ML20044E147
| ML20044E147 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/13/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044E148 | List: |
| References | |
| NUDOCS 9305240012 | |
| Download: ML20044E147 (17) | |
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NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET N0. 50-254 OVAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.14i License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated August 29, 1991, September 30, 1991, and October 2,1991, comply with the standards and requirements of i
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 applications, 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 eart 51 of the Commission's regulations and all applicable i
requirements have been satisfied.
t 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraphs 3.B. and 3.F of Facility Operating License No. DPR-29 are hereby amended to read as follows:
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9305240012 930513 PDR ADDCK 05000254 p
1
- B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 141, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
F.
Fire Protection Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980 and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a j
fire.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION NLt.
8v James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Pages 4 and 5 of License No. DPR-29*
Changes to the Technical Specifications Date of Issuance: May 13,1993 i
- pages 4 and 5 have been retyped and are attached, for convenience, for the composite license to reflect this change 3
! 3.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50 and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regelations and orders of the Commission now or hereafter in effect; and is sueject to the additional conditions specified or incorporated below:
A.
Maximum Power level Commonwealth Edison is authorized to operate s;ad-Cities Unit No. I at power levels not in excess of 2511 megawatts (thermal).
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Deleted per Amendment No.103, dated December 15, 1987.
D.
Eoualizer Valve Restriction i
The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions of 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
These plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Quad-Cities Nuclear Power Station Security Plan," with revisions submitted through July 15, 1992; l
" Quad-Cities Nuclear Power Station Security Personnel Training and i
Qualification Plan," with revisions submitted through July 15, 1992-and " Quad-Cities Nuclear Power Station Safeguards Contingency Plan,"
I with revisions submitted through July 15, 1992. Changes made in-accordance with 10 CFR 73.55, shall be implemented in accordance with the schedule set forth therein.
F.
Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved i
Amendment No. 141 I
i
- in the Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980 and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, I
subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those j
changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G.
Systems Intearity
't The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
{
1.
Provisions establishing preventive maintenance and periodic visual l
inspection requirements, and 2.
Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
H.
Deleted by incorporation into 3.E above, per Amendment No. 64 dated March 19, 1981.
I.
(OPEN)
J.
Iodine Monitorina The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentratior, in vital arms under accident conditions. This program shall include the follov 7 1.
Traic....g of personnel; 2.
Procedures for monitoring; and 3.
Provisions for maintenance.of sampling and analysis equipment.
K.
Deleted by Amendment No. 103 dated December 15, 1987.
Amendment No.141 a'%
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t ATTACHMENT TO LICENSE AMENDMENT NO. 141 1
FACILITY OPERATING LICENSE NO. DPR-29 I
DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages I
identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT j
iii iii iv iv i
Section 3.11/4.11
]
i Section 3.12/4.12 6.1-1 6.1-1
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QUAD CITIES DPR-29 TABLE OF CONTENTS (Cont'd)
J Page 3.7 Limiting Conditions for Operation Bases 3.7/4.7-21 i
4.7 Surveillance Requirements Bases 3.7/4.7-27
~
3.8/4.8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1
]
A.
Gaseous Effluents 3.8/4.8-1 l
B.
Liquid Effluents.
3.8/4.8-9 t
C.
Mechanical. Vacuum Pump 3.8/4.8-13 D.
Environmental Monitoring Program 3.8/4.8-13.
E.
Solid Radioactive Waste 3.8/4.8-17<
F.
Miscellaneous Radioactive Materials Sources 3.8/4.8 i H.
Control Room Emergency Filtration System 3.8/4.8-18 j
3.8/4.8 Limiting Conditions for Operation and Surveillance Req. Bases.
3.8/4.8 '
'3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9/4.9-1 A.
Normal and Emergency A-C Auxiliary Power 3.9/4.9-1 B.
Station Batteries 3.9/4.9-3 i
C.
Electric Power Availability 3.9/4.9-3a i
D.
Diesel Fuel 3.9/4.9-S E.
Diesel-Generator Operability 3.9/4.9-5 l
F.
Reactor Protection Bus Power Monitoring System 3.9/4.9-6 3.9 Limiting Conditions for Operation Bases 3.9/4;9-9 4.9' Surveillance Requirements Bases 3.9/4.9-11 i
i 3.10/4.10 REFUELING 3.10/4.10-1.
A.
Refueling Interlocks 3.10/4.10-1 i
B.
Core Monitoring
' 3.10/4.10-2..
4 C.
Fuel Storage Pool Water Level 3.10/4.10-3 D.
Control Rod and Control Rod Drive Maintenance 3.10/4.10-3 E.
Extended Core Maintenance 3.10/4.10-4 F.
Spent Fuel Cask. Handling 3.10/4.10.
3.10 Limiting Conditions for Operation Bases 3.10/4.10-7 4.10 Surveillance Requirements Bases-3.10/4.10-10
- 3.11/4.11.
