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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 ML20135C1951996-10-31031 October 1996 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1995-1996 ML20134H1791996-06-30030 June 1996 Rev 2 Suppl Reload Licensing Rept for RBS Reload 6,Cycle 7 ML20117H2871996-06-30030 June 1996 Common Cause Assessment of Refuel Operations at River Bend Station ML20096F2351995-11-30030 November 1995 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1994-1995 ML20100F3191995-11-30030 November 1995 Suppl Reload Licensing Rept for RBS Reload 6,Cycle 7 ML20129E2981995-05-31031 May 1995 Final BNL Technical Rept, Metallurgical Evaluation of FW Nozzle to Safe-End Weld from River Bend Station Unit 1 ML20086C4371995-05-31031 May 1995 Draft, Metallurgical Evaluation of Feedwater Nozzle to Safe-End Weld from River Bend Station,Unit 1 ML20080B3961994-11-30030 November 1994 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1993-94 ML20078C7881994-06-30030 June 1994 Revised Semi-Annual Rept on Fitness-For-Duty Program, for Reporting Period of 940101-0630 ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20128N3271993-02-17017 February 1993 Rev 0 to EA-PT-0003-S2, Responses to NRC Questions on River Bend Station Plant Transient Analysis Methodology, Suppl 1,EA-PT-91-0003-SP ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20101R0691992-06-0808 June 1992 Rev 92-6 to Approved Vendors List Matl Mfgs & Suppliers of ASME Section III Matl & Subcontracted Svcs ML20094P2691992-03-31031 March 1992 Rev 0 to EA-CA-91-0001-S2, Steady State Core Physics Methods for BWR Design & Analysis, App G ML20091J5161992-01-31031 January 1992 Rev 0 to Steady State Core Physics Methods for BWR Design & Analysis ML20079P1211991-10-31031 October 1991 Suppl 1 to Nonproprietary River Bend Station Plant Station Plant Transient Analysis Methodology - Delta CPR Methodology & Addl Benchmarks RS-91-137, Rev 0 to RCIC Reliability Analysis,River Bend Nuclear Station1991-09-10010 September 1991 Rev 0 to RCIC Reliability Analysis,River Bend Nuclear Station ML20091C5391991-07-31031 July 1991 Technical Justification for Eliminating Mid-Cycle Insp of Feedwater Nozzle (N4A) to Safe-End Weld Indication at River Bend Plant ML20077A4611991-04-30030 April 1991 Transient Analysis Methodology ML20072T6571991-03-31031 March 1991 Rev 1 to Bounding Evaluation for River Bend 1 Heatup Rate Event ML20072P9881990-11-15015 November 1990 Draft Reassessment of Indication in Riverbend Feedwater Nozzle (N4A) to Safe End Weld ML20043A9051990-03-31031 March 1990 Rev 1 to Implementation of Reg Guide 1.99,Rev 2 for River Bend Station,Unit 1. ML20247J9411989-02-0909 February 1989 Analyses of Components in Asco Solenoid Valve ML20043A9061988-06-30030 June 1988 Flux Wire Dosimeter Evaluation for River Bend Station. ML20149J4111988-02-29029 February 1988 IE Bulletin Program Rept ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20141M8571986-01-28028 January 1986 Investigation,Analysis & Corrective Action for River Bend Station,860101 Loss of Offsite Power ML20137H2091985-08-31031 August 1985 Suppl 3 to Preliminary Equipment Survivability ML20134G9611985-08-31031 August 1985 Revised Stuck Open Relief Valve Base Case ML20134G9681985-08-31031 August 1985 Suppl 2 to Preliminary Equipment Survivability Rept ML20134H1661985-08-31031 August 1985 Equipment Survivability Enhancement ML20129E9081985-07-31031 July 1985 Hydrogen Deflagration Pressure Effects on Equipment ML20129F0971985-07-31031 July 1985 Revised Drywell Break Base Case Analysis ML20128H4581985-07-31031 July 1985 Preliminary Equipment Survivability Rept,River Bend Station Unit 1,Jul 1985 ML20128L9401985-06-30030 June 1985 Reg Guide 1.97,Rev 3 Compliance Rept ML20127K6031985-06-0101 June 1985 Operational Safety of Tdi DSR-48 Emergency Diesel Generator Crankshafts at River Bend Station,Gulf States Utils ML20125C4601985-05-31031 May 1985 Dcrdr