ML17284A630
| ML17284A630 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/29/1998 |
| From: | Poslusny C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17284A631 | List: |
| References | |
| NUDOCS 9806040035 | |
| Download: ML17284A630 (11) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CI Amendment No. 154 License No. NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnient by the Washington Public Power Supply System (licensee) dated December 4, 1997, as supplemented by letters dated January 28, 1998, March 3, 1998, March 9, 1998, and April 24, 1998, complies with the standards and requirements 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 facilitywilloperate 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 willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot 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.
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-21 is hereby amended to read as follows:
980M40035 980529 PDR ADOCK 05000397 P
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I'he Technical Specifications contained in Appendix A, as revised through Amendment No. >54 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.
3.
This amendment is effective as of its date of issuance to be implemented within 30 days of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Chester Poslusny, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Nay 29, 1998
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LI EN MENDMEN 0,
154 T F
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Replace the following pages of the Appendix ATechnical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
~lgQT 2.0-1 5.0-21 5.0-22 2.0-1 5.0-21 5.0-22
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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 a 25% RTP.
- 2. 1. 1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:
The MCPR for ATRIUM-9X fuel shall be a 1.13 for two recirculation loop operation or a 1. 14 for single.
recirculation loop operation.
The MCPR for the ABB SVEA-96 fuel shall be a 1.07 for two recirculation loop operation or a 1.09 for single recirculation loop operation.
The HCPR limits for the ATRIUM-9X fuel are applicable to Cycle 14.
- 2. 1. 1.3 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 a 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. +49 45+,154
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t Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT COLR (continued) l.
ANF-1125(P)(A),
and Supplements 1 and 2, "ANFB Critical Power Correlation," April 1990; 2.
ANF-NF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power.
Methodology for Boiling Water Reactors,"
November 1990; 3.
ANF-89-014(P)(A), Revision 1 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Generic Mechanical
~
Design for Advanced Nuclear Fuels Corporation 9x9-IX and 9x9-9X BWR Reload Fuel," October 1991; 4.
XN-NF-81-22(P)(A), "Generic Statistical Uncertainty Analysis Methodology," November 1983; 5.
NEDE-23785-1-PA, Revision 1,
"The GESTR-LOCA and SAFER Hodels for the Evaluation of the Loss-of-Coolant
- Accident, Volume III, SAFER/GESTR Application Methodology," October 1984; 6.
NED0-20566A, "General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with'10 CFR 50, Appendix K," September 1986; 7.
CENPD-300-P-A, "Reference Safety Report for Boiling Water Reactor Reload Fuel," July 1996; and 8.
WPPSS-FTS-131(A),
Revision 1, "Applications Topical Report, for BWR Design and Analysis," March 1996.
Co d.
The core operating limits shall be determined such that all applicable limits (e.g.,
fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
(continued)
WNP-2 5.0-21 Amendment No. 449,154
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Reporting Requirements 5.6 5i6 Reporting Requirements (continued)
I 5.6.6 Post Accident Monitorin PAM Instrumentation Re ort When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation,"
a report shall be submitted within the following 14 days.
The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
WNP-2 5.0-22 Amendment No. 449,154
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