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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999
Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS
ML20196K0831999-06-29029 June 1999
Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution
ML20196G7131999-06-23023 June 1999
Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident
ML20206K5361999-05-0606 May 1999
Proposed Tech Specs Pages,Changing SLMCPR
ML20206R9351999-01-12012 January 1999
Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions
ML20154Q4511998-10-16016 October 1998
TS Bases Update for Period of 970410 Through 981015
ML20236T1661998-07-20020 July 1998
Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue
ML20198J3581998-01-0909 January 1998
Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions
ML20210F6651997-12-22022 December 1997
Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations
ML20217H6211997-12-15015 December 1997
Rev 21 to Odcm
ML20199L5711997-11-26026 November 1997
Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related
ML20198N3231997-11-0606 November 1997
Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan
ML20198N3941997-10-28028 October 1997
Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program
ML20211M8481997-10-0606 October 1997
Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing
ML20210V5581997-09-18018 September 1997
Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12
ML20210H0871997-08-0606 August 1997
Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01
ML20141A1681997-05-0707 May 1997
Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements
ML20140E3211997-04-18018 April 1997
Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201
ML20134N7841996-11-21021 November 1996
Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9
ML20134N7611996-11-20020 November 1996
Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation
ML20134E1261996-10-22022 October 1996
Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls
ML20128M5681996-10-0909 October 1996
Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements
ML20117P4461996-09-19019 September 1996
Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency
ML20117M7021996-09-0505 September 1996
Proposed Tech Specs Re Min Critical Power Safety Limit
ML20117G6781996-08-27027 August 1996
Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves
ML20116F0211996-07-31031 July 1996
Proposed Tech Specs Required to Support Cycle 9,reload 8
ML20113B7381996-06-20020 June 1996
Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage
ML20117L2581996-06-0404 June 1996
Proposed Tech Specs Re Replacement Page for Ltr
RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996
Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks
ML20117D6941996-05-0909 May 1996
Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies
ML20117F4661996-05-0909 May 1996
Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation
ML20111B2701996-05-0808 May 1996
Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency
ML20108E3591996-05-0606 May 1996
Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc
ML20107E4681996-04-18018 April 1996
Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells
ML20100J8391996-02-22022 February 1996
Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves
ML20097C3541996-02-0101 February 1996
Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases
ML20094M8001995-11-20020 November 1995
Proposed Tech Specs Re Drywell Leak Rate Testing Requirements
ML20087B5061995-08-0404 August 1995
Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident
ML20082K3451995-04-13013 April 1995
Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers
ML20108A2691995-03-10010 March 1995
Rev 17 to ODCM
ML20078S5141995-02-14014 February 1995
Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2
ML20078N6611995-02-10010 February 1995
Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval
ML20079B4501994-11-0909 November 1994
Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident
ML20070C9751994-06-24024 June 1994
Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J
ML20065L4971994-04-15015 April 1994
Proposed Tech Specs Re Administrative Controls
ML20059H6101994-01-14014 January 1994
Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220
ML20059H6061994-01-13013 January 1994
Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit
ML20029D6451993-11-30030 November 1993
Reactor Containment Bldg 1993 Integrated Leakage Rate Test.
ML20058D3911993-11-23023 November 1993
Proposed Tech Specs Bases Pages Re Cycle 7 Reload
ML20059A4871993-10-22022 October 1993
Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests
1999-08-20
[Table view]
Category:TEST REPORT
MONTHYEARML20210F6651997-12-22022 December 1997
Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations
ML20059H6101994-01-14014 January 1994
Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220
ML20029D6451993-11-30030 November 1993
Reactor Containment Bldg 1993 Integrated Leakage Rate Test.
