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Discusses addl required info to better define potential for cracking in reactor vessel nozzles.

Accession Number: ML082180533

Date Released: Thursday, October 24, 2024

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• ML082180532 - Responds to FOIA request for 19 categories of documents re nuclear reactor events & safety problems.Forwards documents listed in App A. (15 page(s), 6/28/1982)
• ML082480647 - Discusses addl required info to better define potential for cracking in reactor vessel nozzles. (2 page(s), 5/5/1980)
• ML19281E000 - Evaluates LER 79-062/03L-1 re auxiliary feedwater sys pressure switches.Misapplication of static O-ring diaphragm type switches was limited to facility.Replacement w/stainless steel diaphragm switches seems adequate. (3 page(s), 12/7/1981)
• ML20023A454 - Responds to request to evaluate 811211 trip of two inservice auxiliary feedwater pumps from low suction.Installation of time relay on starting circuitry of motor driven auxiliary feedwater pumps will eliminate problem. (3 page(s), 2/24/1982)
• ML20027A692 - Informs that ESFAS relay failure reviewed to determine significant number of failures,safety consequences & qualifications of ESFAS relays.Failure considered simple isolated event & does not warrant further action. (2 page(s), 5/5/1981)
• ML20027A705 - Concludes that no addl actions are required re engineered safeguards relay failures.Various relays,including new Crydon relays,should be monitored as watch list items. Failures after Sept 1981 outage should be reviewed. (2 page(s), 8/28/1981)
• ML20027A745 - Requests that review be conducted on missile protection of safety-related sys at plants to assure adequate protection against generator rotor retaining rings as missiles. (15 page(s), 2/23/1982)
• ML20027A765 - Submits engineering evaluation re potential for air binding or degraded performance of BWR RHR sys pumps during LOCA recirculation phase.Air bubble generation will not adversely affect RHR pump performance.Gas release calculations encl. (8 page(s), 3/31/1982)
• ML20064J872 - Forwards evaluation of proposed Tech Specs change to operate facility at 2250 or 2000 psia.Proposed changes are acceptable.W/o encl. (6 page(s), 12/26/1979)
• ML20064J908 - Forwards NRC evaluation of use of four mixed oxide fuel assemblies for Cycle 10.Use of assemblies is acceptable w/no changes.For future cycles NRC will require increase in nuclear uncertainty re total peaking factor. (8 page(s), 3/11/1980)
• ML20064J926 - Forwards evaluation of facility for Cycle 6 operation.All Tech Spec changes & safety analyses required for 1500 MW approved. (34 page(s), 3/18/1980)
• ML20064J945 - Forwards RH Moore 800321 comments re NUREG-0572, "Review of LERs (1976-1978)," in response to C Michelson 800321 memo. (1 page(s), 3/28/1980)
• ML20064J947 - Discusses shortcomings in NUREG-0572, "Review of LERs (1976-1978)." (3 page(s), 3/21/1980)
• ML20064J967 - Forwards BL Cohen 800324 ltr & study re design adequacy of refueling water storage tank.Requests views. (1 page(s), 4/18/1980)
• ML20064K223 - Forwards 800505 memo re underclad cracking in reactor vessel nozzles.Review re safety aspects & compliance w/Section IX of ASME Code concludes that problem should not be included on generic issues list. (1 page(s), 7/17/1980)
• ML20064K287 - Submits evaluation of NUREG-0667, "Transient Response of B&W Designed Reactors." Recommends related studies be combined & specified Priority 2 items implemented by expanding an existing task in TMI action plan. (43 page(s), 8/8/1980)
• ML20064K288 - Forwards analysis & recommendations re plants w/o seismially qualified auxiliary feedwater sys.Concludes that shutdown of non-seismically qualified sys would not significantly reduce risk & proposes that more detailed study be initiated. (19 page(s), 8/8/1980)
• ML20064K341 - Forwards response to request for determination of licensing basis for reactor pressure vessel & containment fan cooler sys re FSAR requirements & current NRC criteria.Licensee must perform thermal & stress analysis of vessel. (6 page(s), 10/29/1980)
• ML20064K366 - Forwards Containment Sys Branch discussion paper comparing facility event w/current licensing criteria. (6 page(s), 11/7/1980)