Summary Rept Suppl ML20127K7081985-05-18018 May 1985 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at River Bend Station ML20117A5631985-04-30030 April 1985 Design & Computer Analysis of Siren Prompt Notification Sys River Bend Station ML20111C5501985-02-28028 February 1985 Rev 1 to Tdi Diesel Generator Design Review & Quality Revalidation Rept ML20107H1721985-02-15015 February 1985 Rev 0 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) ML20101M6091984-12-31031 December 1984 Vols I-IV of Tdi Diesel Generator Design Review & Quality Revalidation Rept ML20100N2701984-11-20020 November 1984 Rev 1 to IE Bulletin 79-27 Study,Rept of Findings for River Bend Station Unit 1 ML20099H3761984-10-31031 October 1984 Detailed Control Room Design Review,Methodology & Approach, Human Engineering Discrepancy Results, Summary Rept ML20100N4141984-10-31031 October 1984 Common Sensor Failure Evaluation Rept ML20100N4121984-10-31031 October 1984 Control Sys Failures Evaluation Rept ML20093M7121984-10-0808 October 1984 Gulf States Util Co Position Re Safety/Relief Valve Discharge Testing at River Bend Station ML20093D1861984-07-0909 July 1984 Seismic OBE & SSE Required Response Spectra for Auxiliary, Control,Diesel Generator,Fuel,Turbine,Pipe Tunnels 1 & 2 & Standby Svc Water Pumphouse & Cooling Tower Bldg 1997-11-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
[Table view] |
Text
_ _ . _ . _ _ _ _ - - _ . - _ _
SASR 88-49 DRF'A00 02764 1 June'1988 l
e
- FLUX WIRE DOSIMETER EVALUATION F0h RIVER BEND STATION ,
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Prepared by: .[ '
T.A.. Caine, Senior Engineer Structural Analysis Services Verified by:' la/20/$$ .
G . L .V Stevens . Engineer Structural Analysis Services
-r Reviewed by:
1 S. Ranganath, Manager Structural Analysis Services
, G 90052302bb vooSta GENuclearEnergy i PDR ADOCK 05000a58 p PDC J
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IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT-PLEASE READ CAREFULLY.
This report was prepared by . General ~. Electric solely for the use--
of Gulf States Utilities. The information contained in this report is believed by General Electric to be an accurate and.true representation 1 of the facts known, obtained or provided to - General Electric at the time this report was prepared.
.The only undertakings of.-the' General. Electric Company respecting information in this document are ' contained in the contract governing _
Gulf States Utilities Furchase Order 8-5N 71020 and nothing contained- !
in this document shall be construed as changing 'said contract. .The use of this information except as defined by said contract, Jor for any, purpose other than that for which it is intended,-is not authorized;.
and with respect to any. such unauthorized use. .neither ' General-Electric Company nor any of, the contributors ; to this. document makes-any representation or 1 warranty (express or implied) as 'to completeness, accuracy or usefulness of the :information contained in the-
]
Il this document or that such use of such information: may not infringe i
,1 privately owned rights; nor. do they assume 'any responsibility ' for liability or damage of any kind which may result from such use of'such
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CONTENTS IAS.t
- 1. INTRODUCTION 11
- 2. ANALYSIS 21 31
- 3. RESULTS 4 CONCLUSIONS 41 APPENDICES l
A. TEST REPORT FOR FLUX VIRE DOSIMETER REMOVED FROM A.1-RIVER BEND AT END OF CYCLE 1-I i
I iii
2
- 1. INTRODUCTION r
f In September 1987, River Bend Station completed its first fuel cycle. During the outage that followed, the flux wire dosimeter attached to the surveillance capsule at the vessel 3' atinuth was ,
removed. The dosimeter was shipped to the General Electric Vallecitos Nuclear Center (VNC) in Pleasanton, CA for testing. The test results and the associated determination of peak vessel flux and fluence are presented in this report.