ML20086K4651991-12-31031 December 1991
GGNS Unit 1 Cycle 6 Proposed Startup Physics Tests
ML20067C0851991-02-0202 February 1991
Cycle 5 Startup Physics Test Summary
AECM-89-0145, Cycle 4,Startup Physics Test Summary1989-07-21021 July 1989
Cycle 4,Startup Physics Test Summary
AECM-89-145, Cycle 4,Startup Physics Test Summary1989-07-21021 July 1989
Cycle 4,Startup Physics Test Summary
ML20245G8941989-04-30030 April 1989
Primary Reactor Containment Integrated Leakage Rate Test,Final Rept
ML20065N4901987-02-10010 February 1987
Test Rept for Flux Wire Dosimeter Removed from Grand Gulf 1 at End of Cycle 1
ML20203F1831986-06-16016 June 1986
Balance-of-Plant Sys Piping Thermal Expansion Monitoring Program
ML20203F1611986-06-16016 June 1986
Balance-of-Plant Sys Piping Vibration Monitoring Program
ML20203F1411986-06-13013 June 1986
Special Test-Visual Steady-State Vibration Monitoring Program
ML20154L0101985-11-30030 November 1985
Reactor Containment Bldg Integrated Leak Rate Test, Final Rept
L-01-220, Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept1985-08-19019 August 1985
Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept
ML20080C8071983-11-30030 November 1983
Physical Modelling of Contaminant Concentrations at Control Room
ML20080C8191983-11-30030 November 1983
Physical Modelling of Contaminant Concentrations at Control Room:Apps
L-06-221, Rev 0 to in Situ Operational Testing of HPCS Svc Water Pump for Grand Gulf Nuclear Power Station1983-09-26026 September 1983
Rev 0 to in Situ Operational Testing of HPCS Svc Water Pump for Grand Gulf Nuclear Power Station
ML20069N9571982-11-30030 November 1982
Revision a to Survey of Tests & Analyses on Effectiveness of RHR Sys in Pool-Cooling Mode
ML20064N6651982-11-12012 November 1982
Nuclear Environ Qualification Final Rept of Hydrogen Ignitor Assemblies for Grand Gulf Nuclear Station Unit 1, Vol 1.Ignitor Assemblies Fully Qualified Per IEEE 323-1974
ML20054B5051982-04-14014 April 1982
Primary Reactor Containment Structural Integrity Test, Final Rept
ML20054B5211982-04-14014 April 1982
Primary Reactor Containment Integrated Leakage Rate Test, Final Rept
ML20054E2171982-04-14014 April 1982
Test Rept HPCS Power Supply Unit. Four Oversize Figures Encl.Aperture Cards Are Available in PDR
ML20041F7171982-03-15015 March 1982
Discussion of Kuosheng Safety Relief Valve Mutli-Valve Actuation (MVA-4) Response Spectra. Design Impact Considered Confirmatory
ML20052B1991980-11-0606 November 1980
Qualification Insp of Series 20K Instrument & Control Switch to ESC-STD-1000,Revision 1.
ML20049J5551980-08-18018 August 1980
Seismic Vibration Testings of Two Limitorque Actuators for Limitorque Corp.
ML20052B2071978-01-14014 January 1978
Rept of Test on Seismic Vibration Testing of Switches P/N 20KB-1124A4 for Electro Switch Corp.
ML20081M3281977-01-26026 January 1977
Test Rept:Delaval Standby Generator Set,Grand Gulf Nuclear Station 1 & 2,Engine Unit
ML20049J5501976-11-0404 November 1976
Environ Test Rept on TRC Model 75G-002,1 Inch Y Pattern Solenoid Motor Valve Soft Seated,High Pressure Version.
ML20052B2121975-11-20020 November 1975
Rept of Seismic Qualification Tests of Series 10 & Series 20 Switches.
ML20052B2171975-11-14014 November 1975
Rept of Test on Seismic Vibration of Electro P/N 10KB2212C8 for Electro Switch Corp.
ML20052B2241975-11-14014 November 1975
Rept of Test on Seismic Vibration of Electro P/N 10LB2212C8 for Electro Switch Corp.
ML20052B2281975-11-14014 November 1975
Rept of Test on Seismic Vibration of Electro P/N 10LB2206C8 for Electro Switch Corp.
ML20052B2301975-11-14014 November 1975
Rept of Test on Seismic Vibration of Electro P/N 20KB2210C8 for Electro Switch Corp.
ML20052B2471975-11-14014 November 1975
Rept of Test on Seismic Vibration of Electro P/N 20LB2206C8 for Electro Switch Corp. Justification for Interim Operation of Pressure Indicators B21-R005/R009 Encl
ML20049J5511974-10-22022 October 1974
Environ Test Rept on TRC Model 72V Type,1 Inch Y Pattern Solenoid Motor Valve.
