ML19331D656

Proposed Tech Spec & ETS Changes Transferring Independent Review Responsibility from Existing Sys Nuclear Safety Operating Committee to Safety Evaluation & Control Staff

ML19331D656
Person / Time
Site:	North Anna
Issue date:	08/28/1980
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML19331D653	List: ML19331D652 ML19331D656
References
NUDOCS 8009030428
Download: ML19331D656 (44)

Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGE NORTH ANNA UNIT NO, 1 80099ggg]gg l

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1: 23 77 6.0 ADMINISTRATIVE CONTACLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation.:nd Ch:P d:10 gat: -iting th: :20:05 ic" to thi rt;; n;ibity dr# g 'i: lb::n 0. 6EE AT TACw 2.D PAG E 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. l FACILITY STAFF 6.2.2 The Facility organization shall, be as shewn 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 I 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 l 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. 1

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 responsibilities during this operation.

f. A 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.

Fire Brigade 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 1 6-1 "reneen: ".s l

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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EXECUIWE VICE PRE &idkNT PJWER*

EXECUHVE MANAGER MANAGER MANAGER LICEN51NG AND NUCLEAR NUCLEAR QUALITY A$$URANCE OPER ATIONS & MAINT. TECHNICAL SE RVICES DIRECTOR QUALITY

1. JSURANCE NUCLEAR DIRECTOR DIRECTOR DIRECTOR DIRECTOR STATION OPERA 180N AND SAFETV EVALUATION TECHNICAL CHEMISTRY AND MANAGERS M AINTEN ANCE SERVICES AN0 CONTROL ANALYSIS HE ALTH PHYSICS ST ail 0N SUPE RVISOR SAFETV ENGINE ERING SECTION SECTION SUPE RVISOR SECTION SUPE RVISOR SUPE RVISOR OPERAIl0N AND ADMINIST RATIVE TRAINING MAINTEN ANCE SUPPORT SE RVtCES j ' RESPONSIBLE FOR CORPORATE FIRE PROTECTION PROGRAM Of fsite Organization for Facility Manayment and Technical Support j

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ADMINISTRATIVE CONTROLS MEETING CREQUENCY 6.5.1.4 The SNSOC shall meet at least once per calendar month and as convened by the StiSOC Chairman or his designated alternate.

CUORUM 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 affect nuclear safer.y.

-va~ue, Ne ea- G:ecu _inc ced A. . enwm -

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

• • Cir::: r, '!ucle:r C;e at cn and to the Ch in:r of th:

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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 notification to the Comission.

g. Review of facility operations to detect potential nuclear  ;

safety hazards.

73:rd0Pt "C- '

f;0RTH ANNA - UNIT 1 6-6

5 10 30 ADMINISTRATIVE CONTROLS

h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairnan of the Station Nuclear Safety and Operating Cemittee.

i. Review of the Plant Security Plar and implementing procedures and shall submit reccmended changes to the Chaiman of the Station Nuclear Safety and Operating Committee.

j. Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Chairman 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:imar Of the Systr ': lear 4 Oc f:., ..~ .,. . - . , ., _ i th; of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have respcnsibility for resolution of such disagreements pursuant to 6.1.1 above.

ILector , Safeq Evaluab.n and Cenbct 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-tenance and Chci=r Of th; Systr ':::10:r 5:f ty rd Op: rat'rg SWtt::. l Abe Direcbc , hvey EvokaWen and to&o\.

SWETY EVALuhTION AND Cont;ot (sEc) 6.5.2 SYST7 '".'CLE?" S?"ETY "'O OPE'"I':0 00 "'I~EE '?r': SCC)

FUNCTION-SEC dcW 6.5.2.1 The Sy SOC- shall function to provide independent review aed l ated4+ of designated activities in the arcas of:

NORTH ANNA - UNIT 1 ,

6-7 unicnt t. "

