ML20065T425

Proposed Tech Spec Changes to Section 6.0, Administrative Controls

ML20065T425
Person / Time
Site:	Pilgrim
Issue date:	10/25/1982
From:	BOSTON EDISON CO.
To:
Shared Package
ML20065T412	List: ML20065T411 ML20065T425
References
NUDOCS 8211020452
Download: ML20065T425 (10)

Text

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY The Station Manager shall be accountable for overall facility operation.

In his absence the Station Manager shall designate in writing the individual to assume this responsibility.

6.2 ORGANIZATION A. OFFSITE The Company organization for station management and technical support shall be as shown on Figure 6.2.1.

B. FACILITY The Facility organization shall be as shown on Figure 6.2.2 and:

1. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.1.

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

3. At least two Licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.'

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

5. ALL CORE ALTERATIONS performed while fuel is in the reactor vessel after the initial fuel loading 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.

l 6. A Fire Brigade of 5 members including a Fire Brigade Leader shall be maintained on site at all times. This excludes 3 members of the minimum shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency.

6.3 FACILITY STAFF QUALIFICATIONS The qualifications with regard to educational and experience backgrounds of the facility staff at the time of appointment to the active position shall meet the requirements as described in the American National Standards Institute N18.1-1971, " Selection and Training of Personnel for Nuclear Power Plants." In addition, the individual performing the function of Radiation Protection Manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September, 1975.

8211020452 821025 DR ADOCK 05000293 PDR - 208 -

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c-6.4 TRAINING A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager. The training progrcms for the licensed personnel shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55. The training programs for the Fire Brigade shall meet or exceed the requirements of NFPA Standard No. 27-1975 " Private Fire Brigade". Fire Protection Training sessions will be held quarterly.

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.I Boston Edison company - organization for operation Of Pilgrim I

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& Station Security I AmendRant No. 21. M. 46 - 209 -

Figure 6.2.1 i

PILGRIM NUCLEAR POWER STATION i

STATION MANAGER (ORC)

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i I CHIEF CHIEF STATION CHIEF 3

CHIEF OPERATING RADIOLOGICAL SERVICES TECHNICAL ENGINEER (ORC) MAINTENANCE ENGINEER (ORC) GROUP LEADER ENGINEER (ORC) i (SRO) ENGINEER (ORC)

TECHNICAL TECHNICAL TECHNICAL TECHNICAL WATCH STAFF STAFF STAFF ENGINEER (S) STAFF l (SRO)

Code:

OPERATING ORC - Member of ORC SUPERVISOR (S)

RO - NRC Reactor Operator License (RO) SRO - NRC Senior Reactor Operator License NUCLEAR AUXILIARY Pilgrim Station Organization OPERATOR Figure 6.2.2 NUCLEAR PLANT l OPERATOR l (RO)

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PILGRIM NUCLEAR POWER STATION MINIMUM OPERATING SHIFT CREW COMPOSITION TECHNICAL SPECIFICATION TABLE 6.2-1

• CREW MINIMUM NUMBER ON DUTY STATION CONDITION OPERATING Licensed Senior Reactor Operator 1 Licensed Reactor Operator 2 Unlicensed Operator 2 Shift Technical Advisor ** 1 Licensed Senior Reactor Operator 1 COLD SHUTDOWN Licensed Reactor Operator 1 AND 1

REFUELING Unlicensed Operator None Required Shift Technical Advisor **

• Higher grade licensed operators may take the place of lower grade licensed or unlicensed personnel.

• • Provides an On-Shift Technical Advisor who has a bachelor's degree or equivalentll) in a scientific or engineering dicipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

, (1) Or equivalent is defined as an Associate Degree in nuclear or mechanical engineering plus 5 years nuclear experience.

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Amendment No.

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6.5 REVIEW AND AUDIT A. OPERATIONS REVIEW COMMITTEE (ORC)

1. FUNCTION The ORC shall function to advise the Station Manager on all matters  !

related to nuclear safety.

2. COMPOSITION The ORC shall be composed of the Chairman: Station Manager l Member: Chief Operating Engineer Member: Chief Technical Engineer Member: Chief Maintenance Engineer Member: Chief Radiological Engineer l Member: Onsite Safety & Performance Group Leader The ORC Chairman may appoint subcommittees composed of personnel who are not members of ORC to perform staff work necessary to the efficient functioning of ORC.

ALTERNATES Alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate in an ORC quorum at any one time.

4. MEETING FREQUENCY The ORC shall meet at least once per calendar month and as convened by the ORC Chaiman.

5. QUORUM A quorum of the ORC shall consist of the Chaiman and a majority of members including alternates.

6. RESPONSIBILITIES l

The ORC shall be responsible for:

a. Review of 1) all procedures required by Specification 6.8 j

and changes thereto, 2) any other proposed procedures or

changes thereto that affect nuclear safety.

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

c. Review of all proposed changes to the Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nulcear safety.

e. Investi5ation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and l

recommendations to prevent recurrence to the Vice President-Nuclear Operations and to the NSRAC Chaiman.

