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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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Grand Gulf'Nue' ear Station Unit 1 Attachment 5 to Cycle 6 Proposed Startup Physics Tests GNRO 91/00186 Page 1 of 2 GGNS UNIT 1 CYCLE 6 PROPOSED STARTUP PHYSICS TESTS DECEMBER 1991 l
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9112130128 911205 FDR ADOCK 00000416 P PDR
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Grand Guli Nuclear Station Unit 1 Attachu.ent 5 to Cycle 6 Proposed Startup Physics Tests GNRO-91/00186 Page 2 of 2 Proposed Startup Physics Tests for Cycle 6 9
- 1. Core Loading Verification The core will be visually checked to verify conformance to the vendor supplied <
core loading pattern. Fuel assembly serial numbers, bundie orientations, and core locations will be recorded. A height check will be performed to assure that all assemblies are properly seated in their respective locations.
- 2. Control Rod Functional Testing Prior to criticality following
- s refueling outage, functiona' testing of the control rods will be performed to assure proper operability. T his testing will include
' coupling verification, withdrawal and insertion timing, and friction testing where required.
- 3. Shutdown Margin Determination Control rods will be withdrawn in their standard sequence until criticality is achieved. The shutdown margin of the core will be determined from calculations based upon the critical rod pattern, the reactor period, and the moderator temperature. To assure there is no reactivity anomaly, the actual critical control rod position will be verified to be within 1 % dk/k of the predicted critical control rod position.
- 4. TIP Asymmetry A gross asymmetry check will be performed as part of e detailed statistical uncertainty evaluation of the TIP system. A complete set of TIP data will be obtained at a steady state, equilibrium xenon condition greatar than 85% rated power. A total average deviation or uncertainty will be determined for all symmetric TIP pairs as well as the maximum absolute deviation. The results will be evaluated to assure proper operation of the TIP system and symmetry of the core loading.
L.
Attachment 6 to GNRO-91/00186
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