ML20034B674
| ML20034B674 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/24/1990 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034B675 | List: |
| References | |
| NUDOCS 9004300177 | |
| Download: ML20034B674 (8) | |
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. UNITED STATES l'
c NUCLE AR REGULATORY COMMISSION WASHilv0708d, D. C. 70666
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373
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LASALLE COUNTY STATION, UNIT 1 j
i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 l
License No. NPF-11 f
i' 1.
The Nuclear Regulatory Comission (the Commission or De NRC) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated Septenber 9,1988 complies with the standards and requirements of the Atomic Energy Act of 1954 as amended (the Act), and the Comission's regulations set forth In 10 CFR Chapter It j
B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the regulations of the Comission;
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2 C.
There is reasonable assurance: (1) 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 set forth in 10 CFR 4
Chapter I-D.
The issuance of this amendment will not be inimical to the common
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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 j
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-l tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No NPF-11 is hereby amended to read as follows:
i (2) Technical Specifications and Environmental Protection Plan l
The Technical Specifications contained in Appendix A, as revis " through Amendment No.
, and the Environmental Protection Plan conta, ed in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and j
l-the Environmental Protection Plan, i
l 9004300177 900424 2
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This amendment is effective upon date of issuance.
t FOR THE NUCLEAR REGULATORY COMMISSION l
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Richard F. Dudley, Actin Director Project Directorate III-Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation.
Enclosure:
Changes to the Technical Specifications Date of issuance:
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1 ENCLOSURE TO LICENSE AMENDMENT N0. 73 FACILITY OPERATING LICENSE N0. NPF-11 DOCKET NO. 50-373 Replace the fc110 wing pages of the Appendix 'A' Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and l
contain a vertical line indicating the area of change.
i REMOVE INSERT l
3/4 7-27 3/4 7-27 i
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PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
l APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
ACTION:
With one or more snubbers inoperable, on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.99 on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections Snubbers are categorized as inaccessible or acceE51ble during reactor operation.
Each of these groups (inaccet.sible and accessible) may be inspected independently according to the schedule below.
The first inservice visual inspection of each type of snubber shall be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all hydraulic and mechanical snubbers.
If all snubbers of each type on any system are found OPERABLE during the first inserv-ice visual inspection, the second inservice visual inspection of that system shall be performed at the first refueling outage.
Otherwise l
subsequent visual inspections of a given system shall be performed In
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I accordance with the following schedule:
l No. Inoperable Snubbers of Each Type Subsequent Visual On Any System per Inspection Period Inspection Period *#
0 18 months - 50% + 25%
1 12 months i 25%
2 6 months i 25%
l 3,4 124 days i 25%
5,6,7 62 days i 25%
8 or more 31 days 1 25%
- The inspection interval for each type of snubber on a given system shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be lengthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found on that system.
- The provisions of Specification 4.0.2 are not applicable.
LA SALLE - UNIT 1 3/4 7-27 Amendment No. 73
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NUCLE AR REGULATORY COMMIS$10N j
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1 COMMONWEALTH EDIS0N COMPANY j
DOCKET NO. 50 374
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LASALLE COUNTY STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.57 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
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A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated Septent>er 9,1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i)thattheactivitiesauthorizedby 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 set forth in 10 CFR Chapter I; 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part $1 of the Comission's regulations and all applicable requirements have been j
satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph t
2.C.(2) of the Facility Operating License No MPF-18 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall o>erate the facility in accordance with the Technical Specifications and l
tie Environmental Protection Plan.
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. 3.
This amendment is effective upon date of issuance.
FOR THE MUCLEAR REGULATORY COMMIS$10N l
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i Richard F. Dudley, Actin Director i
Project Directorate III.
Division.of Reactor Projects - !!!,
IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
i Changes to the Technical Specifications Date of Issuance:
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ENCL 05tl}F.TOLICENSEAMENDMENTNO.57 FACILITY OPERATING LICENSE NO. NPF-18 i
DOCKET M0. 50 374 j
i Replace the following pages of the Appendix 'A' Technical Specifications with the enclosed pages. The revised pages are identified by amendment nunber and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 7-28 3/4 7-28 l
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1 1
i 1
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l PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All hydraulic and mechanical snubbers shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.
i ACTION:
With one or more snubbers inoperable, on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Inspection Types j
As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
I b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor i
operation.
Each of these groups (inaccessible and accessible) may be inspected independently according to the schedule below.- The first inservice visual inspection of each type of snubber shall be performed af ter 4 months but within 10 months of commencing POWER OPERATION and shall include all hydraulic and mechanical snubbers.
If all snubbers of each type on any system are found OPERABLE during the first inserv-ice visual inspection, the second inservice visual inspection of that system shall be performed at the first refueling outage.
Otherwise, subsequent visual inspections of a given system shall be performed in accordance with the following schedule:
No. Inoperable Snubbers of Each lype Sub equent Visual On Any System per Inspection Period Insection Period *#
0 18 months - 50% + 25%
1 12 months i 25%
2 6 months i 25%
3,4 124 days i 25%
l 5,6,7 62 days i 25%
8 or more 31 days i 25%
l
- The inspection interval for each type of snubber on a given system shall not be lengthened more than one step at a time unless a generic problem has been identified and corrected; in that event the inspection interval may be l
1engthened one step the first time and two steps thereafter if no inoperable snubbers of that type are found on that system.
- The provisions of Specification 4.0.2 are not applicable.
LASALLE - UNIT 2 3/4 7-28 Amendment No. 57
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