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f. R:: view cf facility operations to detect potential safety hazards,

g. Perfonnance of special reviews and investigations and reports thereon as requested by the NSRAC Chairman.

h. Review of the Station Security Plan and implementing procedures and changes to the plan and procedures.

1. Review of the Emergency Plan and implementing procedures and changes to the plan and procedures.

j. Review the Station Fire Protection Plan and implementing procedures and~ changes to the plan and procedures.

k. Render detenninations in writing with regard to whether or not each item considered under 6.5.A.6(a) through (e) above con-stitutes an unreviewed safety question.

1. Provide immediate written notification to the Vice President -

Nuclear Operations and the Nuclear Safety Review and Audit Conunittee, of disagreement between the ORC members and the ORC Chairman. The Vice President - Nuclear Operations shall have responsibility for resolution for such disagreements.

7. AUTHORITY The ORC shall recommend approval or disapproval to the Station Manager on those areas of responsibility specified in Section 6,5,A.6

8. RECORDS l The ORC shall maintain written minutes of each meeting.

B. NUCLEAR SAFETY REVIEW AND AUDIT COMMITTEE (NSRAC)

1. FUNCTION --

The NSRAC shall function to provide independent review and audit of designated activities in the areas of:

1. nuclear power plant operations; l 2. nuclear engineering;

3. chemistry and radiochemistry; l 4. metallurgy;

5. instrumentation and control;

6. radiological safety;

7. mechanical and electrical engineering;

8. quality assurance practices

9. fire protection

2. COMPOSITION The NSRAC Chainnan and other members shall be appointed by the Senior Vice President - Nuclear, or such other person as he shall l designate. NSRAC mcmbers shall collectively possess experience and competence . required to review and audit the designated areas noted in 6.5.B.1.

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The collective competence of the comittee will be maintained as changes to the membership are made. The membership shall consist of a minimum of five persons.

3. ALTERNATES Alternate members shall be appointed in writing by the Senior I Vice President - Nuclear or the Chairman to serve on a temporary basis; however, no more than two alternates shall participate in a quorum at any one time.

4. CONSULTANTS Consultants shall be utilized as detemined by the NSRAC Chairman to provide expert advice to the NSRAC. ,

5. MEETING FREQUENCY The NSRAC shall meet at least once per six months.

6. QUORUM A quorum of the NSRAC shall consist of the Chaiman and a majority of the NSRAC members including alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

7. REVIEW .

The NSRAC shall review:

a. The safety evaluations for:

(1) Changes to procedures, equipment or systems and (2) Tests or experiments completed under the provision of l 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 which involve l an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety i question as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or operating license.

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

f. Significant operating abnomalities or deviations from normal and expected perfomance of plant equipment that effect nuclear safety.

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g. All events which are required by regulation or Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

h. Any other matter involving safe operation of the nuclear plant which NSRAC deems appropriate for consideration or which is referred to NSRAC by the onsite operating organization or by other functional organizational units within Boston Edison. -

1. Reports and meeting minutes of the Operations Review Comittee.

8. AUDITS Audits of facility activities shall be perfomed under the cognizance of the NSRAC. These audits shall encompass:

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

b. The training and qualifications of the entire facility staff at least once per year,

c. The results of all actions required by deficiences occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.

d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two years.

e. The Emergency Plan and implementing procedures at least once per two years,

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

g. Any other area of facility operation considered appropriate by the NSRAC or the Senior Vice President - Nuclear.

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

9. AUTHORITY The NSRAC shall report to and advise the Senior Vice President -

Nuclear on those areas of responsibility specified in Section 6.5.B.7 and 6.5.B.8.

10. RECORDS Records of NSRAC activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each NSRAC meeting shall be prepared, approved and famarded to the Senior Vice President - Nuclear, NSRAC members, and others the Chaiman may designate, within 14 days following each meeting.

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b. Reports of reviews encompassed by Section 6.5.B.7 e, f, g and h above, shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear, with a copy to the Station Manager within 21 days following the completion of the review.

c. Audit reports encompassed by Section 6.5.B.8 above shall be i

I forwarded to the Senior Vice President - Nuclear and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION The following actions shall be taken in the event of a reportable occurrence:

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

to the requirements of Specification 6.9.

B. Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the ORC and submitted to the NSRAC Chairman and the Station Manager.

6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a Safety Limit is violated:

A. The provisions of 10. CFR 50.36(c) (1) (1) shall be complied with immediately.

B. The Safety Limit Violation shall be reported to the Commission, the Station Manager, and to the NSRAC Chairman immediately.

C. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the ORC. 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 NSRAC Chairman, and the Station Manager within 14 days of the violation.

6.8 PROCEDURES A. Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section 5.1 and 5.3 of ANSI N18.7 - 1972 and.

Appendix "A" of UNSRC Regulatory Guide 1.33, except as provided in 6.8.B and 6.8.C below,

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