ML20153B337

Amend 5 to License NPF-6,changing Tech Specs Dealing W/ Administrative Controls & Plant Organization

ML20153B337
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/13/1978
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Arkansas Power & Light Co
Shared Package
ML20153B335	List: ML20153B330 ML20153B337 ML20153B342 ML20153B347
References
NPF-06-A-005 NUDOCS 7812010377
Download: ML20153B337 (19)

Text

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,8 UNITED STATES NUCLEAR REGULATORY COMMISSION y y.

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WASHINGTON, D. C. 20555 S

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%s j ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT NO. 2_

AMENDMENT TO FACILITY OPERATING LICENSE e

Amendment No. 5 License No. NPF-6 1.

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

A. The application for amendment by Arkansas Power & Light Company (the licensee) dated September 22, 1978, as supplemented i

October 17, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the l

Comission's rules and regulations set forth in 10 CFR Chapter I; j

B.

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

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations;

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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 E.

The issuance of this amendment is in accordance with 10 CFR Par';

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

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated 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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

5, are hereby incoroor-ated in the license. Arkansas Power and Light, Company snall operate the facility in accordance with the Technical 4

Specifications.

The licensee shall be exempted from compliance with the follcwing Appendix A Technical Specification related to the steam genern er j

low water level trip setpoint while conducting the steam generf tcr feedwater system waterhanguer testing during the initial startu..

and power ascension testing program.

The value of the steam i

generator low water level trip setpoint in item 8(b) of Technical Specification Table 3.3-4 may be reduced, during this testing only, from a value of greater than or eqt -1 to 49.4 percen I

to greater than or equal to 10.0 percent. The licensee shall be exempted from compliance with Appendix A Technical Specification 3.3.3.6 for the Containment Radiation Mnnitors during Mode 3 operations.

3.

This license amendment becomes effective no later than 90 days after the date of its issuance.

OR THE NUCLEAR REGULATORY COMMISSION

/

n F. Stolz, Chief ight Water Reactors Branch #1 Division of Project Management

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 13, 1978

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ATTACHMENT TO LICENSE AMENDMENT NO. 5 i

i FACILITY OPERATING LICENSE NO. NPF-6 i

DOCKET N0. 50-368 l

Replace the following pages of the Appendices "A" and "B" Technical i

Specifications with the enclosed pages. The revised pages are i

identified by Amendment number and contain vertical lines indicating i-the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

a Appendix "A" Appendix "B" Pages Paaes

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i 6-1 5-1 4

6-2 3

6-3 5-10 6-5 6-6 I

6-7 i

6-8 6-13 4

6-14 6-15 i

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6.0 ADMINISTRATIVE CONTROLS J

i 6.1 RESP 0NSIBILITY.

6.1.1 The General Manager shall be responsible for overall facility l

operation and shall delegate in writing the succession to this responsi-

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bility during his absence.

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6.2 ORGANIZATION i

0FFSITE f

6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

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

a.

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

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shift crew composition shown in Tabic 6.2-1.

b.

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

4 c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

a d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e.

All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A site Fire Brigade of at least 5 members shall be maintained I

onsite at all times. The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

ARKANSAS - UNIT 2 5-1 AmendmentNo.9

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ARKANSAS POWER & LIGHT COMPANY ARKANSAS NtJCLE AR ONE - UNIT 2 EXECUTIVE DIRECTOR H

GENERATION &

N CONSTRUCTION SAFETY REVIEW COMMITTEE I

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I DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR ADMINISTilATIVE TECHNICAL &

GENERATION GENER ATION GENERATION PflOJECTS SERVICES &

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TECilNOLOGY OPE RATIONS ENGINEERING MANAGEMENT PROJECT e

SE RVICES SUPPORT N

I MANAGER OF NUCLEAR OPE RATIONS

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COMMITTEE c+

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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

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LICEN5E APPLICABLE MODES CATEGORY I

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1, 2, 3 & 4 5&6 SOL 1

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• Does not include the licensed Senior Reactor Operator or Senior i

Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.

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1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acconinodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition tc within the minimum requirements of Table 6.2-1.

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ARKANSAS - UNIT 2 6-4

T ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 3

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 who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

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6.4 TRAINING I

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the General Manager and shall l

meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

I 6.4.2 A training program for the Fire Brigade shall be maintained under j

the direction of the General Manager and shall meet or exceed the require-l i

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

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6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY CO M ITTEE (pSC) 4 i

FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the General l

Manager on all matters related to nuclear safety.