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ADMINISTRATIVE CONTROLS

a. Nuclear power plant operations

b. Nuclear engineering

c. Chemistry and radiochemistry

d. Metallurgy

e. Instrumentation and control

f. Radiological safety

g. Mechanical and electrical engineering

h. Cd i'y::=.n:: pr::* ice' MmiedeArabe. cenkcc\s and guaRty assumnce pcucHces

1. Other appropriate fields associated with the unique char-acteristics of the nuclear power plant en.u nn e_ , . r n.,

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1 CONSULTANTS i Diredor, bWt) EvalucMen and Cen(tei J 6.5.2.4 Consultants shall be utilized as determined by the 5,.*EC~ l C hi .- to provide expert advice to the S/!!:C.  ;

SEC.skcM. l l

l NORTH ANNA - UNIT 1 6-8 -" :nd: nt '!O. F

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

Each member of the SEC staff shall meet or exceed the minimum qualifications of ANSI N 18.l'1971.

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6.5.2.5 The syMSCC :h!! meet at least once per ::londac-quarter during-th: !-f tf:? y::r :f f::f1ity :per::1:n f ?ler:1ng ft:1 :::dfn; :nd ::

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f the a.c.a.t.,en :r duly pp; int:d altsrn:t:: :nd shall 5:= ubje:t t: the- I fe!7:ufng ::::t=19t::

'. The Chi =r er "!:: Chai se the!' te p ereat fr- !!' e2 tings.

2. Me nr: tMr : *n:M ty f th que == : ul' h v: '*n: m:p:::ftf' tty fer ep:=tten ef th: :t:: ten:.

5. f =ti:n ::r ytng vet: meet c:r:t:t of re les: tMn three (3) veter.

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REVIEW GEC sWT:

6.5.2.7 The following subjects shall be revie=ed by the syM550:

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a. Written safety evaluations of changes in the stations as described in the Safety Analysis Report, changes in precedures as described in the Safety Analysis Report and tests or experir.ents 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 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 Comittee and the design change program.

b. proposed changes in procedures, proposed changes in the station, or procosed 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 Comittee following its(eview prior to implementation.

SEC MC

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

,o so , a.

ADMINISTRATIVE CONTROLS REVIEW (Cont'd)

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

2. Significant ocerating abnormalities or deviations from normal or expected performance of station safety-related structures, systems, or components; and

3. Reportable cc:urrences as defined in the station Technical Specification) C, 9 . t . 8 .

Review of events covered under this paragraph shall include the results of any investigations made and reccmmendations resulting frem such investigations to prevent or reduce the procability of recurrence of the event,

e. Any other matter involving safe operatian of the nuclear power s t.a t i ens w h i ch ' .'". '. ' '--.' '.. "".'.'...--i.'.*.^^.^.". ".#.--4'.'.^^.

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d:: : :ppr:tri:t: 'cr ::ntider: tier, er ^':5 is referred to the SyM*:C by the Station Nuclear Safety and Operating Ccemittee.

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SEC stdT Manager, Nuc\eacTecwt Seres 6.5.2.9 The -SyW3G shall report to and advise the E::::uti c: 'in n:g :r Licen ing :nd ~.:Tity '::ur:nco, who shall advise the Executive Vice M

President - Pc',.er on those areas of responsibility specified in Section/ 6.5.2.7. :nd 5.5.2.S.

m the S tC fJ.es and RECOROS SEC o summcq shcli be and 5.5.2.10 Reccrds of Sy" C activities shall be prepared { maintained and disseminated as indicated belcw "it"#- ' ' t : i ; d:y: :: :::' m::t' g '

er f:? ?: wing ::r;1:tien cf the reti:'.. Or :udit. toch Calendoc mcnth.

1. Executive Vice President-Power

2. Nuclear Power Station Managers

3. Manager, ?!uclear Operatiens and Maintenance 1

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. . - . . ". e. ". gonager , gut \ ear Technical gervh es

6. g. Others that the Ch:.i m:n cf th; Sy"50C may designate.

