ML20211N887
| ML20211N887 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/10/1997 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211N892 | List: |
| References | |
| NUDOCS 9710170158 | |
| Download: ML20211N887 (8) | |
Text
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4 UNITO STATES NUCLEAR RECULATGRY CSMMISSIGN WASHINGTON, D.C. SteeHeM ENTERGY GULF STATES. INC. **
[AJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC.
DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.100 1.icense No NPF-47 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated August 29, 1996, as supplemanted by letters dated August 29 (proprietary), September 5 and October 8, 1997, 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(1) 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and
- E01 is authorized to act as agent for Entergy Gulf States, Inc, which has been authorized to act as agent for Cajun Electric Power Cooperative, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
- Entergy Gulf States, Inc., which owns a 70 percent undivided interest in RBS, has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc. was the surviving company in the merger, i
710170158 971010 PDR ADOCK 05000458 l
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. 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-47 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.100 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
EDI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
2.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION e
David L.
ginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 10, 1997 i
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AllACHMENT TO LICENSE AMENDMENT NO. inn FAtlLITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and 1
contain marginal lines indicating the areas of change.
REMOVE INSERT 3.1-4 3.1-4 3.1-5 3.1-5 3.2-4 l
3.2-5 3.3-3 3.3-3 5.0-18 5.0-18 5.0-19 5.0-19 s
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Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTR'OL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored core k-eff and the predicted core k-eff shall be within i 1% ok/k.
APPLICABILITY:
MODES I and 2.
ACTIONS CONDITION REQUIRE 0 ACTION COMPLETION TIME A.
Core reactiv'ty A.1 Restore core 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> difference not within reactivity difference limit.
to within limit.
B.
Required Action and B.3 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Com,letion Time not net.
illVER BEND 3.1-4 Amendment No. 81,100
Reactivity Anomalies 301.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Yerify core reactivity difference between Once within the actual and the predicted reactivity is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after within i 1% Ak/k.
reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AtiQ 1000 MWD /T thereafter during operation in MODE 1 i
RIVER BEND 3.1-5 Amendment No. H.100 1
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RPS Instrumentation 3e3.1.1 SURVEILLANCE REQUIREMENTS
..................................... NOTES------------------------------------
1.
Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.
2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Recutred Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associatec Function maintains RPS trip capability.
SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.1.2
.-------.---.-----NCTE-------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER k 25% RTP.
Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power l
5 2% RTP.
SR 3.3.1.2.3 Adjust the channel to conform to a 7 days calibrated flow signal.
NOTE-------------------
Not required to be performed when entering MODE 2 from NODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
7 days (continued)
RIVER BEND 3.3-3 Amendment Ko. St 100 m
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Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radioloaical Environmental Goeratina Reoort (continued) results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted in a supplementary report as soon as possible.
5.6.3 Radioactive Effluent Release Reoort The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year.
The re> ort shall include a summary of the quantities of radioactive 'iquid and gaseous effluents and solid waste released from the unit.
The material provided shall be consistent with the objectives outlined in the ODCM and process control program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1.Section IV.B.1.
5.6.4 Monthlv Operatina Reoorts Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam safety / relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1)
LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR),
2)
LCO 3.2.2, Minimum Critical Power Ratio (MCPR) (including power and flow dependent limits),
3)
LCO 3.2.3, Linear Heat Generation Rate (LHGR) (including power and flow dependent limits),
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents.
(continued)
RIVER BEND 5.0-18 Amendment No. 81,100 1
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Reporting Requirements 5.6 5.6 Reporting Requirements
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5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1)
NEDE-24011-P-A, ' General Electric Standard Application for Reactor fuel' (latest approved version);*
2)
NEDC-32489P (April 1996), 'T-Factor Setdown Elimination Analysis for River Bend Station' (for power and flow dependent limits methodology only as evaluated and approved by Safety Evaluation and License Amendment 100 dated October 10, 1997).
c.
The core operating limits shall be determined such that all a>plicable limits e.g., fuel thermal mechanical limits, core tlernal hydraulic l(imits Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any midcycle revisions or sup)1ements, shall be provided upon issuance for each reload cycle to the NRC.
- For Cycle 8, specific documents were approved in the Safety Evaluation dated October 6, 1997, to support License Amendment No. 99.
RIVER BEND 5.0-19 AmendmentNo.g05,00,
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