• ML20064K454 - Describes sequence of events leading to containment flooding at Unit 2.Unit 3 should be allowed to return to power operation pending long-term actions.IE Info Notice 80-37 re containment cooler leaks & press release encl. (6 page(s), 11/13/1980)
• ML20064K594 - Forwards revision to evaluation of automatic air header dump on BWRs transmitted in 801208 memo.Revision restructures analysis supporting proposed change to BWR scram discharge sys. (15 page(s), 12/12/1980)
• ML20064K596 - Forwards as part of NUREG-0651 review,cost benefit analysis of radiation detectors on main steam lines to provide added diagnostic capability for PWR operator during steam generator tube rupture. (10 page(s), 12/15/1980)
• ML20064K601 - Discusses 810126 loss of annunciation event at facility. Caused by capacitor shorting.Licensee will review event as addressed in IE Bulletin 79-27, "Loss of Non-Class IE Instrumentation & Control Power Bus During Operation." (1 page(s), 1/30/1981)
• ML20064K605 - Comments on proposed change to STS re battery sys per 801230 request for review.Operating plants using battery sys not covered by STS should submit for approval equivalent surveillance program.Proposed STS & 801230 memo encl. (1 page(s), 1/8/1981)
• ML20064K609 - Informs that Safety Program Evaluation Branch does not develop requirements for non-RCS leakage detection.Branch evaluates proposed requirement adequacy in terms of cost-benefit analysis & possible adverse consequences. (2 page(s), 2/27/1981)
• ML20064K611 - Summary of 810107 operating reactor events meeting.W/o encl agenda. (3 page(s), 1/19/1981)
• ML20064K635 - Operating Reactor Event Memo 81-29 re cracking in several ASME Code Class 1 & Class 2 piping sys.Affected sys are isolation condenser,shutdown cooling,cleanup & LPCI subsystem.Defective sections are under repair. (4 page(s), 3/5/1981)
• ML20064K644 - Forwards summary of 810128 operating reactor events meeting. Next meeting scheduled 810204. (6 page(s), 2/4/1981)
• ML20064K654 - Summary of 810226 operating reactor events meeting re events which occurred since last meeting.Next meeting scheduled for 810311. (6 page(s), 3/4/1981)
• ML20064K686 - Discusses reactor coolant pump seal failure,in response to 800612 memo.Issue will be considered potential unresolved safety issue.Potential failure during station blackout may be taken up under Task Action Plan A-44. (13 page(s), 3/27/1981)
• ML20064K688 - Discusses IE daily rept for 810406 re alternate offsite source interlock w/emergency diesel generators at Unit 1. Licensee will propose mod to correct non-Class IE interlock preventing automatic operation of safety sys. (3 page(s), 4/21/1981)
• ML20064K741 - Forwards findings & recommendations for J Elin 810115 memo re requirements of preferred or offsite power sys. (4 page(s), 4/29/1981)
• ML20064K756 - Discusses evaluation of HPSI pump operability w/o svc water.Operability of HPSI pumps w/o svc water not adequately justified based on info submitted by licensee. (4 page(s), 5/22/1981)
• ML20064K760 - Comments on problem of flow blockage of cooling water sys by asiatic clams (ref IE Bulletin 81-03).Problem considered potentially serious common mode failure.Guidance for proposed stepwise investigation provided. (3 page(s), 5/20/1981)
• ML20064K777 - Discusses inoperability of instrumentation due to extreme cold weather.IE should issue suppl to IE Bulletin 79-24 requesting Tech Spec changes which require daily surveillance during extreme weather. (5 page(s), 6/15/1981)
• ML20064K783 - Discusses Ofc of Nuclear Regulatory Research comments supporting conclusions of Mar 1981 ofc rept re safety concerns associated w/pipe breaks in PWR scram sys. Shortcomings of analysis listed. (3 page(s), 6/11/1981)
• ML20064K787 - Forwards Nuclear Safety Analysis Ctr/INPO rept, "Significant Event Evaluation & Info Network" & background info re review of sreening & preliminary evaluation program,for comment. (15 page(s), 6/22/1981)
• ML20064K791 - Informs that manipulation of control switches for two trains of circulating water sys resulted in tripping of two circulating water pumps located in intake structure.FBI investigated & found no evidence of who operated switches. (1 page(s), 6/24/1981)
