ML19295A611
| ML19295A611 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/29/1980 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML19295A610 | List: |
| References | |
| NUDOCS 8010020498 | |
| Download: ML19295A611 (9) | |
Text
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6.0 ADMINISTRATIVE CONTROLS
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6.1 R ESPONSIBILITY 1he Nuclear Operations Manager shall be accountable for overall facility operation.
In his absence the Deputy Nuclear Operations Manager or an alternate designated in writing by the Nuclear Operations Manager shall 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.
iACILITY 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 shif t 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, t
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 responsilbilitics during this operation.
6.
The organization of the administration of the Pilgrim I Fire Prevention and Proteation Program shall be as shown on Figure 6.2.3.
A Fire Brigade of 5 members including the Fire Chief 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 S TAFF QUALIFICATIONS The qualifications with regard to educational and experience backgrou.ds of the f acility staf f at the time of appointment to the active position shall meet the requirements as described in the American rational Standards Institure 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
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Culde 1.8, September, 1975.
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6.4 TRAINING A.
A retraining and replacement training program for the facility staff shall l
be maintained under the direction of the Nuclear Operations Manager.
B.
A retraining program for the licensed operators shall be maintained under the direction of the Senior Nuclear Training Specialist and shall meet or exceed the requirements and recommendations of Section 5.5 of ANS1 N18.1-1971 and Appendix A of 10 CFR Part 55.
C.
A training program for the Fire Brigade shall be maintained under the direction of the Fire Protection and Prevention Officer and shall meet or exceed the requirements of Section 27 of the NFPA Code 1975. Training sessions will be held quarterly.
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208a
6.5 REVIEW AND AUDIT f..
OPERATIONS REVI,EW COMMITTEE (ORC) 1.
FUNCTION The ORC shall function to advise the Nuclear Operations Manager on all matters related to nuclear safety.
2.
COMPOSITION The ORC shall be composed of the:
Chairman:
Deputy Nuclear Operations Managers Member:
Management Services Group Leader Member:
Chief Operating Engineer Member:
Chief Technical Engineer Member:
Chief Maintensnce Enginter Member:
Chief Radiological Engineer 3.
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 Chairman.
5.
QUORUM A quorum of the ORC shall consist of the Chairman and three members including alternates.
6.
RESPONSIBILITIES The ORC shall be responsible for:
Review of 1) all procedures required by Specification 6.8 a.
and changes thereto, 2) any other proposed procedures or changes thereto that affect nuclear safety, b.
Reviev of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the Technical Specifications.
c.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications anc c.
shall prepare and forward a report covering evaluation and recom-mendations to prevent recurrence to the Nuclear Operations Manager and to the NSRAC Chairman.
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f.
Review of facility operations to detect potential safety hazards, g.
Performance 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.
i.
Review of the Emergency Plan and implementing procedures and changes to the plan and procedures.
7.
AUTHORITY The ORC shall:
Inform the Nuclear Operations Ibnager in writing their a.
approval or disapproval of items considered under 6.5. A.6(a) through (d) above, b.
Render determinations in writing with regard to whether or not each item considered under 6.5.A.6(a) through (e) above constitutes an unreviewed safety question.
Provide immediate written notification to the Nuclear Operations c.
Manager and the Nuclear Safety Review and Audit Committee of disagreement between the ORC members and the ORC Chairman.
The Nuclear Operations Manager shall have responsibility for resolution for such disagrecments pursuant to 6.1 above.
8.
RECORDS The ORC shall maintain written minutes of each meeting and copies shall be provided to the Nuclear Operations Manager and NSRAC Chairman.
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; 2.
nuclear engineering; 3.
chemistry and radiochemistry; 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 Chairman and other members shall be appointed by the Vice President - Nuclear, or such other person as he shall designate.
NSRAC members shall collectively possess experience and competence required to review and audit the designated areas noted in 6.5.B.1.
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 Vice President-Nuclear, with a copy to the Nuclear Operations Manager within 21 days following the completion of the review.
c.
Audit reports encompassed by Section 6.5.B.8 above shall be forwarded to the 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 Nuclear Operations 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 Nuclear Operations 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, aystems 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 Nuclear Operations 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 reco=mendations of Sections 5.1 and 5.3 of ANSI N18.7 - 1972 and Appendix "A" of USNRC Regulatory Guide 1.33, except as provided in 6.8.B and 6.8.C below.
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B.
Each pracedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the ORC and approved by the ORC Chairman prior to implementation and periodically as set forth in station procedures.
C.
Temporary changes to procedures of 6.8.A above may be made provided:
1.
The intent of the original procedure is not altered.
2.
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.
3.
The change is documented, reviewed subsequently by the ORC, and ap-proved by the ORC Chairman within 7 days of implementation.
D.
Written procedures to implement the Fire Protection Program shall be established, implemented and maintained.
6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.
A.
Routine Reports 1.
Startup Report.
A su= mary 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.
The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or character-istics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisf actory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
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 commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
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Office of the President President Senior Vice Presidents Vice President Nuclear Nuclear Safety Review
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l Nuclear Operations Nuclear Operations Quality Assurance Nuclear Engineering Manager - PNPS Support Manager Manager Deputy Managers (2)
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Review Committee Figure 6.2.1 Isoston Edison Company -- Organization for Operation of Pilgrim I
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FIGURE 6.2.3 ADMINISTRATION OF T!!E PILGRIM NUCLEAR PLANT FIRE PREVENTION AND PROTECTION PROGRAM NUCLEAR OPERATIONS MANAGER DEPUTY MANAGERS PILGRIM STATION FIRE PREVENTION AND PROTECTION OFFICER FIRE CHIEF (WATCH ENGINEER)
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