ML17279A220
| ML17279A220 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 04/21/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A221 | List: |
| References | |
| TAC-64217, NUDOCS 8704270102 | |
| Download: ML17279A220 (14) | |
Text
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+y*y4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASIIINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397
'PPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No.
NPF-21 1.
The Nuclear Regulatory CoImission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated December 12, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been 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 2.C.(2) of the Facility Operating License No. NPF-21 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendmeht No. 40, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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t PDR ADOCK 05000397 P
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY CONYiISSION
Enclosure:
Changes to the Technical Specifications 4f
- George,
. Knighton, irector Project Directorate V
Division of Reactor Projects-III/IV/V and
,Special Projects Date of Issuance:
April 21, 1987
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A
April 21, 1987 FNCLOSURE TO LICENSE AMENDMENT NO.
4O FACILITY OPERATING LICENSE NO.
NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE 3/4 7-10 3/4 7-11 B3/4 7-2 INSERT 3/4 7-10 3/4'-11 83/4 7-2 B3/4 7-2a
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40 PLANT SYSTEMS 3/4'. 7.4 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.4 All hydraulic and mechanical snubbers shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
OPERATIONAL CONDITIONS 4
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E y <<
R E
E OPERABLE E tt OPERATEOEAL CONDITIONS¹.
ACTION:
Mith one or more required 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 4.7.4g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE RE UIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
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As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Ins ections Snubbers are categorized as inaccessible or accessible during reactor 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
-after 4 months but within 10 months of commencing POMER OPERATION and shall include all hydraulic and mechanical snubbers.
If all snubbers of each type on any system are found OPERABLE during the first.
inservice 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:
¹Unless the removal of snubber(s) for maintenance or testing is justified by engineering analysis.
MASHINGTON NUCLEAR UNIT 2 3/4 7-10 Amendment No.
40
l I
PLANT SYSTEMS SURt/EILLANCE RE UIREMENTS Continued No. Inoperable Snubbers of Each Type on Any System er Ins ection Period 1
2 3,4 5,6,7 8 or more c.
Visual Ins ection Acce tance Criteria Subsequent Visual Ins ection Period* ¹ 18 months,
+25
, -50 12 months
+ 25K 6 months
+ 25K 124 days
+ 25K 62 days
+ 25K 31 days
+ 25K Visual inspections shall verify that: (1) there are no visible indi-cations of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection 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 tested in the as-found condition and determined OPERABLE per Specification 4.7.4f.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubber s.
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.
h d.
Transient Event Ins ection An inspection shall be performed of all hydraulic 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 its full range of travel.
"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.
¹The provisions of Specification 4.0.2 are not applicable.
MASHINGTON NUCLEAR - UNIT 2 3/4 7-11 Amendment No.
4O
g.
~0 PLANT SYSTEMS BASPS 3/4.7.4 SNUBBERS I
All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program 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 effect on any safety-related system.
Our-ing shutdown, snubbers which are redundant per engineering analysis can be removed for maintenance and/or testing and are excluded from the operability requirements'nubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of
'the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber loca-tion and size and of system affected shall be available at the plant in accord-ance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Operations Committee, The deter-mination shall. be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e. g., temperature, atmos-
- phere, location, etc.),
and the recommendations of Regulatory Guides 8.8 and
- 8. 10.
The addition or deletion of any hydraulic or mechanical. snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to each safety-related system.
Therefore the required inspection interval varies inversely with the observed snubber failures on a given system and is determined by the number of inoperable snubbers found during an inspection.
In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an assumed initiating event.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed, (nominal time less 25K) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
The acceptance criteria are.to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
MASHINGTON NUCLEAR - UNIT 2 B 3/4 7-2 Amendment No. 40
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PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS (Continued)
To provide assurance of snubber functional reliability, one of three functional testing methods are used with the stated acceptance criteria:
1.
Functionally test lOX of a type of snubber with an additional 10K tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or MASHINGTON NUCLEAR UNIT 2 8 3/4 7-2a Amendment No. 4o