• ML20064K793 - Provides info as discussed at ACRS 810507 meeting re control sys failures that could cause or accelerate nuclear power facility accidents.Comments from plant sys unit encl. (5 page(s), 6/24/1981)
• ML20064K810 - Discusses findings gathered during 810617 site visit re facility loss of RHR capability during Apr & May 1981.Util has committed to mod of wash screen wash sys by 1983. Attendance list,chlorinator outage info & drawings encl. (19 page(s), 7/22/1981)
• ML20064K814 - Discusses prioritization of new requirements for PWR feedwater line cracks.Remedial measures development should be responsibility of industry w/approval of design changes responsibility of NRR. (26 page(s), 6/30/1981)
• ML20064K823 - Forwards details re 810717 ignition of gaseous waste decay tank at facility.Event should be included in Commission third quarterly AO rept to Congress for 1981. (3 page(s), 8/6/1981)
• ML20064K828 - Discusses review of LERs re setpoint drift occurrences for Barton Model 288 instrument.Provides recommendations for NRR. (2 page(s), 7/20/1981)
• ML20064K839 - Forwards marked-up draft Commission paper re integrated operational experience reporting sys for concurrence.Draft advance notice of proposed rulemaking & Congressional ltrs encl. (14 page(s), 7/15/1981)
• ML20064K842 - Forwards concurrence on NUREG-0803, "Generic Safety Evaluation re Integrity of BWR Scram Sys Piping." Any significant changes will be provided for consideration. (3 page(s), 7/30/1981)
• ML20064K856 - Forwards highlights of 810810 meeting re reactor water level monitoring,meeting attendance list & draft ltr to util proposing resolution of vessel monitoring requirements for TMI-1 restart. (10 page(s), 9/1/1981)
• ML20064K860 - Advises that review of proposed draft suppl to IE Bulletin 81-02, "Failure of Gate Type Valves to Close Against Differential Pressure," yielded no substantive comments. (1 page(s), 8/6/1981)
• ML20064K866 - Forwards safety evaluation re mod to correct inadvertent opening of atmospheric dump valves on BWR plants during loss of instrument control sys non-nuclear instrumentation power. (2 page(s), 9/4/1981)
• ML20064K872 - Recommends memo be prepared requesting Ofc of Nuclear Regulatory Research to initiate preparation of proposed rule change on high priority basis for General Design Criteria 4. (2 page(s), 8/26/1981)
• ML20064K881 - Comments on proposed IE circular re torque switch jumpers for safeguards svc motors.More appropriate title could be "Torque Switch Jumpers for Safeguards Svc Valve Motor Control Circuits." Marked-up circular encl. (4 page(s), 8/28/1981)
• ML20064K886 - Immediate action memo re desiccant contamination of air lines.Recommends issuance of bulletin requiring all licensees experienced w/air sys contamination to furnish info. (2 page(s), 9/15/1981)
• ML20064K888 - Requests addl info re loss of offsite power event on 810914. (1 page(s), 9/18/1981)
• ML20064K896 - Comments on J Austin 810306 note re purge & vent valve assembly operability during expected accident conditions & potential problems should valve closure be delayed. (4 page(s), 9/24/1981)
• ML20064K899 - Requests addl info from util re 810914 safety injection & natural circulation event during performance of loss of control room test.Info needed includes data just prior to trip & up to 1-h following event. (1 page(s), 9/22/1981)
• ML20064K901 - Discusses 810625 memo re approach to sys interactions in LWRs.No comments were developed which would need to be assimilated into interim guidance.Author ofc will offer assistance w/use of sequence coding & search procedure. (1 page(s), 9/2/1981)
• ML20064K905 - Forwards background statement & discussion of process & policies established for Ofc of Analysis & Evaluation of Operational Data repts.Future repts sent for peer review will be complete & include conclusions & recommendations. (3 page(s), 9/2/1981)
• ML20064K910 - Forwards summary of activities re PWR primary sys voids, initiated by Ofc for Analysis & Evaluation of Operational Data. (2 page(s), 9/30/1981)
• ML20064K912 - Forwards engineering evaluation rept on shutdown cooling sys HX failures which occurred in late Aug 1981.Failures diagnosed as fatigue failures due to flow induced vibration. Recommends event not be considered AO. (7 page(s), 10/15/1981)
