ML20065G275

Proposed Tech Specs Revising Section 6.0, Administrative Controls, to Delete Specific Refs to Staff Positions & Plant Safety Committee Compositions

ML20065G275
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/09/1990
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20065G273	List: 0CAN109002, Application for Amends to Licenses DPR-51 & NPF-6,revising Tech Spec Section 6.0, Administrative Controls, to Delete Specific Refs to Staff Positions & Plant Safety Committee Compositions ML20065G275
References
GL-88-06, GL-88-6, NUDOCS 9010190019
Download: ML20065G275 (21)

Text

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4 PROPOSED TECHNICAL SPECIFICATI0N' CHANGES

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s 6.0 ADMINISTRATIVE CONTROLS

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6.1 RESPONSIBILITY q

6.1.1 The Vice President, Operations ANO shall be responsible for-

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l overa11' facility operation and shall delegate in writing the

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succession to this responsibility ~during his absence.

s 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS l

Onstte and offsite organizations 'shall be established. for unit.

operation and corporate' management,'respectively.

The onsite and l

offsite organizations shall include the. positions for activities affecting the: safety of.the nuclear power plant.

a.

Lines of authority, responsibility, and communic ~ation shall-be established and defined for the highest' management levels through intermediate levels to:and including all operating

.i organization positions.

These' relationships <shall.be=

documented and' updated,'as appropriate, in the' form of organization charts, functional descriptions of departmental.

responsibilities and relationships; and job descriptions for key personnel positions, or~ in equivalent forms of documentation. These requirements shall be: documented in the QA Manual Operations.

b.

The Director, Operations shall. be responsibleL for overall unit.

safe operation and shall.have control.over those onsite activities necessary for safe operation and maintenanc.e of the plant.-

c.

The Vice President, Operatiors ANO shal_l' have' corporate -

responsibility;for overall plant? nuclear' safety;and;shall.take1 any measures needed to ensure acceptable performance ofcthe-l l

staff in operating. mahtaining,-and providing. technical.

support to the plant to ensure nuclearLsafety.

d.

The individuals who train the operati_ g staff! andithose who n

carry out= health-physics and quality' assurance: functions-may L report to the appropriate onsite manager;i however, ;they' shall-have sufficient organizational ~ freedom to ensure their

independence from operating pressures.L l

FACILITY STAFF 6.2.2 The Manager, Operations-and Shift S'upervison shall'holdD J

a senior _ reactor operator 1_icense.

Each'on-duty.shiftishall.be!

composed of at least the minimum shift crew composition shown' in Table 6.2-1.

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Amendment No..JS,- 30,34,.37, 117i y

A7, EE, 59. EA, Et, EE, 99 19E,-122, J2A,'

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6.2.2.1 Administrative controls shall. be established to' limit the 1

amount of overtime worked by plant staf f performing-1 safety-related functions.

These administrative controls shall-be in accordance with the guidance provided by the NRC Policy L

Statement on working hours (Generic Letter 82-12),

j 6.3.

FACILITY STAFF OUALIFICATIS H 6.3.1 Each member of the facility staff shall meet-or exceed the minimum; qualifications of ANSI'N18.1-1971 for comparable-position, except for (1) the designated. radiation protection -

manager, who shall meet or exceed the_ qualifications of H

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.

a' 6.4 TRAINING 6.4.1 A retraining and~ replacement training program for the unit' staff shall be maintained.under the direction ofLthe Manager, Training and Emergency Planning and shall meet or exceed the-requirements and recommendations of Section 5.5 of ANSI-.

t N18.1-1971 and Appendix "A" of 10 CFR-Part 55.-

o 6.4.2 A training program for the Fire' Brigade shal1! be maintained H

under the direction;of the Manager,_ Training and Emergency Planning and shall meet or exceed-the requirements of Section 1

27 of the NFPA Code-1975 except for. Fire. Brigade training-sessions which shall be held at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function

~

1 6.5.1.1 The Plant Safety Committee shall function to advise the Director, Operations and Plant Manager, ANO-1 on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Safety Committee shall'be composed oflat?least eight-members of'ANO onsite management organization-at'the.

superintendent' level or above. 'The PSC Chairman shall ensure that adequate expertise.is present during meetings to evaluate.-

material before the PSC.

