ML20196D689
| ML20196D689 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/06/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20196D694 | List: |
| References | |
| TAC 69038, DPR-65-A-135 NUDOCS 8812090165 | |
| Download: ML20196D689 (5) | |
Text
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UNITE 3 8TATES
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e, NUCLEAR REGULATCRY COMMISSION r.
W ASHINGTON. D. C. 20606 NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 ANENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 I
License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The app (lication for amendment by Northeast Nuclear Energy Company, et al.
the licensee), dated August 2, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conforniity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can bt 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; 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 LFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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2.
Accord gly, 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-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendrwnt No.135, 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 issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h.
Mt Jo n F. Stolz, Director Project Directorate I-4 Division of Reactor Projects I/II l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Cate of Issuance: December 6, 1988 I
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ATTACHMENT T0 LICENSE _ AMENDMENT NO.135 FACILITY _0PERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following page of the Appendix A Technical Specifications with the enclosed prge. The revised page is identified 'oy amendment number a
and contains vertical lines indicating the areas of cht*ge. The corresponding overleaf page is provided to maintain document ".cFleter ass.
Remove inseyt 3/4 7-22 3/4 7-22 t
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'4 PLANT SYSTEMS 3/4.7.8 $NUBBERS LIMITING CONDITION FOR OPER ATION 3.7.8 All snubbers shall be OPERABLE. The only snubbers excJuded fror, the requirements are those installed on nonsafety-related systems and then only if their failure or fa!!ure of the system on which they are installed would have no adverse effect on any safety-related system.
APPLICABILITY MODE 51,2,3, and 4. MODES 3 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
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 perfoin an engineering evaluation per Speelfication 4.7.8.c on the attached component or decJare the attached sptem inoperable and follow the appropriate ACTION statement for the system.
SURVEILLANCE REQUIREMENT 5 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspetion program and the requirements of Specification 4.0.5.
a.
Visual Intpection Visual Inspections shall be performed in accordance reith the inspection schedule listed in Table 4.7-3.
b.
VisualInspection Acceptance Criteria Visual inspections shall verify: (1) that there are no visible indications of damage or impaired OPERA &!LITY and (2) attachments to the foundatler, or supporting structure are secure. Snubbers which appear inoperable as a resu!t of visual inspections may be determined OPERABLE for the purpose of estab!!shing the next visualinspection 4
Anterval, provided that:
1 1.
The cause of the rejection is clearly estab!!Omd and remedied i
for that particular snubber and for other snubbers irrespective of type that may be generically susesptiblel and The ' ffected snubber is functionally tested in the as 'emd 2.
a condition and determined OPERABLE per Speelficatlens 4.7J.d or 4.7.8.e, as applicable.'
l All anubbers connected to an inoperable common hydraulle fluid i
reservelt shall be counted as inoperable snubbers.
MILLSTONE - UNIT 2 3/4 7-21 h enhent Nos. dl, M, M. M, 118 SEP 1 G87 I
,N PLANT $YSTEMS
$URVEILL ANCE REQUIREMENTS (Continued) 1 c.
Snubber Tests At least once per eighteen (18) months during shutdown, a representative sample (10% of the total of each type of snubber, mechanical and hydraulle, except steam generator hydraitile snubbers in use in the plant) shall be tested either in place or in a bench test.
For each snubber that does not meet the test acceptance criteria of
$pecification 4.7.8.d or 4.7.8.e, as applicable, an additional 5% of l
that type of snubber shall be tested.
Testing shall continue until no additional looperable snubbers are found within a sample or until all snubbers have been tested. The representative sample selected for testing shallinclude the various configurations, and the range of slae and capacity of snubbers.
Snubbers identified as "Zspecla!!y Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.'
In addition to the regular sample,in locations where snubbers had f ailed the previous test due to operational or environmental condit!ons (excessive vibration extreme heat or humidity, etc.h, water hammer, high radiation, the snubbers currently installed in these locations shall be tested during the next test period. Test l
results of these snubbers may not be incluAd for the resampling. All replacement snubbers shall have been tested prior to installation.
All steam generator hydraulle snubbers shall be tested and refurbished every seven years or less in accordance with the i
preventative maintenance g.rogram,in lieu of the functional test requirements of this specification.
If any(snubber selected for testing either falls to lock-up or falls to move i.e., frotea in place), the cause will be evaluated and if caused l
by manufacturer design deficiency, all snubbers of the same design i
subject to the same defect shall be tested regardless of location or i
dlificulty of removal. This testing requirement shall be Independent of the requirements stated abeve for snubbers not meeting the test j
acceptance criterla.
For the snubber (s) found inoperable, an engineering eval tion shall
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be performed cn the components which are supported by the snutber(s). The purpose of thl engineering evaluation shall be to i
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- Permanent or other exemptions from functional testing for individual snubbers i
in these categories may be granted by the Commission only if a justifiable basis for exemption is presented.
MILLSTONE. - UNIT 2 3/4 7-22 Amendaeut Nos. M. M. M, /M 41%135 1
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