1997-12-22
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SEN ER AL $ ELECTRIC FMT TPM SMITTAL NO. 87 212 0007 NUCLEAR FUEL & ENGINEERING SERVICES DEPARTMENT TUEL MATERIALS TECHN0thGY TEST REPORT DETERMINATION OF FAST NEUTRON FLUX DENSITY AND FLUENCE:
CRAND CULF NUCLEAR STATION UNIT 1 February 10, 1987 DPJ A00 02764 Prepared By:
- b. b 1!'#/!87 Date G. C. Martin Fuel Materials Technology Reviewed By: <M f.t // A// 7 L. K. Kessler Date ruel Materials Technology Approved By: -
/Y 141 f ._
1 *"~ I ) ~ 2 R.' B. Adamson, Manager Date Fuel Materials Technology i
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BETTP.MINATTON OF TAST NEUTRON TLUX DENSITY AND TLUENCE:
gP>SD CULT NUCLEAR STAT 10N UNIT 1
SUMMARY
The f ast neutron flux density and fluence (integrated neutron flux) at a capsule near the reactor vessel wall of the Grand Gulf Nuclear Power Station Unit 1 of Systems Energy Resources, Inc. have been determined to bei 8.9x108 n/cm2.s >l MeV full power flux density 1.4x10' n/cm .s 2 >0.1 MeV full power flux density 2.6x1028 n/cm 2 >l MeV fluence 4.2x1058 n/cm 2 >0.1 MeV fluence following the analysis of irradiated iron flux dosimeters, in accordance with the CF. CM6S Method No. 10.1.6.0 R3.
EXPERIMENTAL Three iron wires were irradiated in a CE pressure vessel capsule holder at Crand Gulf Unit 1 from September 25, 1983 (startup) to September 5, 1986 (end of cycle 1). Each wire was removed from the capsule, cleaned with 4N RS03 ,
weighed, mounted on a counting card, and analyzed for Mn 54 content at a calibrated 4 cm source to detector distance with 100 ce and 80 ec Ce(Li) detector systems.
From daily thermal power generation summary tables, the irradiation time periods were calculated. Operating days for each period and the reactor average power fraction are shovn in Table 1. Zero power days between fuel periods are also listed.
TABLE 1. prand Culf Unit 1 Irradiation Periods (Cvele li Percent of Between Period Period Date Daya Full Power
- _Ilye (Days) 1 09/25/83 11/08/83 45 0.019 166 2 04/23/84 06/01/84 40 0.028 97 3 09/07/84 02/09/85 156 0.167 46 4 03/28/85 10/12/85 199 0.690 58 5 12/10/85 08/25/86 259 0.655 6
6 09/01/86 09/05/86 5 0.634
(*During operation.
Full power was 3B33 MWt .) 704 (Total) 0.460 (Av) 1 l
r l .
DISCUSSION OF PESULTS Trom the activity measurements and power history, reaction rates for 6*Te(n.p)5'Mn were calculated. These data appear in Table 2. The Grand Gulf Unit 1 >l MeV flux density reaction cross section for iron was calculated te be 0.187 barns. This value was obtained from measured cross section data functions from more than 65 spectral determinations for BVRs and for the General Electric Test peactor using activation monitors and spectral unfolding techniques. These data functions were applied to BVR pressure vessel locations based on water gap (fuel to pressure vessel) distances. The >l MeV/>0.1 MeV cross section ratio at BVR pressure vessel locations is approximately 1.6.
The determined full power flux density and actual fluence results at the Grand Gulf reactor vessel vall capsule holder location are given in Table 2. The >l MeV and >0.1 MeV values of 8.9x108 and 1.4x10' n/cm .s from the iron flux 2
monitors were calculated by dividing the reaction rate measurement data for the
- *Te(n p)6 *Mn reaction by the 0.187 barn and 0.187/1.6 barn cross sections.
The corresponding fluence results, 2.6x10:e and 4.2x1088 n/ca' for >l MeV and
>0.1 Mev, respectively, were obtained by multiplying the full power flux density values by the product of the total seconds irradiated (6.08x10' s) and the full power reaction (0.480).
The 20 errors of the values in Table 2 are estimated to be:
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