ML20078S861
| ML20078S861 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/22/1995 |
| From: | Stang J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078S865 | List: |
| References | |
| NUDOCS 9502270324 | |
| Download: ML20078S861 (12) | |
Text
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UNITED STATES
.p s-g NUCLEAR REGULATORY COMMISSION l
2 WASHINGTON, D.C. 30806 0001
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COMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 f
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.132 License No. DPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, i
1993, February 16, 1993, and January 27, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as 1
amended (the Act), and the Comission's rules and regulations set.
l forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act and the rules and regulations of the j
Comission; C.
There is reasonable assurance (i) that.the activities authorized i
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be j
conducted in compliance with the Comission's regulations-i 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable i
requirements have been satisfied.
i 2.
Accordingly, the license is amended by changes to the Technical Specifi-j cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows i
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9502270324 950222 DR ADOCK O 7
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Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 132, are hereby incorporated in the l
license. The licensee shall operate the facility in accordance with the Technical Specifications.
t 3.
This license amendment is effective as of the date of its issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION cW
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jihn F. Stang nior Project Manager i
Project Direc ate III-2 i
Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications i
Date of Issuance:
February 22, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO.132 FACILITY OPERATING LICENSE HO. DPR-19 DOCKET NO. 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 the captioned amendment number and contain marginal lines indicating the area of change.
t REMOVE INSERT 3.0-2 3.0-2 3.0-2a B 3.0-3 B 3.0-3 i
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Dresden II DPR-19 Amendment No.132 3.0 LIMITING CONDITION FOR OPERATION (cont'd).
hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in at least cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
t C. Specifications 3.0.A and 3.0.B are not applicable in refueling or cold shutdown.
D. Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,2, and 3 components shall be applicable as follows:
- 1. Inservice Inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Pan 50, Section 50.55a(g) and 50.55a(f),
respectively, except where specific written relief has been granted by the Commission pursuant to 10 CFR Part j
50, Section 50.55a(g)(6)(i) or 50.55a(f)(6)(i), respectively.
l 1
- 2. Surveillance intervals specified in Section XI of the ASME Boiler and
(
Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the
)
ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these i
Technical Specifications:
3.0-2
1 1
Dresden II DPR-19 Amandment No. 132 3.0 LIMITING CONDITION FOR OPERATION (cont'd).
I i
AsME Boiler and Pressure Vessel Required Frequencies l
Code and applicable Addenda for performing inservice
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terminology for insemce inspection inspection and testing and entine activit' n activitnes e
i Weekly At least once per 7 days Monthly.
At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually.
At least once per 366 days Biennially or every 2 years At least once per 731 days
- 3. The provisions of Specification 1.0.CC.a are applicable to the above required frequencies for performing inservice I
inspection and testing activities.
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- 4. Performance of the above inservice inspection and testing activitics shall be in addition to other specified Sur';eillance Requirements.
j
- 5. Nothing in the ASME Boiler and Pressure Vessel Code
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shall be construed to supersede the requirements of any Technical Specification.
- 6. The Inservice Inspection Program for piping identified in NRC Generic 12tter 88-01 shall be performed in I
accordance with the staff positions on schedule, methods, l
and personnel and sample expansion included in Generic 12tter 88-01 or in accordance with alternate measures approved by the NRC staff.
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Dresden II DPR-19 Amendment No.132 3.0 LIMITING CONDITION FOR OPERATION BASES 3.0. A.
This specification delineates the action to be taken for circumstances not directly provided for in the Limiting Condition for Operation statements and whose occurrence would violate the intent of the specincation.
3.0.B.
This specification delineates what additional conditions must be satisned to permit operation to continue, consistent with the Limiting Condition for Operation statements for power sources, when a normal or emergency power source is not operable. Power sources am denned as AC Auxiliary Electrical Systems as defined in Section 3.9.A.1, 3.9.A.2, and 3.9.A.3. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.
