Text

Amends 47 & 17 to Licenses DPR-51 & NPF-6 Respectively, Modifying Tech Specs Apps a & B Dealing W/Util Mgt Organizational Structure
	ML19345B110
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/14/1980
From:	Clark R, Reid R; Office of Nuclear Reactor Regulation
To:	; Arkansas Power & Light Co
Shared Package
ML19345B111	List: ML19345B110; ML19345B112; ML19345B114;
References
	DPR-51-A-047, NPF-06-A-017 NUDOCS 8011260174
	Download: ML19345B110 (34)
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UNITED STATES

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NUCLEAR REGULATORY COMMisslON y*

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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKAtlSAS NUCLEAR ONE - UNIT NO. 1 AME'4DME'1T TO FACILITY OPERATING LICENSE Arendment No. 47 License No. DPR-51 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for arendment by Arkansas Power & Light Carcany (the licensee) dated September 29, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as arended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; S.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by tnis amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part

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51 of the Comission's regulations and all applicable requirements have been satisfied.

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i ATTACHMENT TO LICENSE AMENDMENT NO.

47 FACILITY OPERATING LICENSE NO. OPR-51 00CKET NO. 50-313 2

Replace the following pages of the Aopendices "A" and "B" Technical Specifi-cations with the enclosed pages. The revised pages are identified by amend-ment nunter and contain vertical '

.e3 indicating the area of change.

Appendix "A" Page.,

Insert Rer.ove iv iv 117 117 119 Figure 6.2-1 119 120 Figure 6.2-2A 12G Figure 6.2-2 121 120a Figure 6.2-2B 122 121 Figure 6.2-2C 123 121a Figure 6.2 124 122 125 123 125 124 141 125 144 126 4

141 144 Accendix "B" Pages 5-9 5 i i

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INTPODUCTTON These Technical Specificatices apply to Arkansas Nuclear One, thit 1 and are in accordance with the requirements of 10 0FR 50, Section 50.36.

Se bases, which provide technical sunnert or reference the certinent FSAR secticn for technical supcort of the individual specifications, are included for infor=atimal purposes and to clariP/ the intent of the seccificaticn.

dese bases an not part of the Technical Specifications, and thev do not constitute limitations or requirements for the licensee.

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LIST OF FIGL*RES l

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2.1-1 CORE PROTECTION SAFETY LIMIT 9a 2.1-2 CORE PROTECT!0N SAFETY LIMITS 9b 2.1-3 CORE PROTECTION SAFE *Y LDtI!S 9c 2.3-1 PROTECTICN SYSTEM MAXIMUM ALLOWA3LE SET POINTS 14a 2.3-2 PROTECTION SYSTEM MAXIML3 ALLO'4A3LE SET POINTS 14b 3.1.2-1 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS 20a 3.1.2-2

-REACTOR COOLANT SYS*EM C00LDOWN LIMIT 20b 3.1.9-1 LIMITING PRESSURE *.'S.

TEMPERATURE FOR CONTROL ROD 33 DRIVE OPERATION '4ITH 100 STD CC/ LITER H,0 s

f 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AX;AL 53a D!3ALANCE I:."JICA!!0N i

3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL 53b FLUX TIL' INDICAIION 3.5.a-3 INCORE INSTRUME:T:'ATION SPECIFICA!!ON 53c o.0-1 MANAGEMENT ORGANIZATION CHART 119 i

6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATICN 120 l

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iv Amenc:nent No. 47

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m 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPCNSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and tech-nical support shall be as shown on Figure 6.2.-l.

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

Each on duty shift shall Se composed of at least the minimum shift crew composition shown in Table 6.2.-l.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N13.1-1971 for comparable position, except for the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained and shall meet or exceed the require-ments and 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 fire protection training shall be maintained and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 with the exception of frequency of training which shall be six times per year.