1 The surveillance program for River Bend consists of three ;
surveillance capsules and one flux wire dosimeter. Each surveillance capsule contains Charpy specimens of the beltline base, weld and HAZ
- materials;, and a set of flux wires used to determine the fit.ence experienced by the capsule. The surveillance capsules cre scheduled ;
to be withdrawn periodically during plant life (the current schedule required by ASTM E185 82 is a capsule at 6,15, and 32 effective. full .
power years)., in addition to the flux wires in the surveillance ,
capsules, a flux wire dosimeter is attached to the capsule at 3*, as shown in Figure 11, for removal af ter the first fuel cycle. Since the vessel fluence is proportional to thermal power produced, the +
results of the flux wire dosimeter test are used to provide a !
calibration point of vessel fluence versus accumulated thermal power.
A linear extrapolation provides an estimate of the fluence at 32 effective full power years (EFT 7). It should be noted that the flux wires that will be removed later as part of the surveillance capsules will have an irradiation history more typical of norma 1' operation, and will be useful for re calibrating the 32 ETPY fluence' estimate, l
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1
- 2. ANALYSIS 1
The determination of the peak 32 EPPY fluence is basically a
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two step process. First, the flux wires are analyzed to determine the l flux and fluence at the dosimeter location. Then, lead factors are f
calculated which relate the flux magnitude at the dosimeter location l to that at the location of peak flux.
The flux wire dosimeter was disassembled at VNC and the iron flux wires were cleaned and weighed. Camma spectrometry was used to determine the rate of disintegrations. The daily power history of the i first fuel cycle was used, along with cross section data developed for BWRs to transform the disintegration data into rates of irradiation, or flux (n/ca' s). The detailed procedure used in evaluating the flux wires is contained in the test report in Appendix A.
The determination of lead factors was done for a generic 218 inch. ,
diameter vessel with 624 fuel bundles. This matches the River Bend configuration. The lead factors are essentially geometry dependent.
Plant specific characteristics of the flux are accounted for in the results of the flux wire test. Furthermore, the generic lead factors were calculated assuming an equilibrium fuel cycle, which is representative of a typical normal operation core power distributien.
Therefore, the generic lead factors provide the best available means of predictin6 peak 32 EFPY fluence from the flux wire data.
Determination of the lead factors for the RPV peak location at the inside wall and 1/4 T depth was done using a combination of one dimensional and two dimensional finite difference computer analysis. The two dimensional analysis established the relative i
fluence in the azimuthal direction at the vessel surface and 1/4 T l depth. A series of one dimensional analyses was done to determine the core height of the axial flux peak and its -relationship to the:
surveillance capsule height. The combination of azimuthal and axial distribution results provides the lead factor between the dosimeter l location and the peak flux location, t
l 21 L
The two dimensional DOT computer program was used to solve the Boltzman transport equation using the discrete ordinate method on an ,
(R,#) geometry, assuming a fixed source. One quarter core symmetry was used with periodic boundary conditions at O' and 90*. Neutron cross sections were determined for 26 energy groups, with angular scattering approximated by a third. order 14gendre expansion. A total i of 99 radial intervals and - 90 ezimuthal intervals were used. The model consists of an inner and outer core region, the shroud, water regions inside and outside the shroud, the vessel wall, and an air region representing the drywell, riux as a function of azimuth was ;
calculated, establishing the azimuth of the peak flux and its magnitude relative to the flux at the dosimeter location of 3' . This factor, the azimuthal component of the lead - factor, is shown in Figure 2 1.
The one dimensional computer code (SN1D) was used to calculate radial flux distribution for several core elevations at the peak azimuth angle. The elevation of the peak flux was determined, as well as its magnitude relative to the flux at the dosimeter elevation.
