ML17328A608
| ML17328A608 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/09/1990 |
| From: | Thoma J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A609 | List: |
| References | |
| NUDOCS 9003230182 | |
| Download: ML17328A608 (16) | |
Text
t UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
132 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 6, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph
- 2. C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 132
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
5'003230l82 900309 PDR ADOCK 050003l5 P
-2" 3.
This license amendment is effective as of.the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of-Issuance:
March 9,:.1990
'ohn 0.
Thoma, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 5 Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
132 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 6-1 through 6-4 INSERT 6-1 through 6-4
6.0 ADMINISTRATIVECONTROLS 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 ONSITE AND OFFSITE ORGANIZATIONS 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include tne positions for activities affecting the safety of the nuclear power plant.
a.
b.
.Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the, FSAR and updated in accordance with 10 CFR 50.71(e).
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
The Vice President
- Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
"The Xvdividuals who crain the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager;
- however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
FACILITY STAFF 6 2.2 The Zacility organization shall he sub)ect to the. following:
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 control room shutdown and D. C.
COOK - UNIT 1 licensed Operators shall, be present in the during reactor start-up, scheduled reactor during recovery from reactor trips.
6-3.
Amendment No. 77, 13~
AD~fINISTRATIVE CONTROLS FACILITY STAFF Continued d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
ALL CORE ALTERATIONS 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 respon ibilities during this operation, f.
A site Fire Brigade of at least 5 members shall be maintained nnsite 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).
h.
The Shift Supervisor, Assistant Shift Supervisor, and Unit Supervisor shall hold a senior reactor operator licensees D.
C.
COOK - UNIT 1 6-2 Amendment No. 07, 132
TABLE 6.2-1
,Nl¹NUl4 SHIFT CREW COY2'OSITIONÃ LICENSE CATEGORY 1, 2, 3
a 4
5 a
6 APPLICABLE NODES SOL
] **
NON-Licensed Shift Technical Advisor 1**
None Required "Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS after the initial fuel loading.
HShift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum recuirements of Table 6.2-1.
- Shared with D. C.
Cook Unit 2.
D. C.
COOK - '::::":" 1 6-3 Amendment No. If/,88,132~
THIS PAGE INTENTIONALLYLEFT BLANK D. C.
COOK UNIT 1 6-,4 Amendment No.
g9, N, 132
~
~g8 RfQy~
~C p0
~
Q
~
A.
++*++
t UNITED STATES t
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POMER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No.
DPR-74 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 6, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph
- 2. C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
117
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 9, 1990 John 0.
Thoma, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
117 TO FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REHOYE 6-1 through 6-4 INSERT 6-1 through 6-4
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 04SITE AND OFFSITE ORGANIZATIONS 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management; respectively.
,The onsite and offsite organizations shall include the positions for activities affecting, the safety of the nuclear power plant.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels,to and including all operating organization positions, These relationships shall be documented and,updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President
- Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
The individuals who train the operating staff'nd those who carry out health physics and quality assurance functions may report to the appropriate onsite manager;
- however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
FACILITY STAFF 6.2.2 The Facility organization shall be subject to the following:
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 control room shutdown and D.
C.
COOK - UNIT 2 licensed Operators shall be present in the during reactor start-up, scheduled reactor during recovery, from reactor trips.
6-1 Amendment No. gg, 117
AD.fINISTRATIVE CONTROLS FACILITY STAFF Continued d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
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.
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.
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).
The Shift Supervisor, Assistant Shift Supervisor, and Unit Supervisor shall hold a senior reactor operator license.
D.
C.
COOK - UNIT 2 6-2 Amendment No, 7$,
117
TABLE 6.2-1 MZNZMiJM SHIFT CREW COMPOSITIONS LICENSE CAT"GORY 1, 2, 3
6 4
5 a
6 APPLICABLE MODES SOL 1*
Non-Licensed Shift Technical Advisor None Required
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS 4/Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
- Shared with D. C. Cook Unit l.
D C.
COOK UNIT 2 Amendment No. 88~1 "7
THIS PAGE INTENTIONALLYLEFT BLANK D. C.
COOK - UNIT 2 Amendment 'No. gg, 117