ML20128K173
| ML20128K173 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/09/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Vermont Yankee |
| Shared Package | |
| ML20128K177 | List: |
| References | |
| DPR-28-A-089 NUDOCS 8507240056 | |
| Download: ML20128K173 (11) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION p,
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WASHINGTON, D. C. 20555
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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-28 1.
The Nuclear Regulatory Comissf,n (the Comission) has found that:
A.
The application for amendment by Vennont Yankee Nuclear Power Corporation (the licensee) dated May 20, 1983, as revised February 7,1984, and superseded October 22, 1984 and supplemented November 6,1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the B.
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 end.1gering 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-28 is hereby amended to read as follows:
8507240056 850709 ADOCK0500g1 PDR P
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89, 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 N CLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 9,1985 9
9 9
a
t ATTACHMENT TO LICENSE AMENDMENT NO. 89 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Revise the Technical Specifications as follows:
Remove Insert 110a 110a 110b 110b 110c 110c 110d 110e 110f 116 116 116a 116b 116c 125 125 125a
(
The revised areas are indicated by marginal lines.
1
i VYNPS I
3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS l
i I.
Shock Suppressors (Snubbers)
I.
Shock Suppressors (Snubbers) 1.
Except as noted in 3.6.I.2 and 3.6.I.3 below, 1.
Each snubber shall be demonstrated operable l
all required safety-related snubbers shall be by performance of the following inspection l
operable whenever its supported system is program.
required to be operable.
l a.
Visual Inspections l
2.
With one or more required 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 Visual inspections shall be performed in restore the snubber to operable status and accordance with the following schedule:
perform an engineering evaluation per Specification 4.6.I.Ib and c, on the No Inoperable supported component. In all cases, the Snubbers per Next Required required snubbers shall be made operable or Inspection period Inspection Intervals I
replaced prior to reactor startup.
O 18 months +25%
3.
If the requirements of 3.6.I.1 and 3.6.I.2 1
12 months 125%
j cannot be met, the supported system shall be 2
6 months 125%.
declared inoperable and the appropriate 3, 4 124 days 125%
action statement for that system shall be 5,6,7 62 days 125%
followed.
8 or more 31 days 125%
The snubbers may be categorized into two groups:
the accessible and those inaccessible during reactor operation.
Each group may bc inspected i
independently in accordance with the 1
above schedule. The inspection interval shall not be lengthened more than one step at a time.
Inaccessible snubbers are required to be inspected only if the j
period of time in which they become i
accessible is greater than 48 hcurs.
i Amendment No. Jk( 89 110a ii i
h VYNPS 1
3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIRENENTS l
b.
Visual Inspection Acceptance criteria i
Visual inspections shall verify (1) that there are no visible indications of damage or impaired operability, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures.
Snubbers which appear inoperable as a result of visual inspections may be determined operable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied 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 Specification 4.6.I.c, as applicable. When the fluid port of a hydraulic snubber is found to be
],
uncovered, the snubber shall be determined inoperable unless it can be i
determined operable via functional 1
testing for the purpose of establishing t
the next visual inspection interval.
The functional test, in this case, shall be started with the piston in the as-found condition, extending the piston rod in the tension mode direction.
110b Amendment No. 2A, 29, JHI 89 i
i
m VYNPS 3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS c.
Functional Tests 4
At least once per 18 months during shutdown, a representative sample of IDE of the snubbers in use in the plant shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of j
specification 4.6.I.1.d. an additional 10% of the snubbers shall be functionally tested until no more l
failures are found or until all snubbers i
have been functionally tested.
Snubbers of a rated capacity greater than the capability of the testing machine shall be functionally tested as follows:
(1) the lock up and bleed velocity of the snubber valve shall be j
verified by testing it on a cylinder that is within the capability of the testing machine, (2) the free stroke of the cylinder shall be checked, and (3) the pressure retaining capability of the cylinder shall be checked.
i 1
i i
i l
Amendment No. 89 Il0C l
VYNPS 3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS Snubbers identified as especially difficult to remove or in high radiation areas shall also be included in the representative sample.
In addition to the regular sample, snubbers which failed the previous
. functional test shall be retested during the next test period unless the root cause for the problem has been determined and corrective actions implemented. If a spara snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test period. Failure of these snubbers shall not entail functional testing of additional snubbers.
If any snubber selected for functional testing either fails to lock up or fails to move, i.e.,
frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency, all Amendment No. 89 110d
VYNPS 3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS generically susceptible snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, a documented engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).
The scope of the evaluation shall be based on engineering judgement and may be limited to a visual inspection of the supported component (s). The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service, d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
110e Amendment No. 89 T
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VYNpS 3.6 L1HITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREHENTS 1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is uithin the specified range in compression or tension. For snubbers speelfically i
required to not displace under continuous load, the ability of the snubber to withstand load without I
displacement shall be verf fled.
J.
Thermal Ilydraulle Stability J.
Thermal llydraulic Stability 1.
When the reactor mode switch is in RUN, the Operation in the natural circulation mode shall be reactor shall not intentionally be operated
" timed and recorded for special tests. Also, in a natural circulation mode, except as during special teste loop temperatures, vessel permitted in 3.6.J.2 helow, nor shall an idle asturation temperature (pressure), vessel top head recirculation pump he started with the temperature, and vessel bottom head temperature reac t or in a natural c i rculation mode, except shall be monitored and recorded.
as permit ted in 3.6.J. 2.
2.
For the purpose of performing special tests, operation in the natural circulation mode is pe rmi t ted.
For the purpose of recovering forced circulation operation during and af ter special, tests at natural circulation, startup of an idle recirculation pump is permitted if s The AT between the idle loop and vessel i
a.
saturation temperature is $500F.
t b.
The AT between 'the idle loop and an operating' loop is 3,500F.
Amendment No. 89 11Df c.
The AT between the vessel top head and the vessel bottom head is 11450F.
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3.6.I and 4.6.I SHOCK SUPPRESSORS (SWUBBERS)
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.
i The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
l Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by I
the number of inoperable snubbers found during an inspection. 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 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previcus schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may 1e generically susceptible, and verified by functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are (1) of a specific make or model, (2) of the same design, and (3) similarly located or exposed to the same environmental conditions such as temperature, s radiation, and vibration. These characteristics of the snubber installation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
When a snubber is found ino-tble, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in er to determine if any safety-related component or system has been adversely affected by the inoperability of the s..obber.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested once each operating cycle. Observed failures of these sample snubbers shall require functional testing of additional units.
3.6.J THERNAL HYDRAULIC STABILITY Not allowing operation in a natural circulation mode will provide additional stability margin, and it will provide protection against a reactivity insertion transient due to starting of an idle recirculation pump from the natural circulation mode.
Amendment No. 2A, g 89 125 1
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