ML17284A885
| ML17284A885 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/27/1999 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17284A886 | List: |
| References | |
| NUDOCS 9910040248 | |
| Download: ML17284A885 (10) | |
Text
gD,5i REGG "o
Cy A,0 C
O
.A Y/
+G
~O~
++*++
, UNITED STATES NUCLEAR REGULATORY COlVIMISSION WASHINGTON, D.C. 20555-0001 ENERGY NORTHWEST DOCKET NO. 50-397 WNP-2 AMENDMENTTO FACILITY0 ERATING LICENSE Amendment No.
158 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
=
Theapplicationforamendmentbythe Energy Northwest(licensee) dated April7, 1999, as supplemented by letters dated May 25, June 21, August 2, and August 30, 1999, 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.
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:
99%0040248 990927 PDR ADOCK 05000397 P
P t
'L (2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.158 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..
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORYCOMMISSION Stephen Dembek, Chief, Section 2 Project Directorate IV8 Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
september 27, 1999
I[
'j
ATTACHMENTTO LICENSE AMENDMENTNO.
158 FACILITYOPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 2.0-1 5.0-21 2.0-1 5.0-21
1'l I
Il
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs
- 2. l.l. 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 HCPR for ATRIUM-9X fuel shall be a 1. 10 for two recirculation loop operation or a 1. 11 for single recirculation loop operation.
The HCPR for the.ABB SVEA-96 fuel shall be a 1.10 for two recirculation loop operation or ~ 1. 12 for single recirculation loop operation.
- 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 ( 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 ~ 484.158
J,
Ieporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COE OPERATING LIMITS REPORT COLR (continued) 1.
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 Models 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.
9.
ANFB Critical Power Correlation Uncertainty for Limited Data Sets, ANF-1125(P)(A), Supplement 1, Appendix D, Siemens Power Corporation
- Nuclear Division, July 1998.
c ~
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. 449 484,158
't i:,'
f(
L, i
tl j
il