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COMPOSITION l

6.5.1.2 The Plant Safety Committee shall be composed of the:

4 Chairman:

Operations and Maintenance Manager l

Member:

Operations Superintendent Member:

Technical Analysis Superintendent l

Member:

Maintenance Superintendent Member:

Instrumentation & Controls Superintendent Member:

Plant Analysis Superintendent Member:

Health Physics Supervisor The General Manager shall appoint in writing an acting chairman in the absence of the Operations and Maintenance Manager.

g ARKANSAS - UNIT 2 6-5 Amendment No.

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ADMINISTRATIVE CONTROLS l

ALTERNATES i

6.5.1.3 All alternate members shall be appointed in writing by the PSC I

Chairman to serve on a temporary basis; however, no more than two i

alternates shall participate as voting members in PSC activities at any l

one time.

3 MEETING FREQUENCY-i 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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OUORUM i

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 e

j and three members including alternates.

RESPONSIBILITIES f

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 i

thereto as determined by the General Manager to affect nuclear l

safety.

j b.

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

l c.

Review of all proposed changes to Appendix "A" Technical

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Specifications.

4 d.

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

I e.

Investigation of all violations of the Technical Specifications i

including the preparation and forwarding of reports covering evaluation and recemendations to prevent recurrence to the General Manager and to the Chairman of the Safety Review Committee. l l

ARKANSAS - UNIT 2 6-6 Amendment No. 5' o

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o ADMINISTRATIVE CONTROLS 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, h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the General Manager or the l

Safety Review Committee.

i.

Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Safety Review Committee.

j.

Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Safety Review Committee.

AUTHORITY 6.5.1.7 The Plant Safety Committee shall:

Recomend in writing to the General Manager approval or disapproval I a.

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 Director, Generation Operations and the Safety Review Comittee of 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.

RECORDS 6.5.1.8 The Plant Safety Committee 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.

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ARKANSAS - UNIT 2 6-7 Amendment No. 5'

ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)

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

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.

quality assurance practices COMPOSITION 6.5.2.2 The SRC shall be composed of the:

Chairnen:

Director, Generation Operations Member:

Director, Generation Technology Member:

Director, Technical and Environmental Services Member:

Manager of Safety Member:

Arkansas Nuclear One General Manager l

Member:

Manager, Technical Analysis Member:

Arkansas Nuclear One Plant Analysis Superintendent i

Member:

Director, Generation Engineering Member:

Radiation and Health Physics Consultant

• Member:

Nuclear Safety Consultant *

• The Radiation and Health Physics Consultant and the Nuclear Safety Consultant shall have an academic degree in engineering or physical science field; and in addition, each shall have a minimum of five years technical experience, of which a minimum of three years shall be in their respective field of expertise.

ARKANSAS - UNIT 2 6-8 Amendment No. 3'

e 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 Comission, the Manager, Nuclear Operations and to the SRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PSC.

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.

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d.

The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Manager, Nuclear Operations within 14 days of the violation.

I 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

a.

The applicable procedures recomended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations, Surveillance and test activities of safety related equipment.

c.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program impit: mentation.

6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the PSC and approved by the General Manager prior to l

implementation and reviewed periodically as set forth in administrative procedures.

ARKANSAS - UNIT 2 6-13 Amendment No.

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o ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made pro-vided:

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 holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the PSC and approved by the General Manager within 14 days of implementation.

l 6.9 rep 0RTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 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 Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

j STARTUp rep 0RT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment 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 startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license coriditions based on other commitments shall be included in this report.

6.9.1.3 Startuo eports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or comencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or comencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ARKANSAS - UNIT 2 6-14 Amendment No. S'

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l ADMINISTRATIVE CONTROLS

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ANNUAL rep 0RTSM 6.9.1.4 %nnual reports covering the activities of the unit as described i

' below for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March 1 of i

the year following initial criticality.

i 6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis for the number of station, 3

utility and other personnel (including contractors) receiving i

exposures greater than 100 mrem /yr and their assopated man rem exposure according to work and job functions, e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. 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 individusi total dose need not be accounted for.

In the aggregate, at least 80% of the t; cal whole body i

dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspee-tions perfomed during the report period (reference Specifica-tion 4.4.5.5.b).

1/ A single submittal may be made for a multiple unit station.

The

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submittal should combine those sections that are common to all units

'at the station.

2f This tabulation supplements the requirements of 520.407 of 10 CFR Part 20.

4RKANSAS - UNIT 2 6-15 Amendment No. 5'

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1 ADMINISTRATIVE CONTROLS i

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MONTHLY OPERATING REPORT l

6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Manage-ment and Program Analysis, U.S. Nuclear Regulatory Commission Washington, D.C.