HIGH ENERGY PIPING INTEGRITY - Deleted per Amendment No. 140 I
i
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i
.iii' Amendment No.-141-l
i QUAD CITIES DPR-29 TABLE OF CONTENTS (Cont'd) i 3.12/4.12 FIRE PROTECTION SYSTEMS - Deleted per Generic Letters 86-10 and 88-12 (Amendment No.141 ).
5.0 DESIGN FEATURES 5.0-1 6.0 ADMINISTRATIVE CONTROLS 6.1-1 6.1 Organization, Review, Investigation, and Audit 6.1-1 6.2 Procedures and Programs 6.2-1 6.3 Reportable Event Action 6.3-1 6.4 Action to be Taken in the Event a Safety Limit is Exceeded 6.4-1 6.5 Plant Operating Records 6.6-1 6.6 Reporting Requirements 6.6-1 6.7 Environmental Qualification 6.7-1
- 6. 8 Offsite Dose Calculation Manual (ODCM) 6.8-1 6.9 Process Control Program (PCP) 6.9-1 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6.10-1 6.11 Radiation Protection Program 6.11-1 6.12 High Radiation Area 6.12-1 1
i e
i i
iv Amendment No.141
QUAD-CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION, REVIEW, INVESTIGATION, AND AUDIT A.
Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of i
the nuclear power plant.
1.
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 organization charts, functional descrip-tions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities:
Section 6 Interdepartmental Relationships.
2.
The Station 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 Senior Vice President-Nuclear Operations shall have the corpo-3.
7 rate 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.
4.
The Individuals who train 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.
B.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.
The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
C.
The shift manning for the station shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent, Operating Engineer, Shift Engi-neers, and Shift Foremen shall have a Senior Operator's License.
The i
Fuel Handling Foreman has a limited Senior Operator's License.
The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.
The Maintenance Assistant Superintend-ent will be responsible for implementation of the Fire Protection Program.
w 1
t 6.1-1 Amendment No.141
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'o UNITED STATES g
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 License No. DPR-30
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Commonwealth Edison Company (the licensee) dated August 29, 1991, September 30, 1991, and October 2, 1991, comply 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 applications, 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 sue.h 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 c
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 paragraphs 3.B. and 3.F of Facility Operating License No. DPR-30 are hereby amended to read as follows:
1 h
B.
Technical Specifications i
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
F.
Fire Protection Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in.the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980 and February 12, 1981; December 30, 1982; December 1,1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n2 James E. Dyer, Director
.i Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation F
Attachment:
Pages 4, 5, and 6 of License No. DPR-30*
Changes to the Technical Specifications i
Date of' Issuance: May 13, 1993
- pages 4, 5, and 6 have been retyped and are attached, for convenience, for the composite license to reflect this change r
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1
' 3.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
f Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50 and Section 70.32 of Part 70; is subject.to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A.
Maximum Power level Commonwealth Edison is authorized to operate Quad-Cities Unit No. 2 at power levels not in excess of 2511 megawatts (thermal).
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C.
Deleted per Amendment No. 104, dated June 17, 1988.
D.
Eoualizer Valve Restriction The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions of 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
These plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Quad-Cities Nuclear Power Station Security Plan," with revisions submitted through July 15, 1992;
" Quad-Cities Nuclear Power Station Security Personnel Training and Qualification Plan," with revisions submitted through July 15, 1992; and " Quad-Cities Nuclear Power Station Safeguards Contingency Plan,"
with revisions submitted through July 15, 1992. Changes made in accordance with 10 CFR 73.55, shall be implemented in accordance with the schedule set forth therein.
r F.
Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved Amendment No.136 t
in the Safety Evaluation Reports dated July 27, 1979 with supplements dated November 5, 1980 and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commissi.'n only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G.
Deleted by incorporation into 3.E above, per Amendment No. 58 dated March 19, 1981.
H.
Systems Inteority The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual i
inspection requirements, and 2.
Leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
I.
Iodine Monitorina The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include 4
the following:
'~
1.
Training of personnel; f
2.
Procedures for monitoring; and 3.
Provisions for maintenance of sampling and analysis equipment.
J.
Deleted K.
Post-Accident Samolina A program will be established, implemented and maintained which will ensure the capability to obtain and analyze reactor coolant, r
Amendment No. 136 i
- radioactive iodines and particulates in plant chimney effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
1.
Training of personnel, 2.
Procedures for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
4.
This license is effective as of the date of issuance, and shall expire at midnight, December 14, 2012.