In addition, the Director, Operations shall designate ih i.

writing a PSC Chairman'and at least one Alternate Chairman..

' i Amendment No. JE, 39, 34, 37, 117a 47, EP, EP,.EA, 82, EE, 99: 109, 122, 224, s

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' ALTERNATES 1

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6.5.1.3'

'All alternate members shall be appointed in writing,by the PSC.

Chairman to serve _on a_ temporary basis; however, no more than J

two alternates shall participate as voting members in PSC activities at any one time.,

MEETING FRE0l H Cl 6.5.1.4 The PSC shall meet at least once per calendar month and:as convened by the PSC Chairman or his designated alternate.

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6.5.1.5 The minimum quorum of the PSC necessary for the performance of

. 5 the PSC responsibility and authority provisions of these technical specifications shall' consist of the Chairman or.his designated alternate and four' members including alternates.'

RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be re: pani,ible for:

a.

Review of 1). all procedures. required by, Specification 6.8 and changes'in intent thereto, 2) any_other l

proposed procedures or revisions thereto as.

determined by the Director,;0perations or Plant'.

Manager ANO-1 to affect nuclear safety.

b.

Review of all proposed. tests and experiments that affect nuclear safety.

-1 c.

Review of all-proposed changes to.the' Appendix "A" Technical. Specifications.

d.

Review of al_1 proposed changes-or modifications-to" plant systems or.equipm_ent that affect. nuclear safety.

Investigation of=all. violations of the Technical l

e.

l' fpecifications,. including the. preparation and "orwarding of reports covering. evaluation and recommendations 1to prevent. recurrence to-the' Plant i

Manager,'ANO-1, Director,10perations;and to the-Chairman of theLSafety Review Committee.

f.

Review of REPORTABLE EVENTS.

a u

g.

Review of_ facility operations to" detect potential' nuclear safety hazards.

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Amendment.No. SE, 99, J07,::JJ2, JJS, J24, 121:.

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Performance of special-reviews, investigati_ons, Lor'.

analyses and reports thereon as requested by the P_lant.

3 Manager, ANO-1, Director, Operations or-the. Safety Review:-

Committee.-

i 1.

Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the:

Dire'ctor, Operations and the Safety Review Committee.

j.

Review of the Emergency Plan and implementing procedures-and submittal of recommended changes to the Director,-

l Operations and the Safety Review Committee.

k.

Review of cheages'to the Offsite' Dose Calculation Manual-i and the Process Control Program.

AUTHORITY 6.5.1.7.

The Plant Safety Committee shall:

a.

Recommend in writing their approval or disapproval.of, items considered.under 6.5.1'.6(a) throught (d)1above.

b.

Render determinations in writing with regard to wh' ether:or not each item considered under 6.5.1.6(a) through (e),

4 above constitutes an unreviewed' safety question.

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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, Operations ANO and the Safety Review Committee of disagreement between.the:PSC'and the Plant Manager,

i kNO-1 or the Director, Operations;ihowever, the Director,-

l Operations shall have; responsibility for resolution of such. disagreements' pursuant;to 6.1.1'.above.

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RECORDS

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6.5.1.8 The Plant Safety Committee shall maintain written minutes of each PSC meeting'that,.at a minimum,-documentLthe:results of' l

l all PSC activities performed under:the'responsibilityiand..

i authority provisions of these technical'. specifications. Copies

- hall'be provided to the Plant Manager, ANO-1, Director,z 1

s Operations and Chairman ~of the Safety Review Committee..

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6.5.2 Safety Review Committee (SRC) l FUNCTION 6.5.2.1 The Safety Review Committee shall' function _to provide-

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independent review and audit'of designated; activities _in~.the areas of:

a.

nuclear. power plant operations b.

nuclear engi_neering; a

c.

chemistry,and radiochemistry' Amendment No. JS, '3A, 37,17, ES; SE, 122 c.i SS, 99, JS9r J24..

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3.

d.

metallurgy.

e.

instrumentation and control ~

f.

radiological safety _

g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION 6.5.2.2 The Safety Review Committee shall be composed of a Chairman and eight to twelve members which collectively have the experience and competence required by ANSI /ANS-3.1-1981 to. review problems.

in the areas:specified in Section 6.5.2.1, a-h.