• ML20064K920 - Responds to inquiry into status of BWR scram discharge vol pipe break safety concerns.NUREG-0803 contains guidance for resolving outstanding issues on plant by plant basis. (1 page(s), 10/2/1981)
• ML20064K923 - "Pressure Boundary Degradation Due to Pump Seal Failure of Arkansas Nuclear One." (6 page(s), 11/3/1981)
• ML20064K927 - Forwards draft proposed rule & reg guide re new LER sys,for review.Comments should indicate whether improved sys will meet needs for operational safety data. (24 page(s), 10/6/1981)
• ML20064K932 - Responds to 810828 memo re draft rept, "Compressed Air & Backup Nitrogen Sys in Nuclear Power Plants." Forwards comments re areas where addl work is suggested prior to final publication. (3 page(s), 10/7/1981)
• ML20064K939 - Recommends comprehensive assessment of plant operating conditions to determine specific predetermined time related sequences of occurrence to emergency buses.SRP should be revised re design features. (4 page(s), 10/16/1981)
• ML20064K941 - Comments on draft IE circular re MSIV failures to close. Problem w/control air for MSIV may be part of larger spectrum of problems for many valves. (1 page(s), 10/1/1981)
• ML20064K950 - Requests Div of Sys Integration review SER section on leak rate & leak rate detection criteria.Conclusions should be limited to subj plants but general comments would be appreciated. (3 page(s), 10/9/1981)
• ML20064K954 - Discusses LER 81-002/03X-1,dtd 810430,re inoperable solenoid valves.Cause found to be impurities in internal mechanisms. Valves replaced w/Keane valves & solenoids w/higher strength coil.Findings to be incorporated in instrument air study. (3 page(s), 11/10/1981)
• ML20064K959 - Operating Reactor Event Memorandum 81-32:on 810903,control room operator manually tripped reactor after transient from 88% power initiation by steam generator flow & level oscillator.Caused by regulated power supply failure. (9 page(s), 10/31/1981)
• ML20064K962 - "Rept on Millstone Unit 2 Loss of 125-Volt DC Bus Event on 810102." (26 page(s), 11/30/1981)
• ML20064K966 - Comments on draft ORNL 810930 rept, "Evaluation of Events Involving Svc Water Sys in Nuclear Power Plants," per 811020 request.Several recommendations made w/o sufficient justification to merit serious consideration. (1 page(s), 11/10/1981)
• ML20064K979 - Provides info re better means of coordinating & reducing duplication in screening LERs & evaluation efforts. Supporting info encl. (8 page(s), 11/9/1981)
• ML20064K989 - Forwards summary of NRR,NMSS & IE actions resulting from Ofc of Analysis of Evaluation & Operational Data activities, in response to recommendations contained in case studies & engineering evaluations. (4 page(s), 11/12/1981)
• ML20064K996 - Recommends that proposed LER rule including existing & proposed reporting requirements & coordination plan be sent to Commission for consideration. (1 page(s), 11/24/1981)
• ML20064K998 - Requests assistance of Ofc of Nuclear Regulatory Research to complete editorial & administrative activities necessary to issue encl draft reg guide. (1 page(s), 11/17/1981)
• ML20064L002 - Forwards description of events & resulting action re high circulating current associated w/inverter output due to lack of circuit tuning.IE circular or info notice should be issued to address issue. (4 page(s), 12/10/1981)
• ML20064L009 - Discusses LER 81-66 re facility diesel generator jacket water temp control valve & manual bypass valve.No further action recommended. (1 page(s), 12/7/1981)
• ML20064L017 - Comments on NRC evaluation of WCAP-9558 & WCAP-9787,re excluding asymmetric blowdown loads in plant design based on leak-before-break acceptance criteria.Safety evaluation using subj basis will require regulation changes. (21 page(s), 12/2/1981)
• ML20064L029 - Provides background info re FIN B-0445, "Analysis of Reliability Data From Nuclear Power Plants." Review of 811113 in-plant data program (FIN B-0445) progress review meeting encl. (8 page(s), 12/2/1981)
• ML20064L032 - Forwards Chairmen Palladino & Ahearne 811110 & 05 memos re Commission briefing on NRC program for reactor operational experience evaluation. (1 page(s), 11/25/1981)
