ML20210Q896
| ML20210Q896 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/26/1997 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210Q898 | List: |
| References | |
| NUDOCS 9709020200 | |
| Download: ML20210Q896 (8) | |
Text
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION j;
l WASHINGTON. D.C. 30006 4 001
'49 l
ENTERGY GULF STATES. INC. **
I CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC.
DOCKET NO. 50-458 RIVER Bifid STATION. UNIT 1 AMENDMENT TO FACIllTY OPERATING LICEl(1E Amendment No. 97 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated January 20, 1997, as supplerented by letter dated July 7, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C.
There is reasoaable 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 condacted in compliance with the Commission's regL'ations;
- 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 River Bend, has merg,ed with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc. was the surviving company in the
- merger, p
9709020200 970026 i
DR ADOCK 050004 8
1 D.
The issuance of this license 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.
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 Licente No, NPF-47 is hereby amended to read as follows:
(2) Technical toecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 97 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
E01 shall operate the facilit/ 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 REGULATORY COMMISSION
~
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David L. W ton, 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:
August 26, 1997 s-w-
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ATTACHMENT TO LICENSE AMENDMEWT NO. 97 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-453 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
Revised bases pages and Technical Requirement Manual pages are also included for completeness.
REE INSERI 3.3-7 3.3-7 3.4-1 3.4-1 3.4-2 3.4-2 B 3.4-3 8 3.4-3 8 3.4-5 8 3.4-5
RPS Instrumentation 3.3.1.1 table 3.3.1.1 1 (pope 1 of 3) teoctor Protectlen treten instrueentation CONDifl0ml APPLICA8Lt kt0Vitt0 atFitthttD le:Ott On Diptt CMANNELS ft(M SPECIFitD Pit inlP tt0UltID sutVIILL&htt AllouAtti FUNCTION CONDifl0NS titfEM ACTIC:I D.1 attuttEMEWit VALUE l
i inier. wiese me,.e m iiore e.
moutron fluu NIsh 2
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st 3.3.1.1.1 s 122/125 at 3.3.1.1.4 elvlelene et 3.3.1.1.6 of futL st 3.3.1.1.7 ocate SR 3.3.1.1.13 at 3.3.1.1.15 5(*)
3 I
SR 3.3.1.1.1 s 122/125 SR 3.3.1.1.5 divisions tR 3.3.1.1.13 of full SR 3.3.1.1.15 ocete b.
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N SR 3.3.1.1.4 hA st 3.3.1.1.15 5(*)
3 I
SR 3.3.1.1.5 EA st 3.3.1.1.15 2.
Aversee Power tonee Monitors o.
Neutran flux-Nich, 2
3 N
SR 3.3.1.1.1 s 201 RIP letdown SR 3.3.1.1.4 st 3.3.1.1.7 st 3.3.1.1.8 SR 3.3.1.1.11 at 3.3.1.1.15 b.
Flow Bleted Stoutetod 1
3 6
34 3.3.1.1.1 s 0.M W e thermal Power = Nish SR 3.3.1.1.2 671 RTP and
}
st 3.3.1.1.3 s 1131 SR 3.3.1.1.8 gyptb)
SR 3.3.1.1.9 SR 3.3.1.1.11 54 3.3.1.1.14 SR 3.3.1.1.15 st 3.3.1.1.17 SR 3.3.1.1.18 (contirued)
(e) With any control red withdrawn from a core cell contelning one or more fust seeembtles.
(b) Attowebte Vetue is s 0.M W e ett RTP when reset for einste loop operation per LCO 3.4.1
- t wirculation Leops Operating."
RIVER BEND 3.3-7 Amendment No. M,97
Recirculation loops Operating 3.4.1 l
3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating l
LCO 3.4.1 A.
Two recirculation loops shall be in operation with:
- 1. Natched flows; and
- 2. Total core flow and THERMAL POWER within limits, i
E B.
One recircolation loop shall be in operation with:
- 1. THERMAL POWER S 83% RTP; l
- 2. Total core flow and THERMAL POWER within limits;
- 3. Required limits modified for single recirculation loop operation as specified in the COLR; and
- 4. LCO 3.3.1.1, ' Reactor Protection System (RPS)
Instrumentation," Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High),
tilowable Value of Table 3.3.1.1-1 reset for single loop operation.
e----------NOTE----------------------------
Required limit and setpoint modifications for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single recirculatten loop operation.
APPLICABILITY:
MODES I and 2.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Recirculation loo) jet A.1 Shutdown one 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pum) flow mismate) not recirculation loop.
wit 11n limits.
(continued)
RIVER BEND 3.4-1 Amendment No. 81,97
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RecirculationloopsOperatin$
3.4.
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.
THERMAL POWER > 83%
B.1 Reduce THERMAL POWER 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> RTP during single loop to s 83% RTP.
operation.
