ML20246C849
| ML20246C849 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/30/1989 |
| From: | Shemanski P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20246C854 | List: |
| References | |
| GL-86-10, GL-88-12, NUDOCS 8907110165 | |
| Download: ML20246C849 (14) | |
Text
_
p UNITED STATES -
g NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D. C. 20555
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a COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237
_DRESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDf!ENT:TO PROVISIONAL OPERATING LICENSE Amendment No. 106 License No. DPR-19 3.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated February 22, 1989 complies with the standards and requirements of the Atomic tnergy Act of 1954, as amended (the Act), and the Comission'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.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health dnd safety of the public, and (ii) that such activities Will be conducted in ccirpliance with the Comission's regulations; D.
The issuance of this amendment will not' be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
8907110165 890630 PDR ADOCK 05000237 P
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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.H. of Provisional Operating License No. DPR-19 are hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, are hereay incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
H.
Commonwealth Edison Company shall innplement and maintain in effect all provisions of the approved fire projections program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SERs dated March 22, 1978 with supplements dated December 2,1980 and February 12, 1981; January 19,1983; July 17,1987; September 28, 1987; and January 5, l'989, subject to the following provisions:
The licensee may make changes to the approved fire protection program without prior approval of the Comission 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 to be iraplemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Q c.r u Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1989
ATTACHNENT TO LICENSE AMENDMENT NO. 106 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET N0. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by l
the captioned amendment number and contain marginal lines indicating the area of change.
l REMOVE INSERT iv iv 3/4.12-1 4
3/4.12-2 3/4.12-3 j
3/4.12-4 3/4.12-5 3/4.12-6 3/4.12-7 3/4.12-8 3/4.12-9 3/4.12-10 3/4.12-11 3/4.12-12 3/4.12-13 3/4.12-14 B 3/4.12-15 B 3/4.12-16 B 3/4.12-17 8 3/4.12-18 B 3/4.12-19 B 3/4.12-20 B 3/4.12-21 6-1 6-1 6-7 6-5 6-13 6-11 1
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DRESDEN 11 DPR-19 Amendment No. 82, 83, 106 (Table of Contents, Cont'd.)
.P.ag,e 3.9.C Diesel Fuel 3/4.9 - 4 3.9.D Diesel Generator Operability 3/4.9 - 4 I
Limiting Conditions for Operation Bases (3.9)
B 3/4.9 - 7
-Surveillance Requirement Bases (4.9)
B 3/4.9 - 8 3.10 Refueling 3/4.10- 1 1
3.10.A Refueling Interlocks 3/4.10- 1 3.10.B Core Monitoring 3/4.10- 1 3.10.C Fuel Storage Pool Water Level 3/4.10- 2 3.10.D Control Rod and Control Rod Drive Maintenance 3/4.10- 3 3.10.E Extended Core Maintenance 3/4.10- 4 3.10.F. Spent Fuel Cask Handling 3/4.10- 5 Limiting. Conditions for Operation Bases (3.10)
B 3/4.10- 8 Surveillance Requirement Bases (4.10)
B 3/4.10-11 3.11 High Energy Piping Integrity (outside containment) 3/4.11-1 Limiting Conditions for Operation Bases (3.11)
B 3/4.11-4 Surveillance Requirement Bases (4.11)
B 3/4.11-4 3.12 Fire Protection Systems - Sections 3.12.A through 3.12.H - Deleted per Generic Letters 86-10 and 88-12 (Amendment 106) 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Protection System 3/4.1 - 1 4.2 Protective Instrumentation 3/4.2 - 1 4.2.A Primary Containment Isolation Functions 3/4.2 - 1 4.2.B -Core and Contair. ment Cooling Systems --
Initiation and Control 3/4.2 - 1 4.2.C Control Rod Block Actuation 3/4.2 - 2
- 4. 2. 0 Refueling Floor Radiation Monitors 3/4.2 - 2 4.2.E Post Accident Instrumentation 3/4.2 - 3 4.2.F Radioactive Liquid Effluent Instrumentation 3/4.2 - 4 4.2.G Radioactive Gaseous Effluent Instrumentation 3/4.2 - 5 4.3-Reactivity Control 3/4.3 - 1 4.3.A Reactivity Limitations ~
3/4.3 - 1 4.3.B Control Rods 3/4.3 - 4 4.3.C Scram Insertion Times 3/4.3 -10 iv AMENDMENT NO.
106
y DRESDEN II DPR-19 Amendment No. 82,86,97,105,106 E
6.0 ' ADMINISTRATIVE CONTROLS
~ Organization, Review, Investigation and Audit 6.1 A.