6.5 REVIE'd AND AUDIT 6.5.1 Plant Safety Committee (PSC) Function 6.5.1.1 The Plant Safety Co=sittee shall function to advise the General Manager on all matters related to nuclear fety.

COMPOSITION

6. 5.1. 2 The Plant Safety Committee shall be composed of the:

(See Page 121) l g

-117-Amerp ent No. 14 30, 3 t.. 37.

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ha cd Figure 6.2-2 Functional Organization for Plant Operation 2P W

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Chair =an: Manager of Special Projects Member:

Operations Manager Meaber:

Maintenance Manager.

Member:

Engineering and Technical Suppor: Manager Member:

Administrative Manager Member:

Technical Analysis Superintendent Member:

Plant Analysis Superintendent Member:

?lant Engineering Superintenden:

Member:

Health Physics Supervisor The General Manager shall designate in wri:ing the Alternate Chairman in the absence of the Chair =an.

ALTERNATES 6.5.1.3 All alternate se=bers shall be appointed in vri:ing by the PSC Chairman to serve on a te=porary basis; however, no more than two alternates shall participate as voting =esoers in PSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The PSC shall meet at least once per calendar sonth and as convened by,the PSC Chair =an or his designated alternate.

OUORUM 6.5.1.5 The mini =um quorus of the PSC necessarf for the perfor=ance of the PSC responsiblity and authority provisions of these technical specifications shall consist of the Chair =an or his designa:ed alternate and four me=bers including al:ernates.

RESPONSIBILITIES 6.5.1.6 The Plant Saf ety Co=mittee shall be responsible for:

a.

Review of 1) all procedures required by Specifica: ion 6.8 and revisions thereto, 2) any other proposed pro-cedures or revisions thereto as de:er=ined by the General Manager to affect nuclear safe:y.

b.

Review of all proposed tests and experinents that affeer nuclear safety, Review of all proposed changes to the Appendix "A" c.

Technical Specifications.

d.

Review of all proposed changes or modifications to plant I

syste=s or equipmen: that affect nuclear safety, Investigation of all violations of the Technical Specifica-e.

tions, including the preparation and forwarding of reports covering evalua: ion and reco==endations :o prevent recurrence to the General Manager.

f.

Review of those Reportable Occurrences requiring 24-hour no tification of :he Co==ission.

A=end:ent No.

16, 34, 37, 121 27

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Review of facility operations to detect potential nuclear saf ety hazards, h.

Perf or=ance of special reviews, investigations and reports thereon as requested by the General Manager.

1.

Review of the Plant Security Plan and i=ple=enting procedures and shall submit reco== ended changes to the General Manager.

j. Review of the E=ergency Plan and i=ple=enting pro-cedures and shall sub=it recacaended changes to the General Manager.

AUTHORITY 6.5.1.7.1. The Plant Safety Co==ittee shall:

I a.

Reco==end to the General Manager written approval or disapproval of ite=s considered under 6.5.1.6(a) through (d) above.

b.

Render deter =inations in writing with regard to whether or not each ice 2 considered under 6.5.1.6(a) through (e) l above constitutes an unreviewed safety question.

c.

Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Operations and the Safety Review Co=sittee of disagree =ent between the PSC and the General Manager; however, the General Manager shall have responsi-bility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.3.1.8 The Plant Safety Co==ittee shall =aintain written =inutes of each PSC meeting that, at a =ini=u=, document the results of all PSC activities perfor=ed under the responsibility and authority provisions of these technical specifications. Copies shall be provided to the General Manager and Chair =an of the Safety Review Co==1ttee.

6.5.2 Safety Review Coccittee (SRC)

FUNCT10;i 6.5.2.1 The Saf ety Review Co==1ttee shall function to provide in-dependent review and audit of designated activities in the areas of:

a.

nuclear power plant operations b.

nuclear engineering c.

che=istry and radioche=istry A=end=ent No. I6, 34, 37, 17 12?

