ML20005F566
| ML20005F566 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/04/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005F567 | List: |
| References | |
| NUDOCS 9001160405 | |
| Download: ML20005F566 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
W ASHINGToN, D. C. 20655
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SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC. COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY.0F ANAHEIM. CALIFORNIA DOCKET-NO. 50 362 SAN ONOFRE NUCLEAR. GENERATING STATION.. UNIT.NO. 3 AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No.69 License Nu. NPF-15 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment to the license for San Onofre Nuclear Generating Station, Unit 3 the facility) filed by Southern' California Edison Company SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (licensees) dated July 26, 1989 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; 5.
.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 (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 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 Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.' NPF-15 is hereby anended to read as follows:
1 (2); Technical Specification The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 69, are hereby incorporated in the license. SCE shall operate the facility in accordoace with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
George)f Knighton irector I
Project Directorate V Division of Reactor Projects - III, l
IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to'the Technical Specifications Date of Issuance: December 4, 1989 L
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ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362
- Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page is identified by
-i amendment number and contain marginal lines indicating the area of change.
Also enclosed is the following overleaf page to the amended page.-
AMENDMENT PAGE-OVERLEAF PAGE 3/4 7-17 3/4 7-18 t
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PLANT SYSTEMS 3/4.7.6' SNUBBERS' LIMITING CONDITION FOR OPERATION-3.7.6 ~All snubbers shall be OPERABLE.
The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed, would-have no adverse effeet on any safety-related system.
APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems regliTred OPERABLE in those MODES),
ACTION:
1 With-one or more snubbers inoperable, 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 a
per Specification 4.7.6.g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement'for that system.
SURVEILLANCE REQUIREMENTS 4,7.6-Each snubber shall be demonstrated OPERABLE by performance of the 1
following augmented inservice inspection program.
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
- The first inservice visual inspection of snu',bers shall be performed after 4. months but within 10 months of commencing POWER OPERATION and shall include'all snubbers.
If less than two snubbers are found inoperable during the first inservice = visual inspection, the second
. inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection.
Otherwise, subsequent visual j
inspections shall be performed in accordance with the following schedule:
L No, Inoperable Snubbers Subsequent Visual
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.per Inspection Period Inspection Period *y 0
18 months 25%
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12 months 1 25%"
2 6 months 1 25%
3,4 124 days 25%
5,6,7 62 days i 25%
8 or more 31 days i 25%
- The inspection interval shall not be lengthened more than one step at a time.
- The provisions of Specification 4.0.2 are not applicable.
- 20 months 25% for inspections conducted during the Cycle 4 refueling outage.
SAN ON0FRE-UNIT 3 3/4 7-17 AMENDMENT NO. 69 l
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) j The snubbers may be categorized into two groups:
Those accessible and.those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
c.
. Visual Inspection Acceptance Criteria 1
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Visual-inspections shall~ verify (1):that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to (a) the component or pipe and (b) the snubber anchonge are secure.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERASLE for the pur-pose of establishing the next visual inspection interval, provided-that (1) the cause of the rejection is clearly established and re-medied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifi-cation 4.7.6.e or 4.7.6.f, as applicable.
However, when a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot.be determined OPERABLE via functional testing.for the purpose of establishing the next visual inspection i
interval.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall-be counted as inoperable snubbers.
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Functional Tests
- l At least once per refueling interval during shutdown, a representative l
' sample of at least 15% of the total of each type of snubber in use in
~ the plant shall be functionally tested either in place or in a bench test.
For each snubber of a type of that does not meet the functional test acceptance criteria of Specification 4.7.6.e or 4.7.6.f, an L
additional-15% of that type of snubber shall be functionally tested l
l; until no more failures are found or until all snubbers of that type f
have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
The first snubber away from each reactor vessel nozzle 1.
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Snubbers within 5 feet of heavy equipment (valve, pump, turbine motor,etc.)
3.
Snubbers within 10 feet of the discharge from safety relief valve.
" Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
SAN ON0FRE-UNIT 3 3/4 7-18 AMENDMENT NO.64 m -
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