ML17292A928
| ML17292A928 | |
| Person / Time | |
|---|---|
| Site: | Columbia  (NPF-21-A-151) |
| Issue date: | 07/03/1997 |
| From: | Colburn T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17292A927 | List: |
| References | |
| NUDOCS 9707160067 | |
| Download: ML17292A928 (10) | |
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0 Op UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 2055&4001 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
151 License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated May 20,
- 1997, as supplemented by letters dated June 6.
- 1997, and July 3.
1997.
complies with the standards and requi rements of the Atomic Energy Act of 1954.
as amended (the Act) and the Commission's 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.
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-21 is hereby amended to read as follows:
9707i60067 970703 PDR ADOCK 05000397 P
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C (2)
Technical S eci fications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
151 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
In addition, the license is amended as indicated in Appendix C attached to this license amendment and paragraph 2.C.(30) of Facility Operating License No.
NPF-21 is hereby amended to read as follows:
(30)
Additional Conditions The Additional Conditions contained in Appendix C.
as revised through Amendment No.
151, are hereby incorporated into this license.
Washington Public Power Supply System shall operate the facility in accordance with the Additional Conditions.
This license amendment is effective as of its date of issuance to be implemented prior to startup for Cycle 13 for the HCPR limits and prior to exceeding 25 percent power for Cycle 13 for the additional conditions in Appendix C.
Impl'ementation shall include for Cycle 13, accommodating the variability in the agreement between the US96A7 correlation redictions and the calculated matrix CPR values as identified in the icensee's July 3.
1997. lette'r, and evaluated in the staff's Safety Evaluation attached to this amendment.
FOR THE NUCLEAR REGULATORY CONNISSION Timothy G. Colburn, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Attachments:
1.
Changes to the Technical Specifications 2.
Appendix C
Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
151 TO FACILITY OPERATING LICENSE NO.
NPF-21 DOCKET NO, 50-397 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
REMOVE 2.0-1 INSERT 2.0-1
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SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure
< 785 psig or core flow <
10% rated core flow:
THERMAL POWER shall be ( 25% RTP.
2.1.1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:
2.1.1.3 The MCPR for ATRIUM-9X fuel shall be a 1. 13 for two recirculation loop operation or a l. 14 for single recirculation loop operation.
For all other fuel, the MCPR shall be a 1.07 for two recirculation loop operation or a 1.08 for single recirculation loop operation.
The MCPR limits for the ATRIUM-9X fuel are applicable to Cycle 13 only.
Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant S stem Pressure SL Reactor steam dome pressure shall be ~ 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2. 1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
WNP-2 2.0-1 Amendment No. 449 151
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APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO.
NPF-21 Washington Public Power Supply System shall comply with the following conditions on the schedules noted below:
Amendment Number 149 Additional Condition The licensee shall relocated certain technical specification requirements to licensee-controlled documents as described below.
The location of these requi rements shall be retained by the licensee.
Implementation Date Implementation shall be completed by June 30.
1997.
This licensee condition approves the relocation of certain technical specification requirements to licensee-controlled documents (e.g.,
as described in Attachment 1 to the licensee's letter dated January 14, 1997.
The approval is documented in the staff's safety evaluation dated Harch 4, 1997.
149 Regulatory Guide 1.160 commitments as as described in Attachment 1 to the licensee's letter dated January 14, 1997.
Implementation shall be completed 90 days from the date of issuance of Amendment 149.
151 To ensure sufficiently conservative SPC Implementation 9x9-9 OLNCPRs, the calculation of hCPR shall be completed will include a conservative adder based prior to exceeding on the variability observed in the 25 percent power US96A7 comparison with the ANFB for Cycle 13.
correlation.
This adder will be at a
minimum, the greater of two times the standard deviation in the mean error of the predictions relative to the calculated matrix values or a factor of 0.975 applied to the hCPR calculation, and will be independent of the 0.975 factor included in the US96A7 correlation as a conservative bias to the the US96A7 predictions of CPR for the SPC fuel.
Amendment No. 449.151
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