once per two calendar years,

g. Any other area of facility operation considered appropriate by the

' Executive Manager-Licensing and Quality Assurance or tne Executive Vice President-Power.

h. The Station Fire Protection Program and implementing procedures at 4 least once per two calendar years,
i. An independent. fire protection ano loss prevention program inspection and audit shall be performed at leas' once per calendar year utilizing either qualified offsite licensee personnel or an outsice fire pro-

. tection firm.

$ An inspection and audit of the fire protection and loss prevention

~

program shall be performed by a qualified outside fire consultant at least once per tnree calendar. years.

Authority 6.5.3.2 Tne Quality Assurance Department shall report to and advise the

- Executive Manager, Licensing-and Quality Assurance, who shall aavise the Executive Vice President-Power on those areas of responsibility specified in section 6.5.3.1.

J

A .i $'

Records-6.5.3.3. R'ec'ords of 'the Quality Assurance Department audits shall be prepared and maintained in the department files. Audit reports shall be disseminated

. as indicated below:

J1. Nuclear Power. Station Manager

2.  ; Manager - Nuclear Operations and Maintenance
3. Manager - Nuclear Technical Services ~

1 4. Supervisor - Quality-Assurance, Operations and Maintenance

  • 5 .~ Sepervisor of area audited
6. Nuclear Power Station Resident Quality Control Engineer 9

I J

ADMINISTRATIVE CONTROLS 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the SNSOC and submitted to the SyM50C and the Manager - Nuclear Operations and Maintenance.

Sic chaff {

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a, The facility shall be placed in at least HOT STANDBY within one hour.

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager, Nuclear l Operations and Maintenance, and the SyM500 shall be notified within l l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. MC MV
c. A Safety Limit Violation Report shall be prepared. The report 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 SyMSOC and the Manager - Nuclecr Operations and l Maintenance within414 days of the violation.

L SEC ske.Cf

_6. 8 PROCEDURES & PROGRAMS 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.
b. Refueling operations.

KORTH ANNA - UNIT 2 6-13

__ _ . _ , __ _ _ . _ . . ~ . - - - .

ADMINISTRATIVE CONTROLS

1. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
m. Records of meetings of the SNSOC.ed the 5;MSCC.
n. sE: CnCHC 7%GE
o. % _ Records of secondary water sampling and water quality.

' 6.11 RADIATION PROTECTION PROGRAM J

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit." Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation mointoring device which continously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated

, dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in the protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the f&cility Health Physicist in the Radiation Work Permit.

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt'from the RWP issuance requirement during the performance of their assigned radiation protection duties, provide they comply with approved radiatio. - otectinn proc:.dures for entry in high radiation areas.

NORTH ANNA - ljNIT 2 6-20 9

. _ , , -r. . --

. 7 Y

, . _ 7 h_

n. - r Records-of meetings.of tne System Nuclear Safety and Operatin'g Committee held prior to. issuance of Amendment No. .

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