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Category:NRC TECHNICAL REPORT
MONTHYEARML20212B0321986-12-17017 December 1986 Emergency Diesel Generator Component Failures Due to Vibration, Engineering Evaluation Rept ML20132E4291984-10-19019 October 1984 Rept of Investigation Entitled, Congressman Markey Ltr Re Region II Actions Re Grand Gulf Nuclear Station. Portions Deleted ML20132E4801984-10-11011 October 1984 Rept of Interview W/Jp O'Reilly Re Discrepancies in Reactor Operator Training Program at Plant,Per Restart of Facility on 830925 & 830923 Meeting W/Util at Region Ii.Nrc Response to Markey Questions Encl.Portions Deleted ML20132E7781984-09-25025 September 1984 Rept of Interview W/Af Gibson Re Deficiencies in Reactor Operator Training Program at Facility & 830923 Meeting W/Util at Region II Concerning Util Refusal to Submit Ltr to Nrc.Portions Deleted ML20132E6431984-09-25025 September 1984 Rept of Interview W/Dh Beckham Re Discrepancies in Reactor Operator Training Program at Facility,Per Impact on Facility Operation.Portions Deleted ML20132E5861984-09-24024 September 1984 Rept of Interview W/Dm Verrelli Re Events & Circumstances of 830923 Meeting W/Util at Region II & Language Used in 831205 Confirmation of Action Ltr to Util ML20132E6171984-09-21021 September 1984 Rept of Interview W/Region II Employee Re Reactor Operator & Senior Reactor Operator License Applications & Operator Training Deficiencies at Facility.Portions Deleted ML20132E5591984-09-19019 September 1984 Rept of Interview W/Region II Employee Re Discrepancies in Reactor Operator & Senior Reactor Operator Licensing Program at Facility.Portions Deleted ML20132E5221984-09-18018 September 1984 Rept of Interview W/Jm Puckett Re Discrepancies in Licensed Operator Training Program at Facility,Per Region II Enforcement Actions.Reactor Operators Not Trained Per FSAR Commitments.Portions Deleted ML20132E7111984-09-17017 September 1984 Rept of Interview W/Ofc of Investigation,Atlanta Field Ofc Employee Re Impact Region II 830923 Meeting W/Util Had on Ofc of Investigation Case 2-83-037.Interviewee Name Withheld ML20132E5691984-08-21021 August 1984 Rept of Interview W/Util Employee Re 830923 Meeting W/Util at Region II Concerning Discrepancies in Operator Qualification Cards at Facility.Interviewee Name Withheld ML20132E5271984-08-19019 August 1984 Rept of Interview W/Jp Mcgaughy Re 830923 Meeting at Region II Concerning Discrepancies in Operator Qualification Cards at Facility.Draft Util Ltr Re Discrepancies Encl.Portions of Rept Deleted ML20132E8121984-08-18018 August 1984 Rept of Interview W/Region II Employee Re 830923 Meeting W/Util at Region II & Discrepancies in Reactor Operator & Senior Reactor Operator Training at Facility.Portions Deleted 1986-12-17
[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
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- U. .dUCLEAR GEGULATOnY COMMisslON Office of Inspee
- or and Auditor o..seo..........._ Sept c h r 25, 19B4 eue Report of Interview Don H. Beckham, Chief, Operator Licensing Branch, Division of Human Factors Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comis-sion, was interviewed concerning his knowledge of the discrepancies in the Reactor Operator Training Prognm (ROTP) at Grand Gulf Nuclear Station (GGNS) with respect to the impact on operation of that plant. He provided the following information:
His first involvement in this matter began in the September / October 1983 -
timeframe. He recalled that sub he Auoust 15- 983, ins t GGNS perfomed by -
nw ons Branch (OB), Division of eactor Safety (DRS),
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OLS, OB, DRS, and others, they '
related t r rinoings in that inspection to him.
Generally, they told him that the licensee had an atroscious filing system for ROTP records at the site.' They also told him that based on their findings, they planned to conduct another on-site training assessment of the reactor operators at GGNS. Following that "assment which was conducted from October 31 through November 4, 1983 advised him that apparently some of the reactor operators had not receiveo all of the required training.
On November 18, 1983, he attended a meeting between Mississippi Power and Light (MP&L) and Region II officials to discuss a recertification of ROTP at GGNS that was deemed necessary by NRC as a result of the on-site assessment
' conducted on October 31 through November 4, 1983. At that meeting, MP&L verbally com;tted to NRC that they would conduct a total recertification for ROTP at GGNS and also that until the recertification was completed, the reactor would remain in a state of cold shutdown. At that meeting MP&L provided handouts describing the corrective action plan they were proposing (Exhibit 1).
Coincidental with the meeting of November 18, 1983, he participated in dis-cussions about whether or not operator licenses at GGNS should be revoked or suspended. NRC believed that MP&L was not being totally above board on the issue regarding dis repancies in ROTP, however, there was nothing to substan-tiate that individual operators had committed actions which warranted revoca-tion or suspension of their licenses. Rather, it appeared that MP&L management was at fault for not properly administering RulP.- NRC also believed that although the Readtor Operators (RO) had not received all nf the training required, they had been previously examined and licensed by NRC and were believed to be competent.
[ REDERBS-419 PDR
.. .. .... Sectm h r 25, 1984 .i _ IwtMsda , Md. e .. . = _ 84-35 -
Mark E. IbshInvestigatcr, OIA Septatter 25, 1984 l
Tais DCCuwtNT IS *nopg ay, os NaC et LOANtO TO ANOTwim Act NCv if AND iTS CONTENTS Amt Not To at Dist assVTED CutsiDE TMt StClivsNC ACtNCY WITMOUT PL MMISSION OF TMt 08 pect 08 6NSPECTOa AND Avoston,
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k'ith respect t'6 the suspension or revocation of operator licenses at GGNS and I the resulting irnpact on the operating license, such actions would have, in '
effect, caused a revocation or suspension of it. He noted that there was fuel in the reactor which required the attention sof licensed operators even while the reactor was in a cold shutdown condition. Also, to off. load irradiated fuel would have required direct supervision by licensed operators. These factors were considered in the decision by NRC not to revoke or suspend operator licenses at GGNS.
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