• ML20064L037 - Responds to 811105 memo re functions of Ofc for Analysis & Evaluation of Operational Data.Commission briefing should cover NRC program for reactor operational experience evaluation. (1 page(s), 11/10/1981)
• ML20064L042 - Suggests Commission be briefed on current & projected distribution of Ofc of Analysis & Evaluation of Operational Data resources thru FY84. (4 page(s), 11/5/1981)
• ML20064L045 - Forwards draft FR notice re 810903 AO on failure of high pressure safety injection sys. (9 page(s), 12/8/1981)
• ML20064L048 - Forwards INPO 811110 ltr commenting on draft proposed rule to modify & codify existing LER reporting requirements. Comment 1 should be considered during review of reporting requirements. (1 page(s), 12/11/1981)
• ML20064L051 - Concurs w/procedures for developing NRC research program,in response to NRC 811112 memo.Requests that all research projects collection,storage,analysis or evaluation of operational safety data be sent for review & concurrence. (1 page(s), 11/24/1981)
• ML20064L056 - Recommends issuance of info notice to inform licensees of problems w/ALOYCO swing check valves as encountered at facility.Abnormal wear reported in LER 81-037. (5 page(s), 12/23/1981)
• ML20064L064 - Endorses Committee to Review Generic Requirements recommendation that appropriate ofcs coordinate outline of reporting requirements interrelated w/draft proposed LER rule.Identifies documents re reporting requirements. (2 page(s), 12/8/1981)
• ML20064L067 - Discusses loss of HPI lube oil cooling at facility & failure of monthly operability test of HPI to detect clogging of qualified lube oil coolers.Test deficiency may be more critical than event.Issue to be addressed by IE. (3 page(s), 1/13/1982)
• ML20064L081 - "Evaluation of Events Involving Svc Water Sys in Nuclear Power Plants," draft. (67 page(s), 1/31/1982)
• ML20064L084 - Forwards proposed Commission paper requesting approval of proposed rule which would modify & codify existing LER sys. (1 page(s), 12/30/1981)
• ML20064L092 - Notifies that inadvertent isolation of containment for coolers sys due to radiation alarms is not likely.LER re svc water isolation valves found closed to containment fan coil units does not merit further consideration. (3 page(s), 1/21/1982)
• ML20064L134 - Recommends explicit verification that seismic qualification for all protective devices used in control & protection circuitry for diesel generator units performed w/devices in energized/de-energized & tripped/nontripped states. (2 page(s), 2/24/1982)
• ML20064L148 - Discusses repetitive failures of emergency feedwater flow value as reported in LERs due to valve operator hydraulic problems.LERs encl. (76 page(s), 2/24/1982)
• ML20064L152 - "Evaluation of Events Involving Unplanned Boron Dilutions in Nuclear Power Plants." (37 page(s), 3/31/1982)
• ML20064L163 - Recommends that any guidelines developed for RCS safety valve setpoint testing be applied to steam generator safety valves on PWRs. (5 page(s), 2/22/1982)
• ML20064L169 - "Evaluation of Events Involving Decay Heat Removal Sys in Nuclear Power Plants." (101 page(s), 3/31/1982)
• ML20064L174 - Forwards memo re 790413 Barseback reactor generator rotor retaining ring failure.Caused by brittle fracture at regions of stress concentration & corrosion cracking induced by environ. (1 page(s), 3/16/1982)
• ML20064L178 - Forwards memo re equipment malfunctions during 820114 turbine load reduction operation.Following review of final rept from licensee & Region 1,will complete evaluation of event for generic implications. (1 page(s), 3/15/1982)
• ML20064L182 - Discusses sequence of events of Salem 820114 load reduction transient,operator action,lessons learned & future remedial actions to be taken. (2 page(s), 2/22/1982)
• ML20064L187 - Forwards "Recommendations for Improving NRC Incident Response Technical Assessment Capability." Recommendations consistent w/NRC 820104 ltr re NUREG-0845.List of recommendations encl. (3 page(s), 3/4/1982)
• ML20064L191 - "Recommendations for Improving NRC Incident Response Technical Assessment Capability." (77 page(s), 2/28/1982)