C The provisions of this specification permit the Limiting Condition for Operation Statements associated with individual systems, subsystems, tmins, components or devices to be consistent with the Limiting Condition for Operation statements of the associated electrical power source. It allows operation to be govemed by the time limits of action statements associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual action statements for each system, subsystem, train, component, or device that is determined to be inoperable solely because of the inoperability of its normal or emergency power source.
3.0.C N/A 3.0.D Specification 3.0.D establishes the requirement that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Commission.
This specification includes a clariGcation of the fmquencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarincation is provided to ensure consistency in surveillance intervals throughout the Technical Specificatioms and to remove any ambiguities relative to the frequencies for performing the reopired inservice inspection and testing activities.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
B 3.0-3
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- a UNITED STATES g
,y NUCLEAR REGULATORY COMMISSION
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t WASHINGTON, D.C. 20066 4 001
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COMONWEALTH.EDISDN. COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated July 29, 1992, as supplemented January 14, j
1993, February 16, 1993, and January 27, 1995, 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 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
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. B.
Technical Specifications The Technical _ Specifications contai'.ad in Appendix A, as revised through Amendment No.126, 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 NUC EAR REGULATORY COMMISSION
..)05 !.M U s, ohn F. Sta,, Senior Project Manager roject Di ectorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 22, 1995 l
ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO. DPR-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 3.0-2 3.0-2 3.0-2a B 3.0-3 B 3.0-3
^
Dresden III DPR-25 Amendment No.126 3.0 LIMITING CONDITION FOR OPERATION (cont'd).
r hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in at least cold shutdown within the following i
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C. Specifications 3.0.A and 3.0.B are not applicable in refueling or cold shutdown.
D. Surveillance Requirements for inservice inspection and testing of ASME Code Class 1,2, and 3 components shall be applicable as follows:
- 1. Inservice Inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class l
~ 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g) and 50.55a(f),
respectively, except where specific written relief has been granted by the l
Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i) or 50.55a(f)(6)(i), respectively.
i
- 2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
3.0-2
i Dresden III DPR-25 Amendment No. 126 3.0 LIMITING CONDITION FOR OPERATION (cont'd).
AsME Boiler and Pressure Vessel Required Frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection inspection and testing and tectine activitiet activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days e
Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days i
- 3. The provisions of Specification 1.0.CC.a am applicable to the above required frequencies for performing inservice inspection and testing activities.
- 4. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
- 5. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
- 6. The Inservice Inspection Program for piping identified in NRC Generic Lettet 88-01 shall be performed in accordance with the staff positions on schedule, methods, and personnel and sample expansion included in Generic Letter 88-01 or in accordance with attemate measures approved by the NRC staff.
3.0-2a
Dresden IB DPR-25 Amendment No.126 3.0.
LIMITING CONDITION FOR OPERATipN nASES 3.0.A.
This specification delineates the action to be taken for circumstances not directly pmvided for in the Limiting Condition for Operation statements and whose occurrence would violate the intent of the specification.
3.0.B.
This specification delineates what additional conditions must be satisfied to permit t
operation to continue, consistent with the Limiting Condition for Operation statements t
for power sources, when a normal or emergency power source is not operable. Power sources are defined as AC Auxilian Electrical Systems as defined in Section 3.9.A.1, 3.9.A.2, and 3.9.A.3. It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.
The provisions of this specification permit the Limiting Condition for Operation Statements associated with individual systems, subsystems, trains, components or devices to be consistent with the Limiting Condition for Operation statements of the associated electrical power source. It allows operation to be govemed by the tirne limits of action statements associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual action statements for each system, subsystem, train, component, or device that is determined to be inoperable solely because of the inoperability of its normal or emergency power source.
3.0.C.
N/A 3.0.D.
Specification 3.0.D establishes the requirement that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Presture Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Commission.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required i
inservice inspection and testing activities.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
B 3.0-3
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