|
|
Line 43: |
Line 43: |
| AtttchmInt to AECM-85/0371 Page 3 HCOG and NRC meeting on September 5, 1985 | | AtttchmInt to AECM-85/0371 Page 3 HCOG and NRC meeting on September 5, 1985 |
| -The HCOG met with the NRC on Septecher 5, 1985, te discuss the following items: | | -The HCOG met with the NRC on Septecher 5, 1985, te discuss the following items: |
| ; 1) Resolution of open items on the HCOG Program Plan as identified in the NRC ataff July 8 1935 letter | | ; 1) Resolution of open items on the HCOG Program Plan as identified in the NRC ataff {{letter dated|date=July 8, 1935|text=July 8 1935 letter}} |
| : 2) Resolution of open items effecting production testing as identified in the NRC staff August 16, 1985 letter 3). Agreement on the basis for initiating production testing in the Quarter Scale Test facility, and | | : 2) Resolution of open items effecting production testing as identified in the NRC staff {{letter dated|date=August 16, 1985|text=August 16, 1985 letter}} 3). Agreement on the basis for initiating production testing in the Quarter Scale Test facility, and |
| : 4) to discuss the additional work in progress on the facility heat loss report. | | : 4) to discuss the additional work in progress on the facility heat loss report. |
| 4.0 Test Program Status The summaries and status of the HCOG test program as stated here do not reflect the HCOG position with respect to any test program and represent only an MP&L interpretation of these pro 3 rams. | | 4.0 Test Program Status The summaries and status of the HCOG test program as stated here do not reflect the HCOG position with respect to any test program and represent only an MP&L interpretation of these pro 3 rams. |
Latest revision as of 13:04, 13 December 2021
|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20138A2041997-03-31031 March 1997 Pre-SALP Rept for SALP Period 960225-970906 ML20199G7191997-01-28028 January 1997 Rev 0 to Grand Gulf Nuclear Station Engineering Rept GGNS-97-0002 for GL 96-06 Evaluation of Drywall & Containment Penetrations ML20141A1321996-07-31031 July 1996 Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr ML20115A5851996-06-20020 June 1996 GGNS Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC214,OC302,OC308 & 1A539 ML20108D0861996-04-30030 April 1996 Surveillance Specimen Program Evaluation for Grand Gulf Nuclear Station ML20115A5831996-04-18018 April 1996 Engineering Rept for Evaluation of Ampacity Deratings for Thermo-Lag Fire Barrier Encl Cables in Fire Areas/Zones OC202,OC402,OC702 & 1A316 ML20100J8621996-02-22022 February 1996 Engineering Rept Safety/Relief Valves Safety Function Lift Setpoint Tolerance Relaxation Summary Rept ML20094M5241995-11-20020 November 1995 Self Assessment SALP Period 940227-960224 ML20078S1351995-02-0808 February 1995 SWS Operational Performance Insp (Swsopi) for Ggns ML20072C9891994-04-30030 April 1994 Survey of Melcor Assessment & Selected Applications, Third Draft ML20063H7791993-12-31031 December 1993 1993 Self Assessment ML20046A2601993-06-18018 June 1993 Safety Sys Functional Assessment, Low Pressure Core Spray & RCIC Sys. ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20116K8001992-11-13013 November 1992 Quarterly Status Rept for Period Ending 920930, 'Degraded Core Accident Hydrogen Control Program.' ML20095K0951992-04-30030 April 1992 Resolution of High Groundwater Levels at Grand Gulf Nuclear Station ML20086K4741991-10-31031 October 1991 Cycle 6 Plant Transient Analysis ML20086K4991991-10-31031 October 1991 Cycle 6 Reload Analysis ML20086K5111991-10-31031 October 1991 LOCA Analysis for Single Loop Operation ML20086K5191991-10-31031 October 1991 Nonproprietary Siemens Nuclear Power Corp Grand Gulf Unit 1 Reload XN-1.3,Cycle 4 Mechanical Design Rept Suppl 1 ML20029C3461991-03-31031 March 1991 Simulator Certification Rept for Grand Gulf Nuclear Station. ML20073K8451991-03-31031 March 1991 Entergy Nuclear Performance Rept,Mar 1991 ML20043B6871990-03-31031 March 1990 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Jan-Mar 1990 ML19353B1281989-12-0101 December 1989 Number 1 Low Pressure Turbine Rotor Ultrasonic Insp Summary. ML19332D1691989-09-30030 September 1989 Quarterly Status Rept for Jul-Sept 1989 Degraded Core Accident Hydrogen Control Program. AECM-89-0165, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8906301989-06-30030 June 1989 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 890630 ML20235X2621989-02-28028 February 1989 Criticality Safety Analysis of Grand Gulf Nuclear Station Unit 1 Spent Fuel Storage Racks W/Gaps in Neutron Absorbing Panels ML20235N3271989-02-22022 February 1989 Rept on Evaluation of Torsion Shear Stress Components in Design of Pipe Supports ML20247B1901988-11-30030 November 1988 Revised Flow Dependent Thermal Limits AECM-88-0021, Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-12311987-12-31031 December 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Rept Covering Period 871031-1231 AECM-87-0163, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 19871987-08-27027 August 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Apr-June 1987 ML20065N4861987-04-30030 April 1987 Flux Wire Dosimeter Evaluation for Grand Gulf Nuclear Power Station,Unit 1 ML20214U1711987-03-31031 March 1987 Technical Rept 86.2GG, Verification of Individual Plant Evaluation for Grand Gulf. W/Jr Siegel 870313 Release Ltr AECM-87-0102, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 8703311987-03-31031 March 1987 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending on 870331 AECM-87-0015, Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 