ML20116N368
| ML20116N368 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/16/1992 |
| From: | Stolz F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116N373 | List: |
| References | |
| NUDOCS 9211230365 | |
| Download: ML20116N368 (5) | |
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NORTHEAST NELEAR ENERGY CaliPRif THE CONNECTICUT LIGHT AND POWER CQMPANY IHL1fjTERN MASSACHUSETTS ELECTRJLCOMPANY DOCKET N0. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No.165 License No. OPR-65 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 August 17, 1992, as supplemented by letter dated October 30, 1992, 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; B.
The facility nill operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) 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 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; 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, l
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9211230365 921116 DR ADOCK 05000336 PDR
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. 2.
Accordingly, the license is amended t,y changes to the Technical Specifications as indicated in the attaihment to this license amendment, and paragraph 2.C.(?) of facility Operating License No. DPR-05 is hereby amended to read as follows:
(2) lithnical Specificttiqui The Technical Specifications contained in Appendix A, as revised through Amendment No.165, 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.
F R THE NUCLEAR REGV, TORY COMMISSION f-
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4 Joh iT. Stolz, Direct t
Pr ject Directorate 1-4
'visirn of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 16, 1992 l
i ATTACHMENT TO LICENSE AMEN 0 MENT NO.165 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the following pages of the Appendix A Technical Specifications with-the enclosed pages.
The revised pages are identified by amendment number ar.d contain vertical lines indicating the areas of change.
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CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERAT10f4 3.6.1.6 The structural integrity of the containment shall be maintained at a 1evel consistent with the acceptance criteria in Specification 4.6.1.6.
j 8PPLICABILITY:
MODES 1, 2, 3 and 4.
i ACIl0N:
With the structural integrity of the containment not e.onforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE0VIREMENTS 4.6.1.6.1 Containment Tendons The containment tendons' structural integrity shall be demonstrated at the end of one,* three and five years following the initial containment structural integrity test and at five year intervals thereafter.
The tendons' structural integrity shall be demonstrated by:
a.
Determining that a representative sample of at least 21 tendons (6 dome, 5 vertical, and 10 hoop) each have a lift off force of between 7030 (minimum) and 8940 (maximum) pounds per tendon wire.
If the lift off force of any one tendon in the total sample population is out of the predicted bounds (less than minimum or greater than maximum), an adjacent tendon on each side of the defective tendon shall also be checked for lif t off force.
If both of these tendons are found acceptable, the surveillance program may.
proceed considering the single deficiency as unique and acceptable.
More than one defective tendon out of the original sample population is evidence of abnormal degradation of the containment structure.
Unless there is evidence of abnormal degradation of the containment structure during the first three tests of the tendons, the number of tendons checked for lift off force during subsequent tests may be reduced to a representative random sample of at least 9 tendons (3 dome, 3 vertical and 3 hoop).
- May be extended to no later than midnight, July 15, 1976.
MILLSTONE - UNIT 2 3/4 6-10 Amendment No.165 0070
_.___>__m CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) b.
Removing one wire from a dome, a vertical and a hoop tendon checked for lift off force pursuant to Specification 4.6.1.6.1.a and determir.ing that over the entire length of the removed wire that:
1.
The tendon wires are free of enrrosion.
2.
There are no changes in physical appearance of the sheathing filler grease.
+
3.
A minimum tensile strength of 11,760 pounds for at least three wire sam)1es (one from each end and one at mid-length) cut from eac1 removed wire.
Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.
i 4.6.1.6.2 End Anchoraaes and Adiacent Concrete Surfaces The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes or degradation has occurred in the visual appearance of the end anchorage concrete exterior surfaces or as indicated by the concrete crack patterns adjacent to the end anchorages. Inspections of the concrete shall be performed concurrent with the containment tendon surveillance (reference. Specification 4.6.1.6.1).
4.6.1.6.3 Liner Plate The structural integrity of the containment liner plate shal'. De determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.
_ecorts In lieu of any other report required by Specification 4.6.1.6.4 R
6.6.1, an initial report of any abnormal degradation of the containment structure' detected during the above required tests and inspections shall be made within 10 days after completion of the surveillance requirements of this specification and the detailed report shall be submitted pursuant to i
Specification-6.9.2 within 90 days after completion. This report shall include a description of the' condition of the concrete (especially at-tendon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.
MILLSTONE - UNIT 2 3/4 6-11 Amendment No. JJJ,165 0070
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