ML20212A897
| ML20212A897 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/15/1986 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212A864 | List: |
| References | |
| FRN-50FR27508 NUDOCS 8612290075 | |
| Download: ML20212A897 (4) | |
Text
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8 UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5(
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-34 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Company of Colorado (the licensee) dated May 22, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 comon 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 Comission's regulations and all applicable requirements have been satisfied.
8612290075 861215 PDR ADOCK 05000267 p
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D(2) of Facility Operating License No.
DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 15, 1986 l
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.o ATTACHMENT TO LICENSE AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NO. DPR-34 DOCKET NO. 50-267 Revise Appendix A Technical Specifications by inserting.the attached page as indicated. This page is identified by amendment number and contains vertical lines indicating the areas of change.
Remove Insert 4.9-i I
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' Fort St. Vrain #1 Technical Specifications Amendment No.
Page 4.9-l Specification LCO 4.9.3 Xenon Stability Testing l
Limiting Condition for Operation 1
The requirements of Specification 4.1.3 and 4.1.4 may be l'.
suspended during the performance of the Xenon ' Stability l
physics tests provided power perturbations d.o not exceed those which are expected, as determined ey' an engineering l
l evaluation performed prior to the test, and approved by the-
~l NFSC.
l APPLICABILITY: During Xenon Stability physics tests.
l ACTION:
With the occurrence of power perturbations in excess of l
s.
l the approved maximum limits, reduce thermal power sufficiently to stop power perturbations.
l l
Surveillance Requirement: There is no specific surveillance l
requirement associated with LCO 4.9.3.
This test is conducted I
i n' accordance with the appropriate B series start-up test i
procedures.
2 l
Basis for Specification LCO 4.9.3 I
l In order for the Xenon Stability characteristics of the l
reactor core to be demonstrated, it is necessary to attempt to l
initiate xenon oscillations by. inserting an out of sequence rod.
l The limits on the average temperature rise in LCO 4.1.7, shall I
be maintained throughout this test.
Maintaining operation l
within these limits will fully protect plant equipment and the l
health and safety of the public.
l A detailed engineering evaluation will be performed in l
advance of any Xenon Stability Testing in order to analyze the l
planned test configuration to assure compliance with the intent l
of LCO 4.1.3 and LCO 4.1.4 throughout the test.
This l
engineering evaluation will assure that the maximum worth rod l
pair criteria is met (see FSAR, section 14.2.2.6 and 3.5.5.1),
l and that the assumptions utilized in development,of Core Safety l
Limit SL 3.1 (with regards to region, column, and axial peaking l
factors) remain valid throughout the test.
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