ML20058C401
| ML20058C401 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/22/1990 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058C392 | List: |
| References | |
| NUDOCS 9011010212 | |
| Download: ML20058C401 (4) | |
Text
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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE 137 Amendment No.
License No.~DPR-3 a
1.
The Nuclear Regulatory Commission.(the Commission or the NRC) has found
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that:
A.
The application for amendment filed by Yankee Atomic Electric Compr.y (the licensee) dated June 4,1990 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 forthi-in 10 Cr,e Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rulestand. 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical:to the common 1
defense and security or to the health and safety of the public;. and ~
E.
The issuance of this emendment is in accordance with 10 CFR Part 51 of the Commission's reguletions and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical'Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby -
amended to read as follows:
1 (2) Technical Specifications The Technical Specifications contained in Appendix A,.as revised through Amendment No.137, are hereby incorporated in the' license.
The licensee shall_ operate the facility in accordance with the i
Technical Specifications.
9011010212 901022 PDR ADC'CK 05000029 P
3.
This license amendment is effective as of its date'of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3
Victor Herses, Acting Director Project Directorate I-3 Division of Reactor Projects I/II Office of Huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October. 22, 1990
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o-ATTACHitENT T0 llCENSE AMENDMENT N0.137 i
FACILITY OPERATING LICENSE NO. DPR-3
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DOCKET NO.50-029 7
Replace the following page of the Appendix A Technical Specifications with-i the atteched paDe. The revised page is identified by Amendment number and-1 contains a vertical line indicating the area of change.
l Remove Insert 3/4 1-27 3/4 1-27:
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RE/.CTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT l
f7MTTTMC CONDTTTOM FOR OPFPA? TOM 3.1.3.4 All shutdown rods shall be withdrawn to at least 87 inches.
APPLICABILITY: Modes 1* and 2*#
i ACTION:
With a maximum of one shutdown rod not withdrawn to within the limit, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:
(a) Withdraw the-rod to within the limit, or (b) Declare the rod to-be inoperable and apply Specification 3.1.3.1.
EURVFTLLAMCE RFOUTREMENTS 4.1.3.4 Each shutdown rod shall be determined to be withdrawn to within the limit:
1 (a) Within 15 minutes prior to withdrawal of any rods in control Group C during an approach to reactor criticality.
(b) At least once per four hours thereafter.
4 See Special Test Exceptions 3.10.2 and 3.10.4
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l-1 YANKEE-ROWE 3/4 1-27 Amendment No. #1, 137 i
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