ML20138R017

Proposed Tech Specs,Clarifying Responsibility of Safety Review Committee Appointments & Total Membership of Committee & to Make Section 6.5.2.8 Consistent W/Sts

ML20138R017
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/20/1985
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20138R013	List: 2CAN128507, Application for Amend to License NPF-6,changing Tech Specs to Clarify Responsibility of Safety Review Committee Appointments & Total Membership of Committee & to Make Section 6.5.2.8 Consistent W/Sts.Fee Paid ML20138R017
References
NUDOCS 8512300215
Download: ML20138R017 (12)

Text

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6. 0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Director, Site Nuclear Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION

, OFFSITE 4

4 6.2.1 The of fsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

3 FACILITY STAFF 1

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 j shift crew composition shown in Table 6.2-1.

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

c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor I

shutdown and during recovery from reactor trips.

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

e. All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent 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 shift crew necessary for safe shutdown

, of the unit and any personnel required for other essential functions during a fire emergency.

g. Administrative controls shall be established to limit the amount 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. 82-12).

ARKANSAS-UNIT 2 6-1 Amendment No. 5, 52, 57

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FIGURE 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATIONS ARKANSAS - UNIT 2 ,

6-3 Amendment No. U ,29,52

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 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) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a bachelors 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.

6.4 TRAINING -

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director, Site Nuclear Operations and shall meet or exceed the requirements 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 the Fire Brigade shall be maintained under the direction of the Director, Site Nuclear Operations and shall 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 quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)

FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the Director, Site Nuclear Operations on all matters related to nuclear safety.

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

Chairman: Manager of Special Projects Member: Operations Manager Member: Maintenance Manager Member: Training Manager Member: Technical Analysis Superintendent '

Member: Engineering Manager Member: Quality Assurance Superintendent Member: Reactor Engineering Supervisor Member: Health Physics Superintendent Member: Nuclear Sof tware Expert

• The Director, Site Nuclear Operations shall designate in writing the Alternate Chairman in the absence of the PSC Chairman.

• See Page 6-Sa ARKANSAS - UNIT 2 6-5 Amendment No. 5,12,I7, 20,29,52

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 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) the Health Physics Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a bachelors 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.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director, Site Nuclear Operations and shall meet or exceed the requirements 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 the Fire Brigade shall be maintained under the direction of the Director, Site Nuclear Operations and shall 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 quarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY COMMITTEE (PSC)

FUNCTION 6.5.1.1 The Plant Safety Committee shall function to advise the Director, Site Nuclear Operations on all matters related to nuclear safety.

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

Chairman: Manager of Special Projects Member: Operations Manager Member: Maintenance Manager Member: Training Manager Member: Technical Support Manager Member: Engineering Manager Member: Plant Modifications Manager Member: Reactor Engineering Supervisor Member: Health Physics Superintendent Member: Nuclear Software Expert

• The Director, Site' Nuclear Operations shall designate in writing the Alternate Chairman in the absence of the PSC Chairman.

• See Page 6-Sa ARKANSAS - UNIT 2 6-5 Amendment No. B,I2,I7, 20,29,52

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.

QUORUM 6.5.1.5 The minimum quorum of the PSC 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.

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 Director, Site Nuclear Operations to affect nuclear safety.

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

c. Review of all proposed changes to Appendix "A" Technical Specifications.

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

e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Director, Site Nuclear Operations and to the Chairman of the Safety Review Committee.

f ARKANSAS-UNIT 2 6-6 Amendment No. 6, 77, 52

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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 Commission.

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

h. Performance of special reviews, investigations or analyses, and reports thereon as requested by the Director, Site Nuclear Operations or the Safety Review Committee.

i. Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Director, Site Nuclear Operations and the Safety Review Committee.

j. Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Director, Site Nuclear Operations and the Safety Review Committee.

k. Review of changes to the Offsite Dose Calculation Manual and 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) 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 Vice President, Nuclear Operations and the Safety Review Committee of disagreement between the PSC and the Director, Site Nuclear Operations; however, the Director, Site Nuclear Operations 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 Director, Site Nuclear Operations and Chairman of the Safety Review Committee.

ARKANSAS-UNIT 2 6-7 Amendment No. 5, 77, 25, 52, 60

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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 Safety Review Committee shall be composed of a Chairman and eight members which collectively have the experience and competence required to review problems in the areas specified in Section 6.5.2.1, a-h.

The Vice President, Nuclear Operations shall designate, in writing, the Chairman and all SRC members.

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

ARKANSAS - UNIT 2 6-8 Amendment No. 5, 27, 25, 52

ADMINISTRATIVE 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 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 methods of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix "B",

at least ence 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 unit operation considered appropriate by the SRC or the Vice President, Nuclear Operations.

h. The Facility Fire Protection Program and implementing procedures at leest 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 utilizing either qualified off-site licensee personnel or an outside fire protection firm.

j. The Offsite Dose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.

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

AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Nuclear Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.

ARKANSAS - UNIT 2 6-11 Amendment No. II,25, 41,52,60

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ADMINISTRATIVE CONTROLS RECORDS ^

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

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the Vice President, Nuclear Operations within 14 days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, Nuclear 4

Operations within 14 days following completion of the review.

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c. Audit reports encompassed by Section 6.5.2.8 above, shall be i- forwarded to the Vice President, Nuclear Operations and to the j management positions responsible for the areas audited within 30 days after completion of the audit.

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

a. The Commission shall be notified and/or a report submitted

pursuant to the requirements of Specification 6.9.

, b. Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the i Commission shall be reviewed by the PSC and submitted to the SRC

! and the Vice President, Nuclear Operations by the Director, Site Nuclear Operations.

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ARKANSAS - UNIT 2 6-12 Amendment No. II,I7,25,52 e

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ADMINISTRATIVE CONTROLS

6. 7 SAFETY LIMIT VIOLATION 6.7.] 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 Vice President, 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.

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

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

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

b. Refueling operations,

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation,

g. Modification of Core Protection Calculator (CPC) Addressable Constants NOTE: Modification to the CPC addressable constants based on information obtained through the Plant Computer

- CPC data link shall not be made without prior approval of the Plant Safety Committee. i

h. New and spent fuel storage. '

i. Offsite Dase Calculation Manual and Process Control Program  !

implementation.

j. Post-accident sampling (includes sampling of reactor coolant, radioactive iodines and particulates in plant gaseous effluent,

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and the containment atmosphere).

6.8.2 Each procedure of 6.8.1 above, the changes thereto, shall be reviewed by the PSC and approved by the Director, Site Nuclear Operations or the responsible General Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

ARKANSAS - UNIT 2 6-13 Amendment No. 24, 28, #3, 52, 60, 63

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• ADMINISTRATIVE CONTROLS l 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

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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 Director, Site Nuclear Operations or the responsible General Manager within 14 days of implementation.

6.9 REPORTING 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 Administrator of the Regional Office unless otherwise noted.

STARTUP REPORT

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 power 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 significantly altered the nuclear, thermal, or hydraulic performance 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 conditions based on other commitments shall be included in this report.

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 initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup l test program, and resumption or commencement of commercial power operation),

l supplementary reports shall be submitted at least every three months until l all three events have been completed.

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ARKANSAS - UNIT 2 6-14 Amendment No. 5, 52 l