20555, with a copy to the Regional Office of Inspection and Enforce-I ment, no later than the 15th of each month following the calendar month covered by the report.

I REPORTABLE OCCURRENCES 1

l 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 i

below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to i

fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP J

6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile 3

transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup 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 supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

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a.

Failure of the reactor protection system or other systems i

subject to limiting safety system settings to initiate the i

required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety d

system setting in the technical specifications or failure to complete the required protective function.

b.

Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.

l c.

rmornal degradation discovered in fuel cladding, reactor cooim orassure boundary, or primary containment.

ARKANSAS - UNIT 2 6-16 w

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i 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility l

Corporate responsibility for implementation of the Environmental l

j Technical Specifications, and for assuring that station operations

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i are controlled to provide protection for the environment has been i

q assigned to the Executive Director of Generation and Construction.

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. The ANO General Manager, through the Engineering and Technical 1

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Support Manager, and Technical Analysis Superintendent shall be responsible for compliance with the Environmental Technical

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Specifications at the plant level.

f The Manager of Technical Analysis shall be responsible for radio-1 j

logical analysis of environmental samples, i

5.2 Organization

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Figure 5-1 shows the organi:ation chart at both plant and j

corporate levels relative to environmental matters.

l 5.3 Review 5.3.1 Plant Safety Committee j

The Plant Safety Committee (PSC) shall be responsible for review of the following:

a.

Proposed changes to the Environmental Technical 4

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Specifications and the evaluated impact of the changes.

b.

Proposed written procedures, as described in Specification 5.5, and proposed changes thereto which affect the plant's environmental impact.

f l.

Amen hent No.

E 5-1

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c.

Proposed changes or modifications to plant systems or equipment which would affect the plant's environmental

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impact.

j d.

Results of the Environmental Monitoring Programs.

Investigation of all reported instances of violations of e.

Environmental Technical Specifications. Where investigation warrants, instances shall be evaluated and recommendations formulated to prevent recurrence.

5.3.2 Safety Review Committee The Safety Review Committee (SRC) shall be responsible for review of the following:

a.

The environmental evajustions for 1) changes to pro-cedures, equipment or systems and 2) tests or experiments completed under Section 5.7.3, to verify that such actions did not constitute an unreviewed environmental question.

b.

Proposed changes to procedures, equipment or systemswhich involve an unreviewed environmental question as defined in Section 5.7. 3.B.

c.

Proposed changes to the Environmental Technical Specifi-cations and the evaluated impact of the changes.

d.

Results of the Environmental Monitoring Programs.

j Investigation of all reported instances of violations e.

of Environmental Technical Specifications.

5-2 l

a.

Records and drawing changes reflecting plant design modifications made to systems and equipment as described in Specification 5.6.3.

b.

Records of environmental surveillance data.

c.

Records to demonstrate compliance with the limiting conditions for operation in'Section 2.

5.8.2 All other records and logs relating to the environmental technical specifications shall. be retained for five years.

5. 9 Special Requirements The AN0-2 transmission line' rights-of-way have low growing species of cedar, sumac, oak and shrubs as a screen and to assist with erosion control.

planting of grass and clover shall be carried out tn further prevent erosion.

Further plantings of game food and clover shall be made in cooperation with landowners and the Arkansas Game and Fish Commission. No herbicides shall be used for land management on transmission line right-of-way.

The grounds in the immediate vicinity of the plant building shall be landscaped.

Remaining portions of the plant site shall be allowed to remain in their present wild state with the exception of the area on which the visitors center will be located.

This area is located approximately 0.7 miles north east of the Containment on a hill overlooking the plant.

5-9 l

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E.\\ECUTIVE DIRECTOR CENERATION AND CONSTRUCTION I

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DIRECTOR DIRECTOR CENERATION OPERATIONS TECHNICAL AND ENVIRONMENTAL SERVICES ARKANSAS NUCLEAR ONE MANAGER GENERAL MANAGER TECHNICAL ANALYSIS ARKANSAS NUCLEAR ONE QiEMISTS ENGINEERING AND TECHNICAL SUPPORT AND BIOLOGISTS ARKANSAS NUCLEAR ONE TECHNICAL ANALYSIS SUPERINTENDENT I

ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE ARKANSAS NUCLEAR ONE CHEMICAL AND RADI0 CHEMISTRY HEALTH PHYSICS ENVIRONMENTAL SUPERVISOR SUPERVISOR SUPERVISOR ARKANSAS" POWER 6 LIGHT CO.

ENVIRONMENTAL SURVEILLANCE FIG. NO.

ARKANSAS NUCLEAR ONE ORGANIZATION CHART 5-1 S-10 Amendment No. $1 l

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