Direde.c, Safeh Evalua%n and Conkred

5. E secuWe Manager , 12censtn3 and Naty Assurance

!! ORTH AtlNA - UflIT 1 6-11 ^m : .d::-t "*. "

6.5.3 Quality Assurance Department Function 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.

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 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 ana loss prevention program inspection and audit shall be perfomed at least once per calendar year utilizing either qualified offsite licensee personnel or an outsiae fire pro-tection fim.

J. An inspection and audit of the fire protection and loss prevention program shall be perfomed by a qualified outsiae fire consultant at least once per tnree calenaar 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.

Records 6.5.3.3 Records of the Quality Assurance Department audite shall be prepared and maintained in the department files. Audit reports shall be dissemincted as indicated below:

1. Nuclear Power Station Manager

2. Manager - Nucicar Operations and Maintenance

3. Manager - Nuclear Technical Services

4. Supervisor - Quality Assurance, Operations and Maintenance

5. Supervisor of area audited

6. Nuclear Power Station Resident Quality Control Engineer

E M 20 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 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 Ccmmission shall be reviewed by the SNSOC and submitted to the SyMSGG and the Manager, Nuclear Operations and Maintenance. l SEC sb79 6.7 SAFETY LIMIT VIOLATION 6.7.1 The folicwing actions shall be taken in the event a Safety Limit is violated: s

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

b. The Safety Limit violation shall be reported ta the Commission,

' the Manager, Nuclear Operations and Maintenance and to the Sp: :: within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l SEC. skif

c. A Safety Limit Violation Re:: ort shall be prepared. The report shall be reviewed by tne SMSOC. This report shall describe (1) applicable circumstances creceding the violation, (2) effects of the violation upon facility comoonents, systens or structures, and (3) corrective action taken to prevent recurrence.

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

SEC. skaff NORTH ANNA - UNIT 1 6-12 kendment 'E "

12 28 IS ADMINISTRATIVE CONTROLS

a. Records and drawing changes reflecting facility design modiff-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility radiation and contamination surveys.

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 GA Manual.

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 SNSCC.and the Sy?!!OC.

m. SEE ATTACHED SHEET' I c . m. Records of secondary water sampling and water quality. I S . l'1 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 "o. 15

m. Records of meetings of the System fluclear Safety ana Operating Comittee held prior to issuance of Amendment flo. .

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ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGE NORTH ANNA UNIT No. 2-I I

6.0 ADMINISTRATIVE CONTRCLS 6.1 RESP 0NSIBILITY 6.1.1 The Station Manager shall be responsible for overall facility operation.

:h:!' d:::;;;; ' writing th: :;;;;;:i:n :: thi: c :;:n:iti'ity der e n; -f:

absence. SEE NT%C.HED PM 6.1.2 The Shift Supervisor (or during his absence from the Contro1 Room, a designated individual) shall be responsible for the Control Room cenmand function and shall be the only individual that may direct tne licensed activ-ities of licensed operators. A management directive to this effect, signed by the Executive Vice reesident, Power, shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 0FFSITE 6.2.1 The offsite organization for facility management and technical succort 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 addition, 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.

1. The health pnysics technician and Fire Brigade 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 provided immediate action is taken to fill the required positions.

NORTH ANNA - UNIT 2 6-1 t

. -. __= . _ . . . . _ __ . . _ . _ - _ __.

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

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E XECU TIVE VICE PRESIDENT POWER

• EXECUTIVE MANAGER MANAGER MAN AGE R LICENSING AND NUCLEAR huCLEAR QUALITY AS$URANCE OPER Ail 0NS & MAIN T. TECHNIC &L SERVICES DIRECTOR QUALITY ASSURANCE NUCLEAR OIRECTOR OIRECIOR DIRECTOR 51All0N OIRECTOR OPERAil0N AND SAFEIV EVALUA TION TECHNICAL CHEM 63TRY ANO MANAGERS MAINTEN ANCE SERVlfES AN0 CONTROL ANALYSl$ HE ALTH PHYSICS ST Ail 0N SUPERVISOR SAFETY ENGINE ERING SECTION SECTION SUPE RVISOR SEtI10M SUPE RVISOR SUPE RVISOR OPERATION AND ADMINISTRAllVE TRAINING MAINTEN ANCE SUPPORT SE RVICES i

' RESPONSIBLE FOR COHPORATE FIRE PHOTECTION PROGRAM i

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I ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI 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.

