ML17324B165
| ML17324B165 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/01/1986 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17324B164 | List: |
| References | |
| NUDOCS 8612090497 | |
| Download: ML17324B165 (17) | |
Text
ATTACHMENT 2 TO AEP:NRC:0659J REVISED TECHNICAL SPECIFICATION PAGES TO D.
C.
COOK NUCLEAR PLANT UNIT ~ NOS. I AND 2 8612090497 861201 PDR ADOCK 05000315 PDR
6.0 ADMINISTRATIVECONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in hriting 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 referenced in Figure 1.7-4 of the FSAR.
FACILITY STAFF 6.2.2 The facility organization shall be shown in Figure 1.7-5 of the FSAR 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 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.
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 or any personnel required for other essential functions during a fire emergency.
g.
The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with NRC Policy Statement on working hours (Generic Letter No. 82-12).
D.
C.
COOK - UNIT 1 6-1 Amendment No.
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C.
COOK - UNIT 1 6-2 Amendment No.
This page intentionally left, blank D.
C.
COOK - UNIT l 6-3 Amendment No.
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Supervisor, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975; (2) the Shift
-Technical Advisor, who shall have a bachelor's 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; (3) personnel who perform inspections on safety-related construction and major modifications shall be qualified to ANSI N45.2.6 (1978);
and (4) personnel who perform non-destructive testing examinations shall be qualified to SNT-TC-1A.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator 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 Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.
D.
C.
COOK - UNIT 1 6-5 Amendment No.
ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The PNSRC shall be composed of representatives of the following functional areas:
Chairman:
Plant Manager or Designee Member:
Managerial ---------- Assistant
Assistant Support
"Assistant
Lz.censing Plant Manager
- Production Plant Manager
- Technical Plant Manager
- Administration Coordinator Member:
Operations Operations Superintendent Two Production Supervisors
- Operations Shift Supervisor Member:
Technical Support Physical Science Superintendent Technical Engineering Superintendent Computer Sciences Superintendent Member:
Maintenance Maintenance Superintendent Two Production Supervisors
- Maintenance Production Controller
- Maintenance Member:
Instrumentation-----
and Controls I&C/Planning Superintendent I&C Supervisor Production Supervisor
- I&C Member:
Radiation Protection-Plant Radiation Protection Supervisor ALARA Coordinator MEETING FRE UENCY 6.5.1.4 The PNSRC shall meet at least once per calendar month and as convened by the PNSRC Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the PNSRC shall consist of the Chairman or his Designee and a member from at least four of the functional areas listed in 6.5.1.2.
D.
C.
COOK - UNIT 1 6-6 Amendment No.
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 facility shall be placed in at least HOT STANDBY within one hour.
b.
The Safety Limit violation shall be reported to the Commission and to the Chairman of the NSDRC 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 PNSRC.
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 Chairman of the NSDRC 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,
- November, 1972.
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.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev.
1, June 1974 and Regulatory Guide 4.1, Rev.
1, April 1975.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes
- thereto, shall be reviewed by the PNSRC and approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
Contractor procedures which are subject to an approved 10 CFR 50 Appendix B Quality Assurance program are not required to be reviewed by the PNSRC.
This includes procedures that are used either onsite or offsite.
D.
C.
COOK - UNIT 1 6-13 Amendment No.
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation 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 referenced in Figure 1.7-4 of the FSAR.
FACILITY STAFF 6.2.2 The facility organization shall be shown in Figure 1.7-5 of the FSAR 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 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.
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 or any personnel required for other essential functions during a fire emergency.
g.
The amount of overtime worked by plant staff members performing safety-related functions must be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
D.
C.
COOK - UNIT 2 6-1 Amendment No.
This page intentionally left blank D.
C.
COOK - UNIT 2 6-2 Amendment No.
This page intentionally left blank D.
C.
COOK - UNIT 2 6-3 Amendment No.