Onsite and offsite organizations shall be established for the 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 the highest management levels through the Inte,ediste levels to and including.all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of' organization charts, functional descriptions of department responsibilities and l
relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organiza-tional Authority, Activity; 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 plant.
3.
'The Senior Vice President-Nuclear Operations shall have the 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.
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 operational pressures.
B.
DELETED C.
The shift manning for the statioc shall be as shown in Table 6.1.1.
The Operating Assistant Superintendent, Operating Engineers, Shift Engineers, and Shift Foremen shall have a Senior Operating License.
The Fuel Handling Foreman shall have a limited Senior Operating License.
Thc Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.
An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program.
6-1 AMENDMENT NO. 106
DRESDEN II DPR-19 Amendment No. 82,86,97,105,106 L
- 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
(5) Noncompliance with NRC requirements, or of internal procedures or instructions having nuclear safety significance.
(6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the On-sit? Review and Investigative Function.
~
(?) Reportable events under 10.CFR 50.73.
(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
(9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such changes.
(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations and AVP Quality Programs and Assessment.
(11) Review changes to the Fire Protection Program and implementing procedures.
b.
Station Audit Function The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR Operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
Either of the above, or designated Corporate Staff or Supervisor approved by AVP Quality Programs and Assessment shall approve the audit agenda and checklists, the findings and tha report of each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that safety-related functions are covered within the period designated below:
(1) Audit of the Conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
6-5 AMENDMENT N0. 106
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DRESDEN II DPR-19 Amendment No. 82,83,86,97,105,106 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(7) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Off-site Review and Investigative Function.
(8) Review of the Station Security Plan and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with 6.1.G.2.c.(1).
(9) Review of the Emergency Plan and station imp'lementing procedures and identification of recommended' changes.
(10) Review of reportable events and actions taken to prevent recurrence.
(11) Review 6f any unplanned on-site release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations and to the Superintendent of the Off-site Review and Investigative Functicn.
(12) Review of changes to the PCP and ODCM and major changes to the radwaste treatment systems.
(13) Review changes to the Fire Protection Program and implementing procedures.
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager (or designee) and shall make recommenda-tions in a timely manner in all areas of revies, investiga-1 tion, and quality control phases of plant maintenance, operation and administrative procedures relating to facility operations. The Technical Staff Supervisor shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Manager (or designee) shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility.
All such disagreements shall be reported immediately to the Vice President BWR Operations and the Superintendent of the Off-site Review and Investigative Function.
6-11 AMENDMENT NO. 106
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3 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRE5 DEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE ~
Amencuent flo,101 L-License No. DPR-25 1.
The Nuclear Regulatory Comission (the.Comission) has found that:
A.'
The application for ninendnent by the Coliimonwealth Edison Company (thelicensee)datedFebruary 22, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
Thereisreasonableassurance-(i)thattheactivitiesauthorized by tM s amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducteo in compliance with the Comission's regulations; D.
The issuance of this ariencuent 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 arnendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
..,~
.e.
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.G. of Facility Operating License No. DPR-25 are hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
G.
Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire projections program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SERs dated March 22, 1978 with supplements _ dated December 2,1980 and February 12, 1981; January 19, 1983; July 17, 1987; September 28, 1987; and January 5, 1
1989,-subject to the following provisions:
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 to be implemented within 60 days.
FOR THE NUCLEAP REGULATORY COMMISSION p
i
% c.r M Paul C. Shemanski, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT HO.101 FACILITY OPERATING LICENSE OPR-25 DOCKET NO. 50-249 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 indicating the area of change.
REMOVE INSERT iv iv 3/4.12-1 3/4.12-2 3/4.12-3 3/4.12-4 3/4.12-5 3/4.12-6 3/4.12-7 3/4.12-8 3/4.12-9 3/4.12-10 3/4.12-11 i
3/4.12-12 3/4.12-13 3/4.12-14 8 3/4.12-15 B 3/4.12-16 B 3/4.12-17 B 3/4.12-18 B 3/4.12-19 8 3/4.12-20 B 3/4.12-21 6-1 6-1 6-7 6-5 6-13 6-11
DRESDEN III DPR-25 Amendment No. 75, 77, 101 (Table of Contents, Cont'd.)