This factor is the axial component of the lead factor. The lead ,
factor between the peak and dosimeter locations was calculated as the azimuthal component times the axial component.
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- 3. RESULTS l The flux wire dosimeter test results are presented in detail in Appendix A. A summary of the >l MeV flux and fluence values for the {
dosimeter are presented in Table 31. As dircussed in the test 50% on the >l MeV flux and repart, there is an uncertainty of +254, Table 3 1 shows the upper bound values with the nominal l fluence. .
values. ,
l The lead factors for the peak location inside surface and 1/4 T depth are presented in Table 3 1 with the dosimeter test results. The lead factors are used to predict the peak fluence according to the following equation: '
Peak Fluence - (Dosimeter Flux)*(Full Power Seconds)/1Aad Factor . ,
The first fuel cycle for River Bend consisted of 619 days of operation :
with an average capacity factor of 0.588. This is equivalent' to ,
[
364.0 days at full power, or 1.0 EFPY. These values are used to I calculate the fluence values at the end of cycle one (E001) and at 32 EFPY, as shown in Table 3 1.
i i The fluences at the peak location I.D. and 1/4 T are plotted as a l
function of EFPY in Figure 3 1.
The error range of +256, -50% is not synnetrical because of judgement based on previous dosimeter test results. As some of the 10 year surveillance capsules are being tested, the 10 year dosimetry in '
these capsules are consistently testing at lower flux values than the first cycle dosimetry tests.- This is expected to be caused by the atypical operation of the first fuel cycle compared to the subsequent 10 years of operation. Therefore, it is expected that the flux values '
determined for River Bend in this test are higher than will typically-be experienced in future operation.
t 31
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Table 3 1 ,
FLUENCE DETERMINATION FOR THE PEAK IhCATION '
IN THE RIVER BEND VESSEL Time at Power:
EOC1 1.0 EFPY - 3.14x10 seconds 32 EFPY 32 EFPY - 1.01x10' seconds Lead Factors: ,
I.D. 0.50 t 1/4 T 0.66 r 2
Dosimeter Flux (n/cm .s) 4.4x10' (nominal) 5.5x10' (upper bound) 2 i FLUENCE (n/cm ):
NOMINAL , UPPER BOUND 17 17 EOC1 Peak 1.D. 2.8x10 3.5x10 I 17 EOC1 Peak 1/4-T 2.1x10 2.6x10 10 32 ETPY Peak 1.D. 8.9x10 1.1x10 '
10 10 32 EFPY Peak 1/4 T 6.7x10 8.4x10 l
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- 4. CONC 1%SIONS The flux wire test results summarized in Table 3 1 show a nominal peak fluence on the vessel ID at 32 EFPY of 8.9x10 18 n/cm2 . The l fluence determined by donimetry is sli$h tly higher than the design l fluence value of 8.7x10 18 n/cm 2 shown in Table 4.3 5 of the updated SAR.
i The results from the flux wire testing are generally- used to modify the pressure temperature curves in the Technical Specification. In this case, the flux nearly matches the original design value, if the nominal value from Table 31 is used. [
Furthermore, the NRC is finalizing Revision - 2 to Regulatory Guide 1.99, which will prompt a revision of the pressure temperature curves when it is issued. The curves in the Technical Specification, while based on a slightly non conservative fluence, are intended for 32 EFPY of operation, so even considering that actual flux may be higher, the curves are conservative for current operation. Therefore, it is r recommended that the - River Bend curves be revised once Regulatory Guide 1.99, Revision 2 becomes official.
P Changes to the Technical Specifications at this time need only include an acknowledgement that the flux wires were tested and- ,
possibly a summary of the test results. GSU may-want to include a <
comicitment to revise the pressure temperature curves according to Regulatory Guide 1.99, Revision 2 when'it becomes official.
l 4-1 v , - , ,
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1 I
APPENDIX A i
TEST REPORT FOR .
FLUX WIRE DOSlMETER REMOVED FROM RIVER SEND AT END OF CYCLE 1 f I
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