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d.

metallurgy e.- instrumentation and control.

f.

radiological safety g.

mechanical and electrical engineering h.

quality assurance practices COMPOSITION e

6.5.2.2.

The SRC shall be composed of the:

Chairman: Director. Technical and Environtental Services Member:

Director, Nuclear Operations Member:

Director, Generation Technology Member:

Manager, Quality Assurance Member:

Arkansas Nuclaar One Plant Safety Com=ittee Chairman Member:

Manager, Technical Analysis Me=b er :

Arkansas Nuclear One Plant Analysis Superintendent.

Member:

Director, Generation Engineering Member:

Manager, Electrical Engineering Member:

Manager of System Nuclear Operations The Chairman shall designate in writing the alternate chairman in the aosence of the SRC Chairman.

AITERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two i

alternaces shall participate as voting members in SRC activities at any one else.

CONSULTANTS e.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.

MEETIFG FREQUENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter, j

QUCRUM 6.5.2.6 The minimum quorum of the SRC necessary for the perfor=ance of the SRC review'and audit functions of these technical specifications shall consist of the Chair =an or his designated alternate and at least a SRC members including alternates. No = ore than a =inority of the quorum shall have line responsibility for operation of the un't.

Middle South' Services

. Amendment-No. 16, 34, 37, 123 47

REVIEW 6.5.2.7 The SRC shall review:

a.

The safety evaluations for 1) changes to procedures, equipment or systems, and 2) tests or experiments ccmplaced under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems i

which involve an unreviewed safety questien as defined in Section 50.59, 10 CFR.

l Proposed tests or experiments which involve an unreviewed c.

safety question as defined in Section 50.59, 10 CFR.

d.

Proposed changes in Technical Specifications or licenses, e.

Violations of applicable statutes, codes, regulations, orders, Technical Specificaticas, license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that

' affect nuclear safety.

g.

Events requiring 24-hour notification to the Commission.

l h.

All recognized indications of an unanticipated deficiency in some aspects of design or operation of structures, systems, or components that could affect nuclear safety.

1.

Reports and meeting minutes of the Plant Safety Committee.

AUDITS 6.5.2.8 A2dits of facility activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a.

The conformance of facility operation to provisions contained within the Technical specifications and applicable license conditions at least once per year.

b.

The performance and retraining of all members of the plant

=anagement and operations staff, and the performance, training, and qualifications of new members of the entire plant staff at least once per year.

The results of all actions taken to ' correct deficiencies c.

occurring in facility equipment, structures, systems or nethod of operation that affect nuclear safety at least once per six months.

Amendment No. 16, 30, 34, 104 47 L.

d.

The Facility Emergency Plan and i=plementing proceduras at least once per two years.

e.

The Facility Fire Protection Program and implementing procedures at least once per two years.

f.

The Facility Security Plan and implementing procedures at least once per two years.

g.

Any other area of facility operation considered appropriate by the SRC or the Vice President, Generation & Construction (VP, G&C).

h.

An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Generation

& Construction (VP,G&C) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.3.

RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:

a.

M.inutes of each SRC meeting shall be prepared, approved and forwarded to the Vice President, Generation & Construc-tion (VP, G&C) within 14 days following each =eeting.

l b.

Reports of reviews encompassed by Section 6.5.2.7 above shall be prepared, approved and forwarded to the Vice President, Generation & Construction, (VP,G&C) within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.3 above shall be forwarded to the Vice President, Generation &

Construction (VP, G&C) and to the =ar.agement positions responsible for the areas audited within 30 days af ter completion of the audit.

A=endment No. I6, 30, 34, 37, 42, 125 47 h

1 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 6.12.

b.

Each Reportable Occurrence requiring 24-hour notification to the Commission shall be reviewed by the PSC and submitted to the SRC and the Director, Nuclear Operations by the General Manager.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a

. Safety Limit is violated:

Anendnent No. 16,30, 34, 37, 42, 126 47

'b

The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge ~ measurements.