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The Vice President, Operations ANO shall designate,~in l

writing, the Chairman and all'SRC members.

The Chairman shall designate,.in writing,.the alternate Chairman in the absence of the SRC Chairman.

i ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing-by-the SRC Chairman to servc on a temporary basis; however,'.no more than two alternates shall participate as voting members in:SRC:

activities at-any one time.

. CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman 4

to provide expert advice to-the;SRC.

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MEETING FRE0VENCY I

6.5.2.5 TheSRCshallmeetatleast.oncepercalindar_quarterduring; the. initial year of facility operationTfollowing fuel loading and at least once per six months.thereaf ter. -

--7 OV0 RUM 6.5.2.6

-The minimum quorum of-the SRC necessary for;the performance:of-

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the SRC review and audit functions ofcthese technical-specifications'shall consist of the Chairman!or his deiignated; alternate.and at 1 east:a majority % of-theLSRC memberslincluding alternates.

No more than;a minorityLofJthe q'uorum shall have-line responsibility for operation of<the. unit..

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' Amendment No. 2E, 34, J7, 47,.EE, S24 _123 99,;22), 22A,f 1

d.

-The performance of activities required'by the.0perational' Quality Assurance' Program to meet the criteria of 10CFR50

'i Appendix "B", at least once per 24 months, e.

The Facility Emergency Plan and implementing procedures at least once per 12 months.

f.

The Facility Security _ Plan and implementing procedures'at!

least once per 12 months, g.

Any other area of u' nit operation considered appropriate _ by the SRC or the Vice President,-Operations ANO.

1 h.

.The Facility Fire Proteci. ion Program-and implementing '

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procedures at_least once per 24 months.

1.

An independent fire protection.and!1oss prevention' program i

inspection and audit shall'be-performed at least once per,

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12. months utilizing either qualified off-site licensee ~

personnel or an outside fire protection'f_irm.

a j.

The Offsite Dose Calculation; Manual.and Proces's Control-Program and-implementing procedures 1at.least once per 24.

months.

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k.

The radiological environmental' monitoring program and.the results-thereof at least once per:12 months.,

AUTHORITY q

i 6.5.2.9 The SRC shall report to and advise thelVice: President, Operations ANO on those areas of_ responsibility specified in a

Sections 6.5.2.7 and 6.5.2.8.

i RECORDS

-i 6.5.2.10 Records of SRC activities shall_be' prepared, approved land n

distributed.as indicated below:

a.

Minutes of each SRC meeting _shall be prepared, approved--

and forwarded to the Vice-President, Operations ANO within 14 days following each meeting, i

b.

Reports.of. reviews' encompassed by.Section_6'5.2.7 above, shall be prepared, approved and forwarded to1the Vice" l

President, Operations ANO within 14 days followingl l

completion.of. the'_ review.

c.

Audit reports encompassed byrSection 6.5.2.8Eabove sh'all.

be forwarded to the Vice-President,~ Operations'ANO and to, the management positions responsibic for the areas audited within.30 day' after completion of:the audit.'

s 1:

Amendment No. IS, 20, 3A, 27, AZ, A7,.ES,~ 125

78. SZ, SS, 99,'224,

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6.6 rep 0RTABLE EVENT ACTION 6.6.1 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to'10 CFR Part 50.

r 6.6.2 The following actions shall be taken for REPORTABLE EVENTS:

a.

'A report shall be. submitted to.the Commission-pursuant to

[

the requirements of Section 50.73 to 10 CFP, Part 50, and b.

Each' REPORTABLE EVENT shall be reviewed by.the PSC,.and-the results of this review shall be submitted to the SRC 4

and the Vice President, 0perations ANO..

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be'taken inithe-event a: Safety.

Limit is violated:

a.

-The facility shall-be placed inLat least hot' shutdown:

g within one hour, b.

The.Nuclea'r Regulatory Commission shall be notified.

pursuant to 10 CFR:50.72'and a report submitted pursuant.

to the' requirements of 10~CFR E0.36:and Specification;6.6..

