ML20056G186
| ML20056G186 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/19/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20056G187 | List: |
| References | |
| NPF-49-A-082 NUDOCS 9309020212 | |
| Download: ML20056G186 (4) | |
Text
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2 UNITED STATES i(
~j NUCLEAR REGULATORY COMMISSION j
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f W ASWNGTON. O C. 2055MJOO1 NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 i
AMENDMENT TO FACILITY OPERATING LICENSE I
l Amendment No. 82 i
License No. NPF-49 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated April 15, 1993, 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; j
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B.
The facility will operate in conformity with the application, the l
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 healtS and safety of the public; and i
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.
9309020212 930819 PDR ADDCK 05000423 P
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. 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. NPF-49 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 82
, 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 REGULATORY COMMISSION
/ W i
Je n
. Stolf, Director profect Directorate I-Division'of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 3
Specifications Date of Issuance:
August 19, 1'.93 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-49 ROCKET NO. 50-423
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Replace the following pages of the Appendix A Technical Specifications with l
the enclosed pages.
The revised pages are identified by amendment number and
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contain vertical lines indicating the areas of change.
Remove Insert 3/4 4-16 3/4 4-16 i
i I
STEAM GENERATORS SUPVEILLANCE REOUIREMENTS (Continued) 4.4.5.3 Inspection Frecuencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
a.
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months
- l after the previous inspection.
If two consecutive inspections, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40-month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3a.; the interval may then be extended to a maximum of once per 40 months; and c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
1)
Primary-to-secondary tubes leak (not including leaks
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originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, or 2)
A seismic occurrence greater than the Operating Basis Earthquake, or 3)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or i
4)
A main steam line or feedwater line break.
t Except that the surveillance related to the steam generator inspection, due no later than August 21, 1993, may be deferred until the next refueling outage or no later than September 30, 1993, whichever is i
earlier.
i MILLSTONE - UNIT 3 3/4 4-15 Amendment No. 82 0137