Small exposures totalling less than 20% of the individual total dose need not be ac-counted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

6.12.2.3 Monthly Operating Report Routine reports of operating statistics which include:

1.

Average Daily Unit Power Level 2.

Operating Data Report 3.

Unit Shutdowns and Power Reductions 4.

Narrative Summary of Operating Experience shall be submitted on a monthly basis to the Director, Office of Management and Progrta Analysis. U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, by the fifteenth of each month following the calendar month covered by the report.

6.12.3 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent recurrence, shall be -- r-ted to the NRC as required below.

Supplemental reports may be r to fully describe final resolution of occurrence. In case of ec

.eu or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

6.12.3.1 Prompt Notification With Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24-hours, by telephone and confirmed by telegraph, mailgram, or facsimile transmission to tLe Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks. A copy of the confir=ation and the written followup report shall also be sent to the Director, Office of Management acd Program Analysis, USNRC.

The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplenented. as needed, by additional narrative material to provide complete explanation of the circumstances sur-rounding the event.

Amendment No. 3. 23, 29

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9 (h)

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the Tech 2ical Specifications that have or could have permitted reactor operation in a manner less con-servative than assured in the analyses.

(1)

Performance of structures, syttems, or components that requires remedial action or corrective seasutas to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or Technical Specifications bases; or discovery during plant life of conditicas not specifically con-sidered in the safety analysis report or Technical Specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

NOTE: This ites is intended to provide for reporting of po-tentially generic problems.

6.12.3.2 Thirty Day Written Reports The reportable occurrences discussed below shall be the subject of written reports to the Director of the appropriate Regional Office within thirty days of occurrence of the event. A copy of the written report shall also be sent to the Director, Office of Management and Program Analysis.

The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

(a)

Reactor protection system or engineered safety leature instrument settings which are found to be less conservative than those es-cablished by the Technical Specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

(b)

Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

NOTE:

Routine surveillance testing, instrument calibration, or pre-ventative maintenance which require system ccnfigurations as described in items (a) and (b) above need noc be recorted exceot where test results themselves reveal a degraded mode as described above.

(c)

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

Amendment No. 9. 47

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Arendment No.17 License No. NPF-6 1.

The Nuclear Regulatory Comission (the Comission) has found that:

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A.

The application for amendment by Arkansas Power & Light Company l

(the licensee) dated September 29, 1980, complies with the g

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the C: mission's rules and regulations set a

forth in 10 CFR Chapter I; l

S.

The facility will operate in confomity with the application, l

ne provisions of the Act, and the rules and regulations of i

3 the Comission; 1

C.

There is reasonable assurance (1) that the activities authori:ed by this amend..ent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of tnis amendment will not be inimical to the comen defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Comission's regulations and all applicable mquirements have been satisfied.

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Accordingly, the license is anended by changes to the Technical Specifications as indicatec in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:

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(2) Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised througn Amendment No.17, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the i

Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/e.a k Robert A. Clark, Chief I

Operating Reactors Branch #3 Division of Licensing I

j Attacnment:

Changes to the Technical Specifications Date of Issuance: November 14, 1930 i

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ATTACHMENT TO LICENSE AMENDMENT NO.17 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-268 Replace the following pages of the Appendices "A" and "B" Technical Srecifi-cations with the enclosed pages. The revise' pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

Appendix "A" Accendix "B" Pages Paces 6-2 5-10 6-3 6-5 6-6 6-7 6-8 6-12 6-13

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsi-bility during his absence.

6.2 ORGANIZAT!ON OFFSITE 6.2.1 The offsite organi:ation for facility management and tecnnical support snall be as shown on Figure 6.2-1.

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

a.

Eacn on duty snift snall be composed of at least the minimum shif t crew composition snown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room wnen fuel is in tne reactor, c.