6.8 PROCEDURES 6.8.1 Written procedures shall be. established -implemented and-maintained covering the activitiestreferenced'below:

't a.

The applicable: procedures recommended in Appendix'"A'T of

~.

Regulatory Guide 1 33, November,m 1972.:

a b.

Refueling operations.

~

c.

Surveillanc'e and test activities of safety related-equipment.-

d.

- Security Plan implementation.i

i e.

Emergency Plan implementation.'

f.

Fire: Protection Program implement'ation.

g.

New and spent fuel storage.

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h.

Offsite Dose' Calculation Manual and-Process Control Program-implementation'at the site.-

9 1.

Post accident ' sampling:(includes samplin~g of reactor.-

coolant, radioactiveLiodinesiand particulates in plant +

)

gaseous ef fluents, and' the: containment = atmosphere).

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l Amendment No. JS, 30, 3f, 37, AR, ' A7, 126 u

ES,:82,-79,118,'J24, m

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.I 6.8.2 Each procedure of-6.8.1 above,cand changes in intent-theretb, l

shall be reviewed by.the PSC and approved by the Director, Operations, Plant Manager, ANO-1.or responsible _ General-t Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

~

l 6.8.3 Changes to procedures of 6.8.1 above may be made and-implemented _ prior to obtaining the review and approval required in 6.8.2 above provided:

a.-

The intent of the original' procedure is not; altered.

b.

The change is approved by two members of-the plant management staff, at.least one of whom holdsia Senior Reactor Operator's license on Unit'1.-

The change is documented,~ reviewed tiy:the PSC, and.

c.

approved by the Di' rector, Operations, Plant Manager, ANO-1 or_ responsible-General Manager, within 14 days.of' implementation.

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j Amendment No. JS, 79, 3A, 37, 127; 76, 82, EE,.94,

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PROPOSED TECHNICAL SPECIFICATION CHANGES-ANO-2 1

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 1

6.1.1 -The Vice President, Operations AN0'shall' be responsible for overall

)

facility operations'and shall-delegate in writing'the: succession to this i

responsibility during his absence.

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall' be established.for ' unit operation-and corporate management, respectively. 'The onsite and'offsite organizations shall include the= positions for activit'es_affecting the safety of the nuclear power plant, a.

Lines of authority, responsibility, and communication shall bei l

established and defined for; the, highest management levelst through-1 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'.u These requirements shall be' documented in the QA Manual, Operations.:

b.

.The Director, Operations shall be responsible;for overall, unit

~,

safe operation'and shall have' control over those onsiteL activities necessary-for sr.fe" operation and maintenance of..the.

plant.

c.

The Vice President, Operations'AN0!shall.have corporate-responsibility for.overall, plant nuclear safety and:shall.take any measures needed totensure acceptable performance of the 4

staff in operating, maintaining, and providing~ technical: support--

to the plant to' ensure nuclear' safety.

1; d.

The individuals who train the operating staff ~and those who; carry out health physics -and ' quality ' assurance func:tions may report to the appropriate onsite manager; however, they shall;haveJ sufficient' organizational freedom to ensure theiniindependencei

.j from operating pressures.

6.2.2 FACILITY STAFF-a.

Each on-duty shift shall be composed ~of at least the minimum J

shift crew compositionLshown in Table 6.2-1.

a a

b.

At least one licensed Operator shall be in thetcontrol room.when fuel is in'the reactor.

L I-

-ARKANSAS-UNIT 2-6-1 Amendment:No. E, EE,IE7, 7), SE, $7, S$;

1:

c.

At least two licensed.0perators 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, d

e.

All CORE ALTERATIONS shall be directly supervised by either ai 1

licensed Senior Reactor Operator or Senior Reactor. Operator 4

Limited to Fuel Handling who has no other: concurrent J

responsibilities during this operation..

'1 f.

A site Fire Brigade of at.leastL 5 members shall be maintained-1 onsite at all times..The Fire Brigade shall not include 3 U

. members of the minimum shift. crew'necessary for safe shutdown ofE the. unit and any personnel required for other essential: functions during a fire emergency.

g.

Administrative control shall be established to limit!the amount ~

1 of overtime worked by plant. staff performing. safety-related' functions.