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 +9E9-(

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.

I l

1 COMPOSITION l

J

6. 5.1. 2 The SNSOC shall be composed of the:

- WWt StcEen Nb 7e Chairman: Station Manager Vice-Chai rman: --> S upe '-te-de-t - 0?r st 4 cns l

Member: Superintendent - Maintenance Member: Superintendent - Technical Services Memoce: 59ersnbdenk - OparAn3 l ALTERNATES

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.

l

' NORTH ANNA - UNIT 2 6-6 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.

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.

Mangee , %:.. ear CoaccL% cmd hntenance.

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 44rteter, "uclear

+ Cp;r:ti:n and to the Ch:f rz:r f th: Sy:ter "ucle:r ?:fety 3rd Cg r: ting C:r 'tte:. hrecLe, Sc8et' y Evdachkn ond Cc4 col.

f. Review of events 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.

l NORTH ANNA - UNIT 2 6-7 i

ADMINISTRATIVE CONTROLS -

i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operating Committee.

j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Station Nuclear Safety and Operating 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 Chai- r of th: Sj:te- "u 'e r

-->- 5 f;;y -J C p; r ;t i n g 0;r ' t t:0 of disagreement between the SNSOC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such cisagreements pursuant to 6.1.1 above.

htred.se, Sck y i&&. cwd C&cn 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 Ch;ir-m:r of the Sy:ter "ucle:r 5:fety :nd Ope st"; Cc-ittee. tne geme,

$cM7Evaldien and C A rd.

SMETY EVAtuATtt4 WD CcxTRct (.5Ed 6.5.2 5"STE!1 i;UCLEArs CAT "' At 0 OP PATIt:0 00""T : (5/'500) l FUNCTION M.C dt4F l 6.5.2.1 The syn 606 shall function to provide independent review and zudit of designated activities in the areas of: l

a. Nuclear power plant operations I

b. Nuclear engineering NORTH ANNA - UNIT 2 6-8

ADMINISTRATIVE CONTROLS

c. Chemistry and radiochemistry

d. Metallurgy

e. Instrumentation and control

f. Radiological safety

g. Mechanical and electrical engineering

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

COMPOSITION 6.5.2.2 ^^ SEE AmCnD NE'

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CONSULTANTS Dicee.cc , be et, . Wun om, Ce.4ca I v 6.5.2.4 Consultants shall be utilized as determined by the Sy" SCC C' '- a to provide expert auvice to the Sy" SCC.

SEC stcW. l e

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NORTH ANNA - UNIT 2 6-9 I

l t

d 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 or the SEC staff shall meet or exceed the minimum

! qualifications of ANSI N 18.1-1971.

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ADMINISTRATIVE CONTROLS OUO"U" 5.5.2.5 ^ queru: Of the SyMSCC ch:!' con:f:t Of net 10 : ther a majority of-th: ::.-b e r t er du!y ppe'ated :! tern:te: 2nd th:!' be subject to the #0c'4ag con:trafatt:

The Ch:f : c- "fce Ch 4 e:r ch:!' be present for 21' ectfagc.

2. Me ?cre than -incrity of the queru.? cha!' have '49e *esponsib414ty for 0"eratier of the st:tfens.

2. ^ ectfer-: rrying vetc :::t consist Of nc 10:: th:r three (?) veter.

"O ?cre th2- 2 -incrf ty Of : quorum may bc alternates.

REVIEW 6.5.2.7 The following subjects shall be reviewed by the Cy"500: SEC d6

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 16 CFR 50.59(a)(2) and is accomplished by review of minutes of the Station Nuclear Safety and Operating Comeittee 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 Sj"500 by the Station Nuclear Safety and Operating Committee l following itsVreview prior to implementation.