At least two licensed Operators shall be present in the control room during reactor start-up, seneduled reactor snutdown and during recovery frem reactor trips.

d.

An individual qualified in radiation protection procedures shall be on site wnen 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 wno has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include 3 members of the minimum snift crew necessary for safe shutdown of the unit and any personnel required for other essential functiors curing a fire emargency.

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LS0-SENIOR OPERATOR LICENSE REQUIRED D

LO-OPERATOR LICENSE RLQUIRED f

0NSITE RESPONSIBILITY FOR FIRE PROTECTION PROGRAM g

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N Figure 6.2-2 Functional Organization for Plant Operation e-&

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TABLE 6.2-1 i

MINIMUM SHIFT CRE'd CCMPOSITIONW 4

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f lNon-Licensed I

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'Does not include One licensed Senior Reactor Ooerator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERAT!CNS.

iShift crew composition may be less than the mininum requirements for a ceriod of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to acccerodate

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unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew C0mpositicn to within the minimum requirements of Table 6.2-1.

I ARKANSAS - L' NIT 2 -

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AOMINISTRATIVE CONTROLS 6.3 UNIT STAFF JUALIFICATIONS 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 the Health Physics Supervisor uno shall meet or exceed tne qualifications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1.

A retraining and replacement training program for the unit staff shall De maintained under the direction of the Seneral Manager and shall meet or exceed the requirements and recommend &tions 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 3rigade shall be maintained under the direction of the General Manager and shall meet or exceed the require-ments of Section 27 of the NFPA Code - 1975, except for Fire Brigade train-ing sessions which shall be held at least quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)

FUNCTION l 6.5.1.1 The Plant Safety Ccmmittee shall function to advise the Plant

{ Manager on all matters related to nuclear safety.

' COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of the:

Chai rman: Manager of Special Projects Member:

Operations Manager Member:

Maintenance Manager Member:

Engineering and Tecnnical Support Manager Member:

Administrative Manager Member:

Tecnnical Analysis Superintendent Member:

Plant Analysis Superintendent Memeer:

Plant Engineering Superintencent Member:

Health Physics Supervisor Member:

Nuclear Sof tware Expert

The General Manager shall designate in writing tne Alternate Chairman in the absence of the PSC Chairman.

See page 6-5a i ARKAN5AS - UNIT 2 6-6 Amendment No. 3 JZ, 17

t I

i ACHINISTRATIVE CONTROLS i

'If one of the aoove members of the Plant Safety Comittee meets the qualification requirements for this position, the requirement to have this member is satisfied. This membership may be filled by two appro-oriately qualified individuals who shall ballot with a single combined vote.

Generic qualifications for this membersnip snail be as follon:

One Individual The Nuclear Software Excert shall have as a minimum a Bachelor's degree in Science or Engineering, Nuclear preferred (in accordance with ANSI N18.1).

In addition, he shall have a minimum of four years of technical excerience, of which a minimum of two years shall be in Nuclear Engineer-ing and a minimu:n of two years shall be in Software Enginee:ing. (Soft-ware Engineering is that branch of science and technology which deals witn the design and use of software.

Software Engineering is a discipline directed to the production and modification of comcuter programs that l

are :orrect, efficient, flexible, maintainable, and understandable, in reasonable time spans, and at reasonable costs). The two years of technical excerience in Software Engineering may be general sof tware experience not necessarily related to the software of the Core Protection Calculator System. One of these two years of experience snall be with certified 4

comouter programs.

Two Individuals Cne of the individuals shall meet the requirements of the Nuclear Engineering portion of the above. The second individual shall have a 3acnelor of Science degree (digital comcuter speciality) and meet the Software Engineering requirements of the above.

The memcership (the Nuclear Software Excert or the Digital Comcuter Soecialist) shall be knowledgeable of the Core Protection Calculator i

System with regard to:

a.

The software modules, their interactions with each other and with tne data base.

b.

The relationship between operator's module inputs and the trip variables.

c.