These administrative' controls.shall'be.in accordance with the guidance provided by the'NRC Policy Statement on_ working.

hours. (Generic Letter No.s 82-12).-

I h.

The Manager,<0perations and Shift Supervisor'sha11 hold a senior-reactor operator license.

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'I ARKANSAS-UNIT 2 6 AmendmentiNo. 27,'25F 29,0 52, _.

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ADMINISTRATIVE CONTROLS' I

6.3 UNIT STAFF OVALIFICATIONS 6.3.1 Each member of the ' unit staff shall meet or exceed the minimum.

qualifications of ANSI N18.1-1971.for comparable positions,; except for- (1)'

~

7 l

the designated radiation protectio ~n manager, who shall meet or exceed the-l qualifications of Regulatory Guide,1.8, September 1975, and (2)-the Shift-Technical ~ Advisor who shall have a bachelors degree ~or equivalent in a l

scientific or engineering discipline with specific training in plant design, and response and analysis of. the. plant for transients:and-accidents.

-I 6.4 TRAINING-

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6.4.1 A retraining and replacement training program-for the unit ~ staff shall be maintained under the direction ofothe-Manager, Training:and Emergency Planning and shall meet or exceed the requirements and i

recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of.10-CFR Part 55.

6.4.2 A training program for the Fire Brigade shalllbe maintained under-the direction of the Manager, Training and Emergency Planning and shall i

meet or exceed the requirements of Section 27'of-the NFPA Code _--1975, except for Fire Brigade training sessions which shall be held at-least l

quarterly.

l 6.5 REVIEW AND AUDIT ti 6.5.1 PLANT SAFETY COMMITTEE (pSC)

FUNCTION ai 6.5.1.1 The Plant Safety Committee shall function;to advise the j

Director, Operations and Plant Manager, AN022.on all matters related to nuclear safety.

j COMPOSITION 6.5.1.2 The Plant Safety Committee shall be~ composed of at least eight t

members of ANO onsite management organization (except as discussed under 6.5.1.3) at the superintendent level or above. :The PSC Chairman'shal.1-ensure that adequate expertise is presentLduring meetings to evaluate; material ~before the PSC.

In addition, the Director, Operatio'ns shall designate in writing a P'SC.

Chairman and at least one Alternate Chairman.

6.5.1.3 If Core Protection Calculator (CPC) Software'is being reviewed a'

]

nuclear software expert shall' be present:as! a voting member.

If one of q

the members of the Plant Safety' Committee meets the qualification.

l requirements for this position, the requirementito.have this member is,

satisfied. This membership may be' filled:by two appropriately' qualified individuals who-shall ballot with a_singleL: combined vote. Generic qualifications for~this membership shall be'as follows:

1 ARKANSAS-UNIT 2 6-5 Amendment No. E, 12, 17',.

29, 29, 52,i7 R SE, 98, 1

y 4

ADMINISTRATIVE CONTROLS ~

One Individual.

- i The Nuclear Software Ex' pert shall have_as'a minimum a Bachelor's degree lin Science or Engineering, Nuclear preferred (in accordance with' ANSI N18.1).

In addition, he shall have a minimum of four years'of technical experience, i

of which a minimum of two years shall be in Nuclear Engineering and ai minimum shall be in Software Engineering.'

(Software Engineering is that branch of science;and technology'which deals with'the-design and use-of software. Software: Engineering is a discipline' directed to the~ production and modification of computer programs that.are; correct,' efficient, flexible, maintainable, and understandable,:in reasonable time _ spans, and' at reasonable costs.) The two years of technical experience.in Software Engineering may.be. general software _ experience not necessarily related to the software of the Core Protection Calculator' System. L0ne of?these two:

years of experience shall be with cert _ified. computer programs..

Two Individuals.

One-of the individuals shall meet'the requirements of the Nuclear Engineering portion of the above.

The second, individual shall have'a Bachelor of Science degree (digital' computer speciality);and meet the-Software. Engineering requirements of the above.:

The membership (the Nuclear Software Exaert:or the Digital Computers Specialist) shall be knowledgeable of tie Core Protection Calculator System with regard to:

r a,

'The software modules, their interactions with each other and with.