SEC stc4 -

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 Specificationyg 6.3. t.16. 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 du'y 2;;c4"ted cubec--ittee er re--ittee -^-ber d:r : 2;prepri te for con:ider:ti n, or '*ich is referred to the SyNSCC by the Station Nuclear Safety and Operating Committee.

SECS'aW

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

A i tM T ?P nUWA ss

5. 5. 2. 9 Audit: Of tation ::ti.itic; :h:ll b perf r;;d und:r th ::gni::nt: -

Of the SyMSOC. Th::: : dit: :h:!' :nce ;::::

. The ::nfert:n:: Of f::i'ity Operation t: pr vi:fon: ::ntained withi-th; T :hnic;l Sp :ific;ti:n; :nd :pplic:ble 'icen  ::nditi:n: It 1:2:t ent: per 12 : nths.

b. The perfert:n :, tr:i 'n; :nd qu:lific:ti:n: cf th: :ntir: f :i'ity-t:f' at !:::t On:: p:r 12 :: nth:.

c. The rece!!: Of ::ti n: t:ker t: rrect deficiencic: :: Cur iag 4"-

f::ility equip;;nt, :tructur::, ;y;t;;; cr ::th:d f per:ti:n th:t-affect acclear ::fety :t 1:20t ::: per S conth .

I NORTH ANNA - UNIT 2 6-11

ADMINISTRATIVE CONTROLS

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AUTHORITY _ _

SEC s+4' Mtwue , E t w te s n,u d b u h a n 6.5.2.9 The SyNSOC shall report to and advise the E a tie: ": :g: r - Li c e r.c i ^ g *J

nd Qu:'ity ^.::uren:2, who shill advise the Executive Vice President - Power on those areas of responsibility specified in Section$ 6.5.2.7.and 5.5.2.3

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RECORDS in v e S'C. L es W cen , et surnmac y .+-W ce -

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<,,,,m.._.4.,,, -._..m r ~ - - -- -- ' ' - ' - - __ -- ' ..' - - - tC4b tdleGdar TC,0b e

1. Executive Vice President-Power

2. Nuclear Power Station Managers

3. Manager - Nuclear Operations and Maintenance l

4. Pe-her: ef th: SyMSOC. Managec-Nudeor ==-technical haces l G. f. Others that the Chai- Or. Of th SyMSOC-may designate.

% eaer,S.Ja Eva W 6 c4 Cmtra S- 7 bucunce hecue MemoTc - Licenun3 and Cauan/

NORTH ANNA - UNIT 2 6-12

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

a. The confomance 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 qualifi. cations 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 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 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 least once per two calendar years.

i. An independent fire protection ana loss prevention program inspection and audit shall be performed at least once per calendar year utilizing either qualified offsite licensee personnel or an outsice fire pro-tection firm.

j. 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 calenaar years.

Authori ty 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.

Records 6.5.3.3 Records of the Quality Assurance Department audits shall be prepared and maintained in the 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. Supervisbr - Quality Assurance, Operations and Maintenance

5. Supervisor of area audited

6. Nuclear Power Station Resident Quality Control Engineer f

l 1

AOMINISTRATIVE 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 Sy"!?C and the Manager - Nuclear Operations and Maintenance.

SEC utoff l 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 '

possible and in all cases within one hour. The Manager, Nuclear Operations and Maintenance, and the Sy"!:C shall be notified within l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. SEC skais

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 Sy" SCC and the Manager - Nuclear Operations ar. l Maintenance within)14 days of the violation.

' SEC s' c.ff t 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.

NORTH 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. Recordt of meetings of the SNSOC.:.mt th: 5,MSCC.

n.  %= , . . ^CH ED McE o 14 Records of secondary water sampling and water quality.

6.11 RADIATION PROTECTION PROGRAM 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 ocesonnel 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 meem/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 Pe rmi t.

• 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 maintoring 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 facility 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 radiation protection proctdures for entry in high radiation areas.

NORTH ANNA - UNIT 2 6-20 l

n. Records of meetings of tne System fluclear Safety and Operating Committee held prior to issuance of Amendment flo. .

w.