Page 3.9.C Diesel Fuel 3/4.9-4 3.9.D Diesel Generator Operability 3/4.9-4 Limiting Conditions for Operation Bases (3.9)
B 3/4.9-7 Surveillance Requirement Bases (4.9)
B 3/4.9-8 3.10 Refueling 3/4.10-1 3.10.A Refueling Interlocks 3/4.10-1 3.10.B Core Monitoring 3/4.10-1 3.10.C Fuel Storage Pool Water Level 3/4.10-2 3.10.0 Control Rod and Control Rod Drive Maintenance 3/4.10-3
^
3.10.E Extended Core Maintenance 3/4.10-4 3.10.F Spent Fuel Cask Handling 3/4.10-5 Limiting Conditions for Operation Bases (3.10)
B 3/4.30-S Surveillance Requirement Bases (4.10)
B 3/4.10-11 3.11 High Energy Piping Integrity (outside containment) 3/4.11-1 Limiting Conditions for Operation Bases (3.11)
B 3/4.11-4 Surveillance Requirement Bases (4.11)
B 3/4.11-4 3.12 Fire Protection Systems - Sections 3.12.A through 3.12.H -
Deleted per Generic Letters 86-10 and 88-12 (Amendment 101) 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Protection System 3/4.1-1 4.2 Protective Instrumentation 3/4.2-1 4.2.A Primary Containment Isolation Functions 3/4.2-1 4.2.B Core and Containment Cooling Systems --
Initiation and Control 3/4.2-1 4.2.C Control Rod Block Actuation 3/4.2-2 4.2.0 Refueling Floor Radiation Monitors 3/4.2-2 4.2.E Post Accident Instrumentation 3/4.2-3 4.2.F Radioactive Liquid Effluent Instrumentation 3/4.2-4 4.2.G R?dioactive Gaseous Effluent Instrumentation 3/4.2-5 4.3 Reactivity Control 3/4.3-1 4.3.A Reactivity Limitations 3/4.3-1 4.3.B Control Rods 3/4.3-4 4.3.C Scram Insertion Times 3/4.3-10 iv AMENDMENT NO.
101
1 j
1 i
DRESDEN III DPR-25 Amendment No. 75,79,92,100,101
- 6. 0 ADMINISTRATIVE CONTROLS 6.1 Organization, Review, Investigation and Audit A.
Onsite and offsite organizations shall be established for the 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 the highest management levels through the intermediate levels to and including all operating organization positions.
These relationship shall be documented and updated, as appropriate, in the form or organization charts, 4
functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activity; 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 plant.
3.
The Senior Vice President-Nuclear Operations shall have the 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.
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 opera-tional pressures.
B.
DELETED C.
The shift manning for the station shall be as shown in Table 6.1.1.
The Operating Assistant Superintendent, Operating Engineers, Shift Engineers, and Shift Foremen shall have a Senior Operating License.
The Fuel Handling Foreman shall have a limited Senior Operating License.
The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program.
An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program.
~
6-1 Amendment No. 101
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DRESDEN III DPR-25 Amendment No. 75,79,92,100,101
- 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
l (4) Proposed changes in Technical Specifications.or NRC operating licenses.
(5) Noncompliance with NRC requirements, or of inter-L nal procedures or instructions having nuclear safety significance.
(6) Significant operating abnormalities or deviations from normal and expected performance of plant-equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
(7) Reportable Events reported under 10 CFR 50.73.
(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
(9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such changes.
(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations and AVP Quality Program and Assessment.
(11) Review changes to the Fire Protection Program and implementing procedures.
b.
Station Audit Function The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of the Production Department.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
Either of the above, or designated Corporate Staff or Super-vision approved by AVP Quality Programs and Assessment shall approve the audit agenda and checklists, the findings and the report of each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that safety-related functions are covered within the period designated below.
6-5 Amendment No. 101
' l.
c.
.n DRESDEN Ill DPR-25 Amendment No. 75,77,79,92,100,101
- 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
(6) Review of facility operations to detect potential safety hazards.
(7) Performance of special reviews and investigations and reports thereon as requested by the Super-intendent of the Off-site Review and Investigative Function.
(8) Review the Station Security Plan and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with 6.1.G.2.c(1).
(9) Review the Emergency Plan and station implementing procedures and identification of recommended changes.
(10) Review of reportable events and actions taken to prevent recurrence.
(11)
Review of any unplanned on-site release of radioactive material to the environs including the preparation and fowarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations and to the Superintendent of the Off-site Review and Investigative Function.
(12)
Review of changes to the PCP and ODCM and major changes to the radwaste treatment systems.
(13)
Review changes to the Fire Protection Program and implementing procedures.
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager (or designee) and shall make recom-mendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation and administrative procedures relating to facility operations.
The Technical Staff Supervisor shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Manager (or designee)
I shall follow such recommendations or select a course of action that is more conservative regarding safe operation I
of the facility. All such disagreements shall be reported immediately to the Vice President BWR Operations and the Superintendent of the Off-site Review and Investigative l
Function.
l 6-11 Amendment No. 101 w_-
-