The relationship between sensor input signals and the trip variable.

d.

The design basis of the Core Protection Calculator System, e.

The accroved software change procedure and documentation reouire-ments of a software change.

f.

The security of the computer memory and access procedures to the memory.

ARKANSAS

'JNIT 1 6-Sa knenament No.12 l

I

ADMINISTRATIVE CONTROLS ALTERNATES 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 two alternates shall participate as voting members in PSC activities at any one time.

MEETING FREQUENCY 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.

000 RUM 6.5.1.5 The minimum quorum of the PCS necessary for the performance of the PSC responsibility and authority provisions of these technical specifications shall consist of the Chairman or his designated alternate and four members including alternates.

l RESPONSIBILITIES 6.5.1.6 The Plant Safety Committee shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the General Manager to affect nuclear safety.

b.

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

c.

Review of all proposed cnanges to Appendix "A" Technical Specifications.

d.

Review of all proposed changes or modifications to unit systems or equipment that affect nucicar safety.

e.

Investigation of all violations of the Tecnnical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager and to tne Chairaan of the Safety Review Committee.

ARKANSAS - UNIT 2 6-6 Amendment No. 5, 17

.1 ADMINISTRATIVE CONTROLS f.

Review of events requiring 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months written notification to the Comission, 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 General Manager or the Safety Review C]mittee.

1.

Review of the. Plant Security Plan and implementing procedures and shall submit recomended changes to the General Manager l

and the Safety Review Comittee.

J.

Review of the Emer:ency Plan and implementing procedures and shall submit recomended changes to the General Manager and j

the Safety Review Committee.

AUTHORITY 6.5.1.7 The Plant Safety Committee shall:

a.

Recommend in writing to the General Manager 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Director, Nuclear Operations and the Safety Review Committee of l

disagreement between the PSC and the General Manager; however, the General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECOROS 6.5.1.8 The Plant Safety 'rmittee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of all PSC activities performed under the responsibility and authority provisions of these technical specifications.

Copies shall be provided to the General Manager and Chairman of the Safety Review Committee.

)

ARKANSAS - UNIT 2 6-7 Amendment No. 3,17

ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIE',4 CCriMITTEE (SRC)_

FUNCTIC'l 6.5.2.1 The Safety Review Committee shall function to provide independent I

review and audit of designated activities in the areas of:

a.

nuclear power plant operations l'

o.

nuclear engineering c.

chemistry and radiochemistry L

d.

metallurgy l

e.

instrumentation and control f.

radiological safety

i IJ g.

mechanical and electrical engineering h.

quality assurance practices I!

' ! C C' IPOS ! TION iiil;5.5.2.2.

The SRC shall be composed of the:

i

'I Chai rman:

Director. Tecnnical and Environmental Services l

l1 ember:

Director, Nuclear Operations Member:

Director, Generation Technology tiember:

Manager, Quality Assurance Memoer:

Arkansas Nuclear One Plant Safety Committee Chairman Member:

Manager, Technical Analysis i

riember:

Arkansas Nuclear One Plant Analysis Superintendent Member:

Director, Generation Engineering i

Member:

tianager, Electrical Enoinparinn Member:

fianager of System Nucl~ ear Operations *

'j 1The Chairman shall designate in writing the alternate chairman in the l absence of the SRC Chairman.

:11cale Soutn services i

ARKANSAS - UNIT 2 6-8 Amendment No. 5,17 i.

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v ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities snall be performed under the cognizance of the SRC. These audits shall encompass:

a.

The conformance of unit operation to provisions contained within 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.

c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 montn:=

d.

The performance of activities required by the Operationa Quality Assurance program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months, e.

The Facility Emergency Plan and implementing procedures at least once per 24 months, f.

The Facility Security Plan and implementing procedures at least once per 24 months.

l i

g.