J the data base.

.1 b.

The relationship between operator's moduleLinputs and the trip variables.

The relationship between sensor input signals and the.; trip c.

variable..

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d.

The design basis of the'CorecProtection. Calculator?Syst'em' e.

The approved software change procedure-and documentation 1 requirements of a software change.

J f.

The security of.the computer memory and access, procedures to' the !

l memory.-

1 1

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- i ARKANSAS-UNIT 2 6-Sa IAmendmentNoOJ2

b I

ADMINISTRATIVE CONTROLS ~

't ALTERNATES j

6.5.1.4 Alternate members shall be appointed in'_ writing by'the PSC Chairman to serve on a temporary basis;;however, no more than-two

-alternates shall participate as voting members in'PSC activities at any one-time.

MEETING FRE0VENCY-6.5.1.5

, The PSC shall meet at'.least-once per calendar monti and as convened by the PSC Chairman or his' designated alternate.

OV0RVM i

6.5.1.6 The minimum. quorum of the'PSC~necessary for the performance ~of-the PSC. responsibility and authority provisions of these technical-l specifications-shall consist of the. Chairman or his designated ~aiternate :

i and>four members including alternates.

(

RESPONSIBILITIES q

6.5.1.7

-The Plant Safety Committee shall.be responsible for:1 q

l a.

Review of.1) all procedures required by Specification 6.8 and changes in: intent thereto,;2) anyjother proposed 1

procedures or changes thereto as= determined by the

' Director, Operations or: Plant Manager; ANO-2.to 'af fect -

-nuclear safety..

l b.

Review of all proposed tests and experiment's'that: affect i

~

nuclear safety.

c.

Review of all proposed changes to: Appendix "A", Technical l

Specifications.

L d.

Review of all proposed changesfor modifications to.unitt L

systems or equipment that affect nuclear safety.

i e.

Investigation of all' violations of the Technical q

Specifications,-including the, preparation and: forwarding ofL

'i reports covering: evaluation and : recommendation to prevent.

recurrence to the Plant Manager, ANO-2, Director,: ~

p Operations and to the' Chairman:ofLthe.SafetyLReview Committee.

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, o ARKANSAS-UNIT 2

'6-6 Amendment.No.6,j7,EZ,73,.5,7M, Y

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ADMINISTRATIVE CONTROLS f.

Review of all REPORTABLE EVENTS..

g.

Review of facility operations to detect' potential nuclear safety.

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hazards.

h.

Performance of special reviews', investigations or analyses, and reports thereon as requested by the Plant Manager, ANO-2, '

Director, Operations or the Safety Review Committee.

1.

Review of the Plant-Security Plan and-implementing procedures 1and submittal of recommended changes.to the Director,r0perations and the Safety Review Committee.

J.

Review of the Emergency Plan and implementing procedures.and.

submittal of recommended changes to the Director, Operations'.'and-Safety Review Committee.

k.

Review 1of changes to ths Offsite Dose Calculation' Manual.and Process Control Program.

AUTHORITY 6.5.1.8 The Plant Safety Committee shall:

a.

Recommend in writing their' approval or' disapproval of. items considered under 6.5.1.6(a)'.through (d) above.:

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b.

Render determinations in writing with regard to whether-'or'not each item considered -under 6.5.1'.6(a):through -(e) above-

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constitutes an unreviewed safety = question.;

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to-the Vice?

President, Operations ANO,and the Safety Review! Committee of disagreement between the PSC and'the Plant Manager', ANO-2~or the Director, Operations; however,.the Director, 0perations shall have responsibility for resolution of such disagreementsi I

pursuant to 6.1.1: above.

RECORDS:

l

- 6'.5.1.9: 'The Plant Safety Committee'sha11Lmaintain written 1 minutes o'f each

~

PSC meeting'that, at a minimum,Ldocument?the results;of/alliPSC activities performed under the responsibility and. authority provisions of Lthese technical specifications. Copies.shall;be provided toitheLPlant Manager, ANO-2,' Director, Operations and. Chairman of-the Safety Review. Committee..

q daj ARKANSAS-UNIT 2 6-7.