FOR THE ATOMIC ENERGY COMMISSION Original signed by:
A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing
Enclosures:
Appendices A and B -- Technical Specifications Date of Issuance: December 14, 1972 i
i Amendment No. 136-i l
- ~..
l
.l
.i ATTACHMENT TO LICENSE AMENDMENT NO.136 FACILITY OPERATING LICENSE NO. DPR-30 i
DOCKET NO. 50-265 l
I Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines j
indicating the area of change.
i REMOVE INSERT I
iii 111 i
i iv iv l,
Section 3.11/4.11 Section 3.12/4.12 i
6.1-1 6.1-1
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i 5
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- - -.. - - ~ - ~.. - -
QUAD CITIES DPR-30 TABLE OF CONTENTS (Cont'd)
Page 1
3.8/4.8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1 A.
Gaseous Effluents 3.8/4.8-1 B.
Liquid Effluents 3.8/4.8-6a C.
Mechanical Vacuum Pump 3.8/4.8-9 D.
Environmental Monitoring Program 3.8/4.8-10 E.
Solid Radioactive Haste 3.8/4.8-13 F.
Miscellaneous Radioactive Materials Sources 3.8/4.8-14 H.
Control Room Emergency Filtration System 3.8/4.8-14a 3.8/4.8 Limiting Conditions for Operation and Surveillance Req. Bases 3.8/4.8-15 3.9/4.9 AUXILIARY ELECTRICAL SYSTEMS 3.9/4.9-1 A.
Normal and Emergency A-C Auxiliary Power 3.9/4.9-1 B.
Station Batteries 3.9/4.9-3 C.
Electric Power Availability 3.9/4.9-4 D.
Diesel Fuel 3.9/4.9-5 E.
Diesel-Generator Operability
- 3. 9/4. 9-6 F.
Reactor Protection Bus Power Monitoring System
- 3. 9/4. 9-7 3.9 Limiting Conditions for Operation Bases
- 3. 9 /4. 9-9 4.9 Surveillance Requirements Bases 3.9/4.9-11 3.10/4.10 REFUELING 3.10/4.10-1 A.
Refueling Interlocks 3.10/4.10-1 B.
Core Monitoring 3.10/4.10-2
~
C.
Fuel Storage Pool Water Level 3.10/4.10-2 D.
Control Rod and Control Rod Drive Maintenance 3.10/4.10-2 E.
Extended Core Maintenance 3.10/4.10-3 F.
Spent Fuel Cask Handling 3.10/4.10-3 3.10 Limiting Conditions for Operation Bases 3.10/4.10-4 4.10 Surveillance Requirements Bases 3.10/4.10-6 3.11/4.11 HIGH ENERGY PIPING INTEGRITY -
Deleted per Amendment No.136.
l 3.12/4.12 FIRE PROTECTION SYSTEMS - Deleted per Generic Letters 86-10 and 88-12 (Amendment No.136 ).
l t
111 Amendment No.136
QUAD CITIES DPR-30
+
l TABLE OF CONTENTS (Cont'd)
I Page 1
5.0 DESIGN FEATURES 5.0-1 j
6.0 ADMINISTRATIVE CONTROLS 6.1-1 l
6.1 Organization, Review, Investigation, and Audit 6.1-1 6.2 Procedures and Programs 6.2-1 6.3 Reportable Event Action 6.3-1 6.4 Action to be Taken in the Event a Safety Limit is Exceeded 6.4-1 6.5 Plant Operating Records 6.5-1 6.6 Reporting Requirements 6.6-1 6.7 Environmental Qualification 6.7-1 6.8 Offsite Dose Calculation Manual (ODCM) 6.8-1 6.9 Process Control Program (PCP) 6.9-1 6.10 Major Changes to Radioactive Haste Treatment Systems (Liquid, Gaseous, Solid) 6.10-1 6.11 Radiation Protection Program 6.11-1 6.12 High Radiation Area 6.12-1 t:
t i
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L h
iv Amendment No. 136 i
i I
QUAD CITIES DPR-30
+
6.0 ADMIN!STRATfVE CONTROLS 6.1 ORGANIZATION, REVIEH, INVESTIGATION, AND AUDIT A.
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.
1.
Lines of authority, responsibility, and communication shall be established and defined for tha highest management levels through intermediate levels to and including all operating l
organization positions.
These relationships shall be i
documented and updated, as appropriate, in the form of i
organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities:
Section 6 Interdepartmental Relationships.
2.
The Station 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.
3.
The Senior Vice President-Nuclear Operations shall have the j
corporate responsibility for overall plant nuclear safety and i
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.
4.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall t
have sufficient organizational freedom to ensure their independence from operating pressures.
B.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., licensed Senior Operators, licensed Operators, health physics personnel, equipment operators, and key maintenance personnel.
l The amount of overtime worked by Unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).
C.
The shift manning for the station shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent, Operating Engineer, Shift Engineers, and Shift Foremen shall have a senior operator's license.
The fuel Handling Foreman has a limited Senior Operator's License.
The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.
The Maintenance Assistant Superintendent will be responsible for implementation of the Fire Protection Program.
6.1-1 Amendment No. 136