8612311986-12-31031 December 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 861231 ML20213G2221986-11-10010 November 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 860930 ML20151A8791986-09-30030 September 1986 Rev 1 to SPDS Safety Analysis ML20215L2311986-09-30030 September 1986 Rev 0 to Grand Gulf Nuclear Station Safety Relief Valve Fatigue Evaluation ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20199L1091986-04-0303 April 1986 Station Blackout Evaluation Rept,Grand Gulf Nuclear Station ML20207G6991986-03-31031 March 1986 Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2 ML20155B0911986-02-28028 February 1986 Single Loop Operating Analysis ML20205J7381986-02-18018 February 1986 Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Quarter Ending 851231 ML20141N8871986-02-13013 February 1986 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Final Rept L-09-100, Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept1986-01-31031 January 1986 Rev 0 to MPL-09-100, Grand Gulf In-Plant Safety Relief Valve Test Fatigue Evaluation Final Rept ML20137E4471985-11-19019 November 1985 Metallurgical Evaluation of Recirculation Piping Ctr Cross Surface Cracking Following Induction Heat Stress Improvement,Grand Gulf Nuclear Station - Unit 1, Interim Rept 1999-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) 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 ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,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) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear 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 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
[Table view] |
Text
. l
.l
... Attcchm:nt to AECM/85-0371 Page 1 i
Quarterly Status Report for Quarter Ending September 30, 1985
" Degraded Core Accident Hydrogen Control Program" -
4 Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 Mississippi Power & Light Company i
4 0512050010 851129 .
PDR ADOCK 05000416 R PM J16AECM85111801 - 4
__ __ . . ._ _ _ _ _ = _ . _ _ . _
' '~ i Attcchatnt to AECM-85/0371 Page 2
~ Quarterly Status Report - September 30, 1985
" Degraded Core Accident Hydrogen Control Program" >
i 1.0. Introduction This_ quarterly status repor't is submitted to comply with a requirement in the Grand Gulf Nuclear Station,-Unit 1 Facility Operating License (License No.,NPF-29). .This requirementz specifies that Mississippi Power & Light (MP&L) should provide quarterly reporti outlining the~ status of the on-going research program to address degraded core hydrogen control requirements. This report covers the third calendar quarter of 1985 ending September 30, 1985.
'This report includes brief summaries of the submittals made by MP&L during this quarter along with summaries of meetings between the NRC staff and MP&L. MP&L'is participating in the Hydrogen Control Owners Group (HCOG) which is conducting generic research and completing generic analyses to resolve the degraded core hydrogen control issue. Since the work completed by HCOG complements MP&L's
. program to resolve this issue, this report also includes summaries of meetings between the HCOG and the NRC. The summaries of these Pettings included in this report do not reflect a formal HCOG position with respect to any issue and represent only the MP&L interpretation of the meetings. l 2.0 Summary of MP&L Submitta1s- __
MP&L made'no submittals to the NRC on the Degraded Core Accident Hydrogen Control Program during the third calendar quarter-of 1985 ending September 30, 1985. ,
3.0- Summary of HCOG and NRC Meetings HCOG and NRC meeting on July 17, 1985 The HCOG met with the NRC on July 17, 1985, to review. scoping test.
results and to discuss revisions to the scoping and production test matrices.
Topics of discussion included the review of initial conditions at-the Quarter Scale Test facility, facility instrumentation performance and a presentation on the general combustion phenomena-observed to date in the_ test facility.
The HCOG also indicated in-the meating that they would agree to the hydrogen release histories proposed by the NRC in the letter dated ,
June 24, 1985, fran R. M. Bernero to S. H. Hobbs. ]
J16AECM85111801 - 5
AtttchmInt to AECM-85/0371 Page 3 HCOG and NRC meeting on September 5, 1985
-The HCOG met with the NRC on Septecher 5, 1985, te discuss the following items:
- 1) Resolution of open items on the HCOG Program Plan as identified in the NRC ataff July 8 1935 letter
- 2) Resolution of open items effecting production testing as identified in the NRC staff August 16, 1985 letter 3). Agreement on the basis for initiating production testing in the Quarter Scale Test facility, and
- 4) to discuss the additional work in progress on the facility heat loss report.
4.0 Test Program Status The summaries and status of the HCOG test program as stated here do not reflect the HCOG position with respect to any test program and represent only an MP&L interpretation of these pro 3 rams.
4.1 1/4 Scale Test Program Status Scoping tests to assess the effects of variations in key parameters continued throughout the quarter.
4.1.1 Planned Activities for the 4th Quarter of 1985 Complete two additional scoping tests to assess the effect of grating above the suppression pool surface and gas temperatures near drywell wal l. Assessment of gas temperatures near the drywell wall is required to further evaluate the adequacy of the plume model in the Heat Loss Report. Production testing is expected to begin by the end of the fourth quarter.
J16AECM85111801 - 6
. _ - - . - , . . - .