-Amendment No.;E, 17, 25,~E2, 69, 73,~SE, 92,-

, 78,

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i ADMINISTRATIVE CONTROLS i

l 6.5.2 SAFETY REVIEW COMMITTEE (SRC) j l

FUNCTION

,j 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:-

l a.

nuclear power plant operations b.

nuclear engineering f

c.

-chemistry and radiochemistry-d.

metallurgy e.

instrumentation and control f

f.

radiological safety g,

mechanical and electrica1' engineering-h.

quality assurance practices COMPOSITION

~I 6.5.2.2 The Safety Review Committee shall be'composedto'f 'a Chairman; and -.

eight to twelve members which collectively have the experience; J

and competence required by ANSI /ANS-3.1-1981 to' review problems-l in the areas specified in.Section'6.5.2.1,;a-h.--

The Vice President, Operatio~ns ANO.shall: designate,Ein writing,1

-i the Chairman and all'SRC members.

The Chairman shall: designate, fin. writing, the alternate-Chairman

.j in the absence of the SRC Chairmant-

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ARKANSAS-UNIT 2 6-8 AmendmentNo.'5,J7,25,52,.71,97,

78, ;

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I ADMINISTRATI'sE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance-of the SRC. These audits shall encompass:

a.

The conformance of unit operation to provisions contained sithin' the Technical Specifications and applicable license conditions at-least once per 12 months, b.

The performance, training, and qualifications of,the' entire unit-staff at least once per 12 months.-

1 c.

The results of actions taken to correct-deficiencies occurringLin unit equipment, structure, systems,-or method-of operation that-affect nuclear safety-'at least once per.6 months.

s d.

The performance of activities required'by thel 0perational: Qualityt.

Assurance. Program to meet.the criteria of 10 CFR-50,LAppendixs "B", at least once per 24 months.

e.

The Facility Emergency Plan andEimplementin'g procedures at,least once per 12 months.

i f.

The Facility Security Plan'and. implementing procedures at.least~

once per 12 months.

g.

Any other area of. unit operation considered appropriate by the SRC or the Vice President, 0perations ANO.s j

h.

The Facility Fire. Protection Program and: implementing' procedures.

at least once per 24 months.

i.

An independent fire protection'.and' loss prevention; program.

inspection and audit shall:be performed atLleast once:per 121 1

months. utilizing.either qualified LoffsiteLlicensee personnel or?

an outside' fire protection firm'.

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The Offsite Dose Calculation-Manual-'and' Process:Contro11 Program and implementing. procedures _att least once; per' 24. months.

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An inspection and audit of the fire-protection and loss.

prevention program shall-be. performed by a qualified'outside.-f. ire ~

consultant at least once.perL36' months'.=

AUTHORITY-

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6.5.2.9 The SRC shall report-to:and advise the Vicel President, Operations AN0Lon those areas of responsibil'ity specified in'. Sections 6.5.2.7 and 6'.5.248.

l ARKANSAS-UNIT 2. 11 AmendmentNo.ill,25,$2,;E2,c59,17$, cps;3, l

r ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records'of SRC activities.shall be' prepared, approved and distributed as indicated below:

Minutes of.each SRC. meeting shall be prepared,' approve'd and a.

forwarded to the Vice President, Operations ANO within 14 days-l following:each meeting, b.

Reports of reviews encompassed by Section 6.5.2.7 ab^ove, shall be prepared, approved and forwarded to the Vice President,.

1 Operations'ANO within 14 days following completionfof'the r

review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be 5

forwarded to the Vice President,.0perations AN0 and to the management positions responsible for the: areas-audited.within;30.

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days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a..

A report.shall be submitted to'the Commi'ssion pursuant to the requirements-of Section 50.73 to'10CFR~Part 50, Land '

b.

Each REPORTABLE EVENT-shall be reviewed by'the PSC'and,othe i

results of this review;shall be submitted to the SRC and.the'Vice 1

President, Operations ANO.

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. ARKANSAS-UNIT 2 6-12 Amendment No.:.JJ,125,5NJ,52(59,73,95,.

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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1.The following actions shall be taken in the event a Safety Limit is 1

violated:

a.

The unit shall be placed in at least HOT STANOBY within one hour.,

b.

