ML20128D061
| ML20128D061 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/02/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20128D065 | List: |
| References | |
| NPF-49-A-071 NUDOCS 9212070130 | |
| Download: ML20128D061 (4) | |
Text
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y UNITEn 3TATEs NUCLEAR REGULATORY COMMISSION
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NORTHEAST NUCLEAR ENLilGY COMPANY. ET AL.
DOCKET NO. 50-423 HILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated May 1,1992, as clarified by letter dated June 23, 1992, complies with the standards and requircments-of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules vd regulations set forth in 10 CFR Chah I; B.
The facility will opei..a in conformity with the application., the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this ame dment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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; rnd E.
The issuance of this amendment is in accordance with 10 CFR Part 51 af the Counission's rc;ulations and all applicable requirements have been satisfied.
9212070130 921202 PDR ADOCK 05000423 P
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. 2.
Accordingly, the license is amended by changes to the Tech a.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Soecifisations The Technical Specifications contained in Appendix A, as revised through Amendment No. 71
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR RE LATORY COMMISSION Jo n F._Stolz, Dir tor P oject Directorate I-4 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 2, 1992
.4 ATTACHMENT TO LICENSE AMEND!i[NT NO. 71 FACILITY OPERATJNG LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised ie is identified by amendment number and contains vertical lines inoi; 61ng the areas of change.
fle m n Intert 3/4 7-22 3/4 7-22 4
x PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirements 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 s, stem.
APPIICABILITY:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
AC110N:
With one or more 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 4.7.109 on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REOUIREMENTS 4.7,10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
Insoection Tvoes As used in this specification, " type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Insoections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories -(inaccessible and accessible) may be inspected independently according to the schedule -
determined by Table 4.7-2.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7-2.
c.
Visual Insoection Acceptance Criteria Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired CPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of -
establishing the next visual inspection interval, provided that-(1) the cause of the rejection is clearly established and remedied for th?t particular snubber and for other snubbers irrespective of MILLSTONE - UNIT 3 3/4 7-22 Amendment No. JE, EZ,71 0093