ML20205S528
| ML20205S528 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/16/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205S531 | List: |
| References | |
| NUDOCS 9904260249 | |
| Download: ML20205S528 (4) | |
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION C-WASHINGTON, D.C. 2055MX)01 49.....,o NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTOM NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.1m License No. NPF-49
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Noriheast Nuclear Energy Company, et al. (the li.censee) dated February 10,1999, 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 will operate 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 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.
f 9904260249 990416 i
PDR ADOCK 05000423 p
. 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) TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.169
. 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.
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- 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 1
J mes W. Cliffo, Section Chief Project Directorate 1-2 Division of Licer. sing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 16, 1999 i
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ATTACHMENT TO LICENSE AMENDMENT NO.1m FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A, Technical Specifications, with the attached page. The revised page is identified by amandment number and contains a vertical line indicating the area of change.
Remove Insert 3/4 4-42 3/4 4-42 l
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REACTOR C0OLANT SYSTEN 3/4.4.10 STRUCTURAL INTEGRITY LIMITING COWITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.10.
APPLICABILITY: All MODES.
ACTION:
a.
With the structural integrity of any ASME Code Class I component (s) not conforming to the above requirements, restore the ' structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor -
Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or
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isolate the affected component (s) prior to increasing the Reactor J
Coolant System temperature above 200*F.
c.
With the structural integrity..of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic partical testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels at least once every 10 years.
MILLSTONE - UNIT 3 3/4 4-42 Amendment No. J/, M4 0020 i
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