ML20034A254
| ML20034A254 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/13/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034A255 | List: |
| References | |
| NUDOCS 9004200574 | |
| Download: ML20034A254 (5) | |
Text
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[# %*'g, UNITED STATES p
NUCLEAR REGULATORY COMMISMCrN h,.. }l 2
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I y1RGINIA ELECTRIC AND POWER COMPAfg DOC KET NO. 50-280
$URRY POWER STATION, UNIT P:0. 1 AMENDMENT TO FACILITY OPERATItC LICENSE Arwnonent No.139 License flo. DPR-32 1.
The fluelear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by Virginia Electric and Power Company (the licensee) dated Janaury 8,1990, coglies with the standarcs and requirennts of the Atomic Energy Act of 1964, as anended (the Act) and the Commission's rules and 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 rules and regulations of the Comi ssion; 8
i C.
There is reasonable assurance (i) that the activities authorized l
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; C.
The issuance of this amencarent 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 anendnent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
l I.
Accordingly, the license is amnded by changes to the Technical Specifications as indicated in the attachment to this license l
arnendnent, and paragraph 3.B of Facility Operating License ~
No. DPR-32 is hereby anended to read as follows:
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(B)
Technical Specifications The Technical Specifications containeo in Appendix A.
as revised through Amendnent No.139, are hereby incorporated in the license.
The licens's shall operate the facility in accorcance with the Technical Sp eci ficati on s.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NVCLEAR REGULATORY COMMISSION F
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--A&'
herdert N. Berkow, Director
,19 Projkct Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Atta chment:
Changes to the Technical Speci fica tions Date of 1ssuance:
April 13, 1990 1
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" ATTACHMENT TO L ICENSE AMEN 0 MENT.i l
AHENDMDIT KC.
139 ' FACILITY ' OPERATING l iCENSE NO. OPR-32:
.c DOCKET NO. E0-280-i
- r Revise. Apperidix ' A as follows:
. t Pereve Pages Insert Pc.tes -
TS 4.17 2.
'T3 4.17-2.
TS 4.17-3 TS 4.17 !
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l TS 4.17 2 i
j No, inoperable Snubbers
' Subsequent Visual Per insoection Period -
_lnsoection Period 1
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O 18 months 2 25%
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12 months 25% #
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6 months 25%
3, 4 124 days 25%
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5,6,7 62 days 25%
8 or more 31 days 25%
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2.
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.
I B.
Visual intasetion Acceotance Criteria 1.
Visual inspections shall verify:
a.
That there are no visible indications of damage or impaired operability, b.
Attachments to the foundation or supporting structure are secure, and l
c.
In those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
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l; The inspection interval shall not be lengthened more than one step at a time, l
The current inspection period for Unit 1 may be extended to the Cycle 10 refueling outage but shall expire no later than December 31, 1990 Amendment No. U9 -
t TS 4.17 3
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2.
Snubbers which appear inoperable as a result of visual inspections may be determined operable for the purpose of estab!ishing the next visual inspection interval, providing that the
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cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that inay be generically susceptible and the affected snubber is functionally tested in the as found condition and determined operable per Specification 4.17 D or 4.17 E, as applicable.
3.
When the 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 interval. All snubbers connected to an inoperable common hydraulic fluid
.l reservoir shall be counted as inoperable snubbers.
J C.
Functional Tests i
1.
At least once per 18 months during shutdown, a representative sample of 10% of the total of each type of snubber used in the plant shall be functionally tested either in place or in a bench test.#
2.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. This representative sample shall not, to the extent practicable, include those snubbers tested in a previous representative sample, 3.
At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:
a.
The first snubber away from each reactor vessel nozzle b.
Snubbers within 6 feet of heavy equipment (valve, pump, turbine, motor, etc.)
The Unit 1 function inspection period can be extended until the Cycle 10 refueling outage but shall expire no later then December 31, 1990.
Amendnient No. -139