The.Vice President,-Operations ANO and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

The Nuclear Regulatory Commission shall be notified pursuant to

.i 10CFR50.72 anu a report submitted' pursuant to the-requirements of 10CFR50.36 and Specification'6.6.

j 6.8 PROCEDURES 6.8.1 Written. procedures shall be' established, implemented and maintained covering the activities referenced below:

a.

The applicable procedures recommended 1n. Appendix "A" of Regulatory Guide 1.33, Revision'2, February 1978.'

b.-

Refueling operations.

c.

Surveillance and test activities-of safety related equipment.

4 d.

Security Plan implementation.

-e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection.C. culator.(CPC) Addressable ~

Constants. These procedures shouidcinclude provisions to' assure.

1 that sufficient margin is maintained in'CPC Type I addressable:

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constants to avoid excessive. operator interaction with the CPCs A

during reactor operation.

NOTE:

Modifications to the CPC. software (including changes of algorithms:and fuel cycle specific data).shall..be.

performed in accordance:with the most recent version'of."CPC

)

Protection Algorithm Software Change Procedure,"-CEN-39(A)-P that has been determined to'be applicable to'the. facility./

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Additions or deletions to'CPC addressable constants or-

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changes to addressable constant software limittvalues shall not be implemented.without prior NRC approval.-

L h.

New and spent fuel storage.-,

i.

ODCM and.pCP implementation.

4, J.-

Postaccident sampling (includes sampling <of. reactor coolant, h

radioactive iodines and particulates in plant gaseous effluent,

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L and the containment atmosphere).

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-6.8.2 -Each procedure of 6.8.1 above, the changes in intent thereto, shall.

be reviewed by the PSC and approved by the Director,.0perations,. Plant

- Manager, ANO-2 or responsible General Manager ' prior to, implementation and -

reviewed periodically as set forth in-administrative procedures.

ARKANSAS-UNIT 2 6-13 Amendment No.'24, 2S, A3, E2,.59,'

/EE, 73, 77, SE, N,

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ADMINISTRATIVE CONTROLS 1

6.8.3 Changes to_ procedures of 6.8.1; above may be made and implemented :

j prior to obtaining the review and approval required-in 6.8.'2'above L

provided:

a.

The intent of the original procedure is not altered..

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b.

The change is approved by_two_ members of the plant management staff, at least one of whom holds'a Senior' Reactor Operator's License on Unit 2.

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c.

The change is documented, reviewed by.the PSC and approved by the Director, Operations, Plant' Manager,LANO-2 or responsible General Manager within 14 days.of. implementation..

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall _be submitted to the Administrator of the Regional Office'unless otherwise noted.

STARTUP REPORT i

6.9.1.1 A summary report of plant startup and power escalation testing _

shall be submitted following (1) receipt of. an operating =. license,;(2);'.

amendment to the' license involving.a planned; increase in pover-level..(3) installation of fuel that has a different: design!or has been; manufactured.

by a different fuel supplier,' and-(4) modifications that may have<

l significantly altered the nuclear,_ thermal,Jor' hydraulic performance of.

1 the plant.

6.9.1.2 The startup report shall address each'of'the:testsEidentified in-the FSAR and shall include a description of the measured values of theJ operating conditions or characteristics obtained:during.thentestiprogram-and a comparison of these values with' design:predictionsTand specifications. Any corrective _ actions that-were required to.obtain.

satisfactory operation shall also be described.7. Any additional specific j

details required in~1icense conditions based on other commitments shallibe included.in this report.

I 6.9.1.3 Startup reports shall'be submitted within (1):90 days following:

completion of the startup test. program, (2) 90" days following resumption.or-commencement of commercial power operation, or'(3);9 months following

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initial criticality,'whichever is earliest. /If;the Startup _ Report doesL not cover all three events-(i.e., initial criticality,1 completion of startup' L

test program, and resumption.or commencement of commercial Lpower _

operation), supplementary repor_ts: shall.be ' submitted:at -least 'every 'three j

months until'all.three. events have been completed.

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-ARKANSAS-UNIT 2 6-14.-

Amendment.No. E,_E2,;77, SE,yST,,SS,

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