ML20236A675
| ML20236A675 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/19/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20236A678 | List: |
| References | |
| NPF-11-A-051 NUDOCS 8710230025 | |
| Download: ML20236A675 (4) | |
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- UNITED STATES 4
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
- [E.
-COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment.No. 51-
. License'No. NPF-11 1
1.
Th'e. Nuclear Regulatory Comission (the Comission or the NRC) has found -
that:
A.
The application for amendment filed by the Commonwealth Edison Company (the' licensee),datedJune 16,.1987, complies with the standards and requirements.of the Atomic Energy Act of 1954, as amended.(the Act), and l
the Commission's regulations set forth in 10 CFR Chapter I;
~l B.
The facility will operate'in conformity with the. application, the provisions of thelAct, and'.the regulations of the Comission; j
C. -
There is reasonable assurance: (1)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 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 1
the Comission's regulations and all applicable requirements have been l
satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifica-1 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 l
read as follows.
9 (2). Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A, as revised through
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Amendment No. 51, and the Environmental Protection Plan contained in
'l Appendix B, are hereby incorporated in the license. The licensee shall i
operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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3.
This amendment is effective as of date of issuance.-
FOR THE NUCLEAR REGULATORY COMMI SION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III,
'IV, V and Special Projects
Enclosure:
L Changes to the Technical.
Specifications-
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.Date of Issuance:.0ctober 19, 1987 1
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ENCLOSURE TO LICENSE AMENDMENT NO. 51-i
-3 FACILITY 0PERATING LICENSE NO.' NPF-11 L
DOCKET NO. 50-373 L
i Replace the following page of the Appendix "A" Technical-Specifications with I
'the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the' area of change.
. REMOVE INSERT' l
.3/4 7-28 3/4 7-28 l
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J PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
I c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that:
there are no visible indications of damage.or impaired OPERABILITY and (2) attachments to the foundation nr supporting structure are secure, and (3) fasteners for attachment j
of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections j
may be determined OPERABLE for the purpose of establishing the next i
visual inspection interval, provided that:
(1) the cause of the rejec-q tion is. clearly established and remedied for that particular snubber and for other snubbers irrespective of type on that system that may be generically susceptible; and (2) the.affected snubber is functionally i
tested in the as-found condition and determined OPERABLE per Specifica-tion 4.7.9f.
'All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
For those snubbers common to more than one system, the OPERABILITY of such snubbers shall-be considered in assessing the surveillance schedule for each of the related systems, i
d.
Transient Event Inspection s
An inspection shall be performed of all hydralic and mechanical snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation-of in place snubber piston setting; or (3) stroking the mechanical snubber through 1.ts full range of travel, e.
Functional Tests During the first refueling shutdown and at least once per 18 months
- thereafter during shutdown, a representative sample of-snubbers shall be tested using one of the following sample plans'.
The sample plan shall be selected prior to the test period and cannot be changed during the test period.
The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.9f., an additional 10%
of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or 2)
A representative sample of each type of snubber shall be func-tionally tested, in accordance with Figure 4.7-1.
"C" is the
- The second functional test surveillance shall be conducted 18 months from the commencement of power operation for cycle 2.
LA SALLE - UNIT 1 3/4 7-28 Amendment No. 51
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