C.
Total core flow as a C.1 Determine APRM and Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> function of THERMAL LPRM neutron flux POWER within Region Il noise levels.
AliQ of Figure 3.4.1-1.
30 minutes after l
an increase of I
h 5% RTP 0.
Total core flow as a 0.1 Restore APRM and LPRM 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> function of THERMAL neutron flux noise POWER within Region 11 level to s 3 times of figure 3.4.1-1.
established baseline levels.
AliD APRM or LPRM neutron flux noise level > 3 times established baseline noise level.
E.
Total core flow as a E.1 Restore total core 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> function of THERMAL flow as a function of POWER within THERMAL POWER to Region !!! of Figure within Region I or 11 3.4.1-1.
of Figure 3.4.1-1.
(continued)
RIVER BEND 3.4-2 Amendment No. 8+,97
_g,
B 3.4.1 BASES APPLICABLE The recirculation system-is also assumed to have sufficient SAFETY ANALYSES flow coastdown characteristics to maintain fuel thermal (continued) margins during abnormal operational transients (Ref. 2),
I which are analyzed in Chapter 15 of the USAR.
A plant specific LOCA analysis has been performed assuming only one operating recirculation loop. This antlysis has demonstrated that, in the event of a LOCA caused by a pipe break in the operating recirculation loop, the Emergency Core Cooling System response will provide adequate core cooling, gly (Ref.3).provided the APLHGR requirements are modified l
accord n The transient analyses of Chapter 15 of the USAR have also been performed for single recirculntion loop operation (Ref. 3) and demonstrate sufficient flow coastdown characteristics to maintain fuel thermal margins during the abnormal operational transients analyzed provided the MCPR requirements are modified. During single recirculation loop operation, modification to the Reactor Protection System average power range monitor (APRM) instrument setpoints is also required to account for the different relationships between recirculation drive flow and reactor core flow. The APLHGR and MCPR limits for singl_e loop operation are s>ecified in the COLR. The AP3M flow biased simulated tiermal power setpoint is in LCO 3.3.1.1, ' Reactor ProtectionSystem(RPS) Instrumentation.'
Recirculation loops operating satisfies Criterion't of the NRC Policy Statement.
LCO Two recirculation loops are normally required to be in operation with their flows matched within the limits specified in SR 3.4.1.1 to ensure that during a LOCA caused by a break of the piping of one recirculation loop the assumptions of the LOCA analysis are satisfied.
In addition, the total core flow must be 145% of rated co e flow or total core flow expressed as a function of THEMMAL POWER must be in Region I as identified in Figure 3.4.1-1,
" THERMAL POWER / Core Flow Stability Regions." Alternatively, with only one recirculation loop in operation THERMAL POWER aust be s 83% RTP, tha total core flow limitations l
identified above must be met, modifications to the required APLHGR limits (LC0 3.2.1, ' AVERAGE PLANAR LINEAR HEAT GENERATIONRATE(APLHGR)'),MCPRlimits(LC03.2.2,' MINIMUM fcontinued)
RIVER BEND B 3.4-3 Revision No. 0,1 t.-W*M
Recirculation Loops Operating l
B 3.4.1 BASES ACTIONS A d (continued)
Alternatively, if the single loop requirements of the LCO are applied to operating inits and RPS setpoints, operation with only one recirculation loop would satisfy the requirements of the LCO and the initial conditions of the '
accident sequence.
The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Completion Time is based on the low probability of an accident occurring during this time period, on a
- reasonable time to complete the Required Action, and on frequent core monitoring by operators allowing abrupt changes in core flow conditions to be quickly detected.
L1 Should a LOCA or tranisent occur with THERMAL POWER > 83%
RTP, during single loop operation the core response may not be bounded by t1e safety analyses. Therefore, only a limited time is allowed to reduce THERMAL POWER to s 83%
RTP.
The I hour Completion Time is based on the low probability of an accident occuring during this time period, on a 3
reasonable time to complete the Required Action, and on frequent core monitoring by operators allowing changes In THERMAL POWER to Le quickly detected.
C.1. D.1. and E.1 Due to themal hydraulic stability concerns, operation of the plant is divided into three regions based on THERNAL POWER.and core flows. Region III is a core flow < 39% of the rated core flow. power / flow ratio with Region II is a power / flow ratio with core flow k 39% and < 45% of the rated core flow.
Deliberate entry into Region !!! is not pemitted, and if it occurs, immediate action is required to exit the region within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by reducing THERMAL POWER through control rod insertion or by increasing recirculation loop flow by opening the flow control valve. Operation in
. Region II.is also more susceptible to instability than normal operating parameters. However, operation in this region is allowed with the exception that if evidence of (continued)
RIVER BEND B 3.4-5 Revision No. 4, 2
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