ATTACH 1!ENT 3 PROPOSED ENVIRCN1 ENTAL TECHNICAL SPECIFICATION CHANGE NORTH AN';A UNITS NO. 1 AND NO. 2 l

c. Review of proposed written procedures required by Sections 5.5.2 and 5.5.3 below and changes thereto, which affect the environmental impact of the station.

d. Review of proposed changes to station systems to determine the environmental impact of the changes.

e. Investigation of all reported instances of violation of the Environmental Technical Specifications; and where the investiga-tion indicates, evaluation and formulation of recomendations to prevent recurrence,

f. Review of environmental monitoring programs to detect potential or existing significant adverse environmental impacts that have not been evaluated, or that are significantly greater than that evaluated by the Comission.

5.3.1.3 Authority The SNSOC shall:

a. Review the environmental evaluation of all changes described in Section 5.3.1.2 a, b and c, above. When the evaluation indicates that such activity may result in a significant adverse environ-mental impact that was not evaluated, or that is significantly greater than that evaluated by the Commission, the SNSOC shall ensure that a written evaluation of such activities is provided i

to and prior approval is obtained from the Director of Nuclear Reactor Regulation for the activities.

b. If the SNSOC determines that unexpected harmful effects or evidence of irreversible damage are occurring as a result of operation of the station, the SNSCC shall ensure that an acceptable analysis of :he problem and a plan of action to eliminate or significantly reduce the harmful effects or damage is submitted to the Comission for review and approval.

l c. Review writter reports precared as a result of investigations and reviews conducted under 5.3.1.2 a, e and f.

5.3.1.4 Records The SNSOC shall maintain written minutes of each meeting and copies shall be provided to the Ch:im:n f the Sy: tem :!uch:r s:f;t.' :nd Cpar:t' : C0ritt:: (Sf!!CC) . %ecAcc, Said7 Evakau.n and Centea. -

5-3 W! ? "?

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L Gky Assurance D epaAm.nh  !

5.3.2 Su::rm : r, Cu:P tr ': cur n::. C ration: :nd " i-t nan :

5.3.2.1 Function Guou A The Super"h.or i ,ssurance Depa^mentquality i:: uran :, Cperation: :nd "' int:n:nce shal perform independent audits of the implementation of the Environmental Technical Specifications.

5.3.2.2 Audits The following audits shall be completed:

a. The conformance of facility operation to provisions contained within these Environmental Technical Specifications and applica-ble license conditions at least once per 12 cenths,

b. The performance, training and qualifications of the facility staff involved in ensuring and monitoring compliance with these Environmental Technical Specifications at least once per 12 months.

c. The rasults of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect the environmental impact of the station at least once per 12 months.

5.3.2.3 Records provide a written report of the results of the audits required by 5.3.2.2 above to the SNSOC, the :j." C and the Station Manager.

Sday EvoLaLn ad Cenkt (sEc.

5.3.3 Syste "; 12:r S fety and 0::-)it' ; C:-it- sEc show'"S:C) tt: (S.

5.3.3.1 Function SEC staW .

The Sg"::: as described in Section 6.5.2 of Appendix A of this license, l shall function to provide independent review of designated activities related to the environmental impact of the station.

5.3.2.2 Review SGC staW The S.,NSCC shall review and, where necessary, comment on the results of the reviews conducted by the SNSOC and the independent audits conducted by the Supervisor, Cu:lity 13:ur:nce, Cper. tion: and "2i't22 020-boh yAsssance h g w ent d 5-4 90Y  : T7

5.3.3.3 Resconsibility 'y "

u gg, The $EC stawy"500 has the responsibility for ensuring9 that the station is operated in accordance with the requirements of this license and applicable NRC regulations.

5.3.3.4 Authority SEC stag Manao.er , Sc\eae Tech 4 cut Servn.es The Sy" SCC shall report to and advise the Ex::uti e: ":r ;ce- 2)

Licensin; :nd Ou:!#t; *::uranc:, who shall advise the Executive Vice President-Power on those areas relating to the environmental impact of the station.