6.0 ADMINISTRATIVE,CONTROLS 6.3 FACILITY STAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation. Protection Supervisor, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975; (2) the Shift Technical Advisor, who shall have a bachelor's 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; (3) personnel who perform inspections or safety-related construction and major modifications shall be qualified to ANSI N45.2.6 (1978);
and (4) personnel who perform non-destructive testing examinations shall be qualified to SNT-TC-1A.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Coordinator 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 Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.
6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY REVIEW COMMITTEE PNSRC FUNCTION 6.5.1.1 The PNSRC shall function to advise the Plant Manager on all matters related to nuclear safety.
D.
C.
COOK - UNIT 2 6-5 Amendment No.
D INISTRATIVE CONTRO S
COMPOSITION 6.5.1.2 The PNSRC shall be composed of representatives of the following functional areas:
Chairman:
Plant Manager or Designee Member:
Managerxal Assistant Assistant Assistant Licensing Plant Manager
- Production Plant Manager
- Technical Support Plant Manager
- Administration Coordinator Member:
Operations Operations Superintendent Two Production Supervisors
- Operations Shift Supervisor Member:
Technical Support Physical Science Superintendent Technical Engineering Superintendent Computer Sciences Superintendent Member:
Maintenance---------
Maintenance Superintendent Two Production Supervisors
- Maintenance Production Controller
- Maintenance Member:
Instrumentation-----
and Controls I&C/Planning Superintendent I&C Supervisor Production Supervisor
- I&C Member:
Radiation Protection-Plant Radiation Protection Supervisor ALARA Coordinator MEETING FRE UENCY 6.5.1.4 The PNSRC shall meet at least once per calendar month and as convened by the PNSRC Chairman or his designated alternate.
UORUM 6.5.1.5 A quorum of the PNSRC shall consist of the Chairman or his Designee and a member from at least four of the functional areas listed in 6.5.1.2.
RESPONSIBILITIES 6.5.1.6 The PNSRC 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 Plant Manager 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 plant systems or equipment that affect nuclear safety.
D.
C.
COOK - UNIT 2 6-6 Amendment No.
ADMINISTRATIVECONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within one hour.
b.
The Safety Limit violation shall be reported to the Commission,and to the Chairman of the NSDRC 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 PNSRC.
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 Chairman of the NSDRC 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, November,- 1972.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan'mplementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev.
1, June 1974 and Regulatory Guide 4.1, Rev.
1, April 1975.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes
- thereto, shall be reviewed by the PNSRC and approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.
Contractor procedures which are subject to an approved 10 CFR 50 Appendix B Quality Assurance program are not required to be reviewed by the PNSRC.
This includes procedures that are used either onsite or offsite.
II D.
C.
COOK - UNIT 2 6-13 Amendment No.
ATTACHMENT 3 TO AEP:NRC:0659J FACILITY ORGANIZATION CHART FOR D.
C.
COOK UNITS I AND 2
e FICVRE 1. 7-5 FACILITYORCANIZATION lfCOISS41 ACTMTT COGRSIMATOR ASSISTART RIANT NANNXR
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QNCRVTXIN cvvsoHGIOAL XCCIIIN WQCAR SCC ITIN TDeufcs SCllSIII1 STAMSARSS SCCTRH ACCISSITING QNCRVISIN XCONITT SCCTRN CHOGCIL SCCIIDI Itfnet st XCCTION Sf lsict XCCTON NAOrfCMAHCC DMIOGXRING tferosl XCCTION DCSIGN SCC'I IDI
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In routine matters.
the Plant Rodlatkn Protectkn Supervtsor as headol the Rodlatlon ProtecUon Section reports directly to the Technkol Physkol Sctence Superhlendent.
In malters of rodktlon pftky determhatkn, lnterpretatlon or fmplementaUcn (based upon the Plonl Radlatkn Protection Supervisor's tudrtement) the Plont Rodlatlon Protection Supervftor moy report directly to the Plant tlanoger.