ML20237B623

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Proposed Tech Specs Re Planned Organizational Changes
ML20237B623
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/04/1987
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20237B619 List:
References
NUDOCS 8712170008
Download: ML20237B623 (8)
v • d • e


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PROPOSED TECHNICAL SPECIFICATIONS CHANGES 8712170008 871204 PDR ADOCK 05000368 P

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Executive Director, ANO Site Operations shall be responsible for l

overall facility operations 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 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 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 l

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.

l 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 control 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, $7, 73 L

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OPERATOR OPERATOR ER EI (1) THE HE ALTH PHYSICS SUPERINTENDENT REPORTS TO THE TECHNICAL SUPPORT MANAGER IN ADt04NISTRATIVE FATTERS AND ROUTINE HEALTH PMTSICS CONCERNS AND ME REPOflTS TO THE EXECUTIVE DIRECTOR. A800 SITE OPERA 1JONS Ist MATTERS OF RADsOLOSICAL MEALTM SAFETY AND POLICY.

(E) THE NUCLE AR OUAttTV SENERAL MANAGER REPORTS TO THE VICE PREttDENT OF NUCLE AR OPERATIONS. HE MAS WASTE WASTE tetTERF ACE WITH THE EXECUTIVE DIRECTOR. A080 SITE OPERATIONS IN DARLY COedefUN4C ATSONS, AND MAS 08MECT COstTROL CONTROL ACCESS TO THE SENIOR WICE PRESIDENT ENERSY SUPPLY ON ANY MATTERS CONCEleseuse NUCLEAR OUALITV.

OPERATOR OPERATOR AUEILIAftY AUIILIARY OPER A T OR OPERATOR FIGURE 6.2-2 FUNCTIONAL ORGANIZATION FOR PLANT OPERATIONS ARKANSAS - UNIT 2 6-3 Amendment No. 17,D R,73

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 Executive Director, AND Site 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 Executive Director, AND Site Operations and shall. meet l

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 Executive Director, AND Site Operations on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of a Chairman who is the General Manager, Plant Support and a Nuclear Software Expert *.

Additionally, the Executive Director, ANO Site Operations shall also designate in writing eight additional members which will include a management representative in each of the following functional areas:

Operations Maintenance Training Licensing Plant Engineering Quality Assurance Reactor Engineering i

Health Physics The Executive Director, AND Site Operations shall designate in writing the Alternate Chairman in the absence of the PSC Chairman.

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  • See Page 6-Sa ARKANSAS-UNIT 2 6-5 Amendment No. 5, 12, 17, i

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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 proposed changes to station administrative procedures.

b.

Review and approval of proposed safety evaluations completed per the provisions of 10CFR50.59 to confirm that such items will not constitute an unreviewed safety question.

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 recommendation to prevent recurrence to the Executive Director, AND Site Operations and l

to the Chairman of the Safety Review Committee.

ARKANSAS-UNIT 2 6-6 Amendment NO. 6, 17, 52, 73

ADMINISTRATIVE CONTROLS i

f.

Review of events requiring 24 hours2.777778e-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 Executive Director, AN0 Site Operations or the Safety Review Committee.

i.

Review of the Plant Security Plan and subaittal of recommended changes to the Executive Director, AND Site Operations and the

-l Safety Review Committee.

j.

Review of the Emergency Plan and submittal of recommended changes to the Executive Director, ANO Site Operations and Safety Review l

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 Executive Director, ANO Site Operations; however, the Executive Director, ANO Site Operations shall have_ responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS

6. 5.1. 8 7.19 Plant Safety Committee shall maintain :ritten minutes of each PSC meetiag that at a minimum, document the results of all PSC activities performed Lnder tn.: responsibility and authority provisions of these technical specificati9ns.

Copies shall be provided to the Executive Director, AND #ite Operations and Chairman of the Safety Review Committee.

ARKANSAS-UNIT 2 6-7 Amendment No. 5, 17, 25, 52, 50, 73

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION l

6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

I 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 L

(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.

These procedures should include provisions to assure that sufficient margin is maintained in CPC Type I addressable i

constants to avoid excessive operator interaction with the CPCs 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.

Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

h.

New and spent fuel storage, i.

ODCM and PCP implementation.

j.

Postaccident sampling (includes sampling of reactor coolant, radioactive iodines and particulate in plant gaseous effluent, and the containment atmosphere).

6.8.2 Each procedure of 6.8.1 above, and the changes thereto, shall be reviewed per the provisions of 10CFR50.59 by a reviewer certified by the PSC or SRC as being qualified to perform such reviews.

l 6.8.3 Each procedure of 6.8.1 above, the changes thereto, shall be approved by the Executive Director, AN0 Site Operations; Plant Manager or responsible General Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

ARKANSAS-UNIT 2 6-13 Amendment No. 24, 28, 43, 52, 60, 63, 73, 77

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ADMINISTRATIVE CONTROL 6.8.4 Temporary changes to procedures of 6.8.1 above may be made provided:

l 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, and approved by the Executive Director, ANO Site Operations; Plant Manager or 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 l

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 oe 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 test program, and resumption or co nencement 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. 5, 52, 73 iw_----___-_-_.

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