5.3.3.5 Records T1: 53 .'!!C0 :h:l' : f-t:f- 4tt:r 49ete: c' 2:c" :: #a; -d 3

py :hal' t: provid:d to th: : r #tt : ::mbcr: :nd t' Ex Cutiv "i.: ' ::id:nt ?:xcr :P th0:0 cr::: ':!:t' ; t: t":

On"ir creert:1 #mp::t :? t5: tatica SEE ATTACHED PAGE 5.4 State and Federal Permits and Certificates The licensee shall comply with the provisions of the permits and certificates issued by the Commonwealth of Virginia to North Anna Power Station Under the provisions of Section 401 and 402 of the Federal Water Pollution Control Act, as amended.

5.5 Procedures 5.5.i Written Procedures Detailed written procedures, including appli:able checklists and instructions, shall be prepared and followed for all activities involved in carrying out the Environmental Technical Specifications as defined in Sections 5.5.2, 5.5.3, and 5.5.4, below. Procedures shall include sampling, data recording and storage, instrument calibration, measure-ments and analyses, and actions to be taken when limits are appecached or exceeded. Testing frequency of any alarm shall be included. These frequen:fes shall be determined from experience with similar instru-ments f similar environments and fecm manufacturer's technical manuals.

5.5.2 0:eratine Procedures Plant standard operating procedures shall include provisions, in addition to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Environ-mental Technical Specifications.

"y '?, '??? '7-NORTH AHMA - UNIT 1 5-5 ndmen t ": .

4 l

l

5.3.3.5 Records Records of SEC activities relating to the environmental impact of the station shall be prepared and maintained in the SEC files and a summary shall be disseminated as indicated below each calender month.

1. Executive Vice President - Power.

2. . Nuclear Power Station Managers

3. Manager, Nuclear Operations and Maintenance

4. Manager, Nuclear Technical Services

5. Executive Manager, Licensing and Quality Assurance

6. Others that the Director, Safety Evaluation and Control may designate.

i-6

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1

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I

c. Review of proposed written precadures required by Sections 5.5.2 and 5.5.3 belcw and changes theretc, which affect the environmental impact of the station. .

d. Review of preposed changes to station systems to detar=ine the environmental impact of the changes.

e. Investigation of all reported instances of violation of the Environmental Technical Specifications; and where the investiga ~.,

tion indicates, evaluaticn and formulatica of recc=mendat.icns es prevent recurrence.

f. Review of envircnmental monitoring programs to detect potential or existing significant adversa environmental impacts that have not been evaluated, or that are significantly greater than that evaluated by the Cc= mission.

5.3.1.3 Authcri ty_

The SNSCC shall:

a. Review the environmental evaluation of all changes described in Section 5.3.1.2 a, b and c, above. When the evaluation indicates that such activity may result in a sigr.ificant adverse enviren-mental impact that was not evaluated, or that is significantly greater than that evaluated by the Ccenissien, the SNSCC shall ensure that a written evaluatica of such activities is previded to and prior approval is cbtained from the Director of Nuclear Reactor Regulation for the activities.

b. If the SN5CC determines that unex;ected harmful effects er evidence of irreve. sible damage are occurring as a result of operaticn of the station, the SitSCC shall ensure that an acceptaSte analysts of the problem and a plan of action to eliminate er significantly reduce the harmful effects or damage is submitted to the Cc=nis:fon fer review and approval.

c. Review written reports prepared as a result of investigations and reviews conducted under 5.3.1.2 a, e-and f.

5.3.1.4 Records The SNSCC shall maintain written minutes of each meeting and ccpies shall be provided to the ch:f- :n :f the Sy:t:- Muc!:1- Saf:ty :nd C;2 sti ; C --itt:c (Sp!!CC) . ~Direcbr , ScGeh EvoLaWcn and 0.cntrol.

I 5-3 l ,

i i

OuaKly':Assuranc.e

r, 02:! f t:e DepaAm.nt S:Ur:str. C: r:ti:n -M ":'-t:-inte-l 5.3.2 L::.-

5.3.2.1 Function l De=mewet Quad ; iAssurancer, 02:?!!y Sduc:n;:, 0;;r::i:::

The 4tepc. :nd " int:n:::: shall perfor:n independent audits of the implementatica cf the Envirencen al Technical Specifications.