Any other area of ut.it operation considered appropriate by the SRC or the Vice President, Generation & Construction (VP,G&C).

t 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 at least once per 12 months utili:ing either qualified offsite licensee personnel or an outside fire protection firm.

J.

An inspection and audit of the fire protection and loss preven-tion program shall be performed by a qualified outside fire consultant at least once per 36 months.

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Generation & Construction (VP, G&C) on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

ARKANSAS - UNIT 2 6-11 Amendment No.11

-_~

o ADMINISTRATIVE CONTROLS RECCRDS 5.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicatec below:

3.

Minutes of each SRC meeting shall be prepared, approved and forwarded to tne Vice President, Generation & Construction (VP, G&C) witnin 14 days following eacn meeting.

b.

Reports of reviews encompassed by Section 5.5.2.7 above, snail be precared, approved and forwarded to the Vice President, Generation & Construction (VP, G&C) within 14 days folicwing completion of the review.

c.

Audit recorts encompassed by Section 6.5.2.3 above, shall be forwarded to the Vice President, Generation & Construction (VP, G&C) and to the management positions responsible for the areas audited witnin 30 days after comaletion of the audit.

6.5 REPORTABLE OCCURRENCE ACTION 6.5.1 The following actions shall be taken for REPCRTABLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to tne recuirements of Soecification 6.9.

o.

Eacn REPCRTABLE CCCURRENCE requiring 24 hcur notificatien to the Commission shall be reviewed by the PSC and submitted to the SRC and the Director, Nuclear Operations.

l ARKANSAS UN!T 2 6-12 Amencment No.11,17

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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 violated:

a.

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

b.

The Safety Limit violation shall be reported to the Commission, the Director, Nuclear Operations and to the SRC within 24 l

l hours.

I j

c.

A Safety Limit Violation Report shall be prepared. The report i

shall be reviewed by tne PSC.

This report shall describe (1) l 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 SRC and the Director, Nuclear Operations within l

14 days of the violation.

6.3 PROCEDURES 6.3.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

The applicable procedures recommended in Appendix "A" of a.

Regulatory Guide 1.33, Revision 2, February 1978.

I b.

Refueling operations.

Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation, f.

Fire Protection Program implementation.

6.3.2 Each procedure of 6.S.1 above, and changes thereto, shall be reviewed by the PSC and approved by the General Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

ARKANSAS - UNIT 2 6-13 Amendment No. 5,17

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O ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.3.1 above may be made pro-vided:

a.

The intent of the ordgir.c., procedure is not altered.

b.

The enange is approved by two members of the plant management staff, at least one of wnom holds a Senior Reactor Operator's License on the unit affected.

c.

The cnange is documentad, reviewec by the PSC and approved by i

the General Manager within 14 days of implementation.

l 6.9 REPORTING RECUIREMENTS i

ROUT!NE REPORTS AND REPORTABLE OCCURRENCES j

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports snall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP rep 0RT 6.9.1.1 A summary recort of plant startup and ;ower escalation testin snall ce submitted following (1) receipt of an operating license, (2) g amenoment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The startuo report shall address each of the tests identified in the FSAR and snall include a description of the measured values of the operating can'ditions or characteristics obtained during the test program and a comparison of these values with design predictions and

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speci fications. Any corrective actions that.nere required to obtain satisfactory operation shall also be described. Any aeditional specific i

cetails required in license conditions based on other cannitments shall i

be incluoed in this report.

6.9.1.3 Startuo reports shall be submitted within (1) 90 days following l

completion of tne startup test program, (2)-90 days following resumption 1

or carmencement of commercial power operation, or (3) 9 months following initial criticality, wnichever is earliest.

If the Startuo Report does not cover all three events (i.e., initial criticality, completion of startuo test program, and resumotion or commencement of connercial power operation), sucplementary reports snall be suomitted at least every three months until all three events nave been comoleted.

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ARKANSAS - UNIT 2 6-14 Amencment No. 5 i

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