5.3.2.2 Audits The following audits shall be ccmpleted:

a. TM conformance 'of facility operation to provisions centained within these Envirencental Technical Specifications and applica-ble license cccditicas at least once per 12 mcnths.

b .. The perfor: nance, training and qualifications of'tne facility staff involved in ensuring and monitoring ccmpliance with these Environmental Technical Specifications at least once per 12 months.

c. The results of actions taken to correct deficiencies occurrine in facility equipment, structures, systems or method of operaticit that affect the environmental impact of the station at least once per 12 months.

5.3.2.3 he:rds Frevide a written report of the results of the audits required by 5.3.2.2 above to the SNSOC, the W^ ,and the Statica ."anacar.

E SEC skaff 5.3.3 Sate.t S re t e.

"vduckLa and C<.nied (SEC) ce': - $2'et'f and C::n:t'- 0: 'tt:: (!/!!:C]

5.3.3.1 Function _

S=.C sk95 The E-p!4G as described in Secticn 6.5.2 of Appendix A of this Itcense, l shall function to provide independent review of designated activities related to the environmental impact of the station.

5.3.3.2 Review SEC sbFf The syMSGG shall review and, where necessary, ccm::ent on the results of the reviews conducted by the SNSCC and the independent audits ccaducted by the E p:rf:Or, 02:?!!y 4:Ur:nt , Cp:rati ::~::d I;2120" N Qudit Assuranc.e y Departmenk.

1 1

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5.3.3.3 R_;_s cens ib i l i ty ,Neufw upocopegA,, egygus, SEC sL-JF y

• The Sy"50C has the responsibility f:r ensuring that the stat'on is l ocerated in accordance with the re:uirements.of .r.is licarse and

.pplicable NRC regulaticns. ,

5.3.3.4 Authority _

SEC sbff C"C3*# > bChr k' b"O +

The SjN000 sna11 report to and advise the S : ti : " :;;r-Lic n;!ng and Quclity ".::urance, who shall advise the Secutive Vice President-Power on those areas relating to the environmental impact of the station.

5.3.3.5 ~

Records SEE ATTNCHED ? AGE U. SyM500 Chal' cint:f r '-! tten #"'/ter c' eech "eet#"; " " ' ' '

py : hcl' 50 provided to th: :: -itt : ,::b:= nd th:

0;;utive Vic: Prc;ident F;w:r :n th::: : = :: nl: ting :: th:

envircr:ent:1 imp::t f th: :t: tion.

5.4 State and Federal Per=its and Certificaty.,

Nant 5.5 Frocedures 5.5.1 Written Frocedures

~Cetailed written procedu.es, including applicable checklists and instructions, shall be prepared and follcwed for all activities invched in carrying out the Environmental Technical Scicificatter.s as da rined in Sections 5.5.2, 5.5.3, and 5.5.4, beicw. F.ocedures shall ir.clude sampling, data recording and stcrage, instr. ment calibration, mcisure-menes and analyses, and actions to be taken whan limits are appr: ached or exceeded. Testing frequency of any alarm shall be included. These frequencies shall be determined fr:m experience with similar instru-ments in similar environments and from nanufacturer's technical rar.u_1s.

5.5.2 Ooerating Procedures Plant standard operating procedures shall include provisions, in addition 'to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Envir:n-mental Technical Sp,ecifications.

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5.3.3.5 Records

~

. Records of SEC activities relating to the environmental impacc of the station shall be prepared and maintained in the SEC files and a summary shall be disseminated as indicated below each calender month.

1. Executive Vice President - Power

2. Nuclear Power Station Managers

3. Manager, Nuclear Operations and Maintenance

4. Manager, Nuclear Technical Services

5. Executive Manager, Licensing and Quality Assurance

6. Others that the Director, Safety Evaluation and Control may designate.

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