• ML20064L247 - Forwards deficiency rept re failure of control rod drive hydraulic sys scram pilot valves.Problems w/voltage of reactor protection sys power supplies adequately addressed. (2 page(s), 3/31/1982)
• ML20064L262 - Recommends prompt attention be given to problem of reactor coolant pump closure stud corrosion detected at facilities. Response by 820415 requested. (3 page(s), 3/24/1982)
• ML20064L274 - Advises that proposed circular, "Contamination of Air Serving Safety-Related Equipment," reviewed.Followup to IE Notice 81-38 or IE bulletin should be sent requesting info assessment of plant air supply sys. (2 page(s), 4/1/1982)
• ML20065E235 - Forwards review of B&W ltr rept on effect of fuel rod bowing on DNBR.Proposed method acceptable for licensing calculations. (6 page(s), 7/25/1979)
• ML20065E259 - Notification of ACRS LER Subcommittee 800422 meeting in Washington,DC.Schedule & background info encl. (3 page(s), 4/14/1980)
• ML20065E267 - Outlines INPO & Ofc for Analysis & Evaluation of Operational Data 800311 & 20 reviews of nuclear plant operating data. Related info encl. (6 page(s), 3/26/1980)
• ML20065E275 - "Status Rept,Ofc for Analysis & Evaluation of Operational Data." (10 page(s), 3/20/1980)
• ML20065E292 - Advises that ACRS 800422 meeting w/LER Subcommittee & NRC will include discussion of status organization & planned activities of Ofc for Analysis & Evaluation of Operational Data & NRC program for collection of data. (2 page(s), 3/21/1980)
• ML20065E307 - Confirms telcon re 800422 presentation on INPO w/ACRS LER Subcommittee.Member requested to make presentation on status of organization & plans for future activities re use & evaluation of operational data from nuclear plants. (1 page(s), 4/14/1980)
• ML20065E334 - Recommends ACRS action on recent LERs re HPCI failure to auto start after MSIV failure & single cooling supply line on RHR pump motors. (1 page(s), 6/13/1980)
• ML20065E354 - Discusses failures of HPCI & RCIC sys subsequent to 790603 event culminating in 790627 loss of both sys. (2 page(s), 9/6/1979)
• ML20065E375 - Forwards PNO-79-139 re failure of RCIC & HPCI sys following low water level reactor scram. (1 page(s), 6/29/1979)
• ML20065E396 - Requests detailed rept on PNO-79-139 re failure of backup core cooling sys.Generic implications required. (1 page(s), 6/7/1979)
• ML20065E429 - Reiterates 790607 request for detailed rept re failure of backup core cooling sys per PNO-79-139 & PNO-79-196. Response requested by 790703. (1 page(s), 7/2/1979)
• ML20065E466 - Forwards response to 790607 request for info re failure of backup cooling sys.Corrective measures will be followed to assure reliable state of operational readiness. (5 page(s), 7/2/1979)
• ML20065E519 - Discusses problems w/LER data reporting & recording sys. Form is not designed for subsequent use of data for statistical analyses.Draft notes encl. (8 page(s), 7/1/1980)
• ML20065E748 - Discusses potential problem re Sequoyah reactor pressure nozzle,supplementing 800222 memo.Underclad cracks found by use of ultrasonic equipment.Addl items of recent origin discussed.Related info encl. (9 page(s), 2/28/1980)
• ML20065E790 - Discusses evaluation of applicability of proposed new requirement of Class IE station batteries.Div of Licensing should retain responsibility for further exploration of matter in course of licensing reviews. (2 page(s), 2/28/1980)
• ML20065E806 - Forwards comments on NRC LER sys.W/o encl. (1 page(s), 7/22/1980)
• ML20065H043 - Requests info re LER 80-111/03L-0 concerning isolation of HPCI sys at facility.Nature of nonrepetitive event questioned. (2 page(s), 9/16/1980)
• ML20065H047 - Discusses NRC procedures for reviewing LERs,in response to request during 245th ACRS meeting on 800904-06.Reporting requirements require revision to eliminate unneeded matl. (3 page(s), 9/23/1980)
• ML20065H057 - Responds to 800523 request re action by Ofc for Analysis & Evaluation of Operational Data on two specific LERs.Ofc currently working on more significant safety areas. (1 page(s), 9/23/1980)
• ML20065H063 - Forwards LER 80-20/03L & RO 269/80-9 re failure to open auxiliary feedwater valve & failure of fire detection sys,respectively.Addl attention may be warranted. (1 page(s), 5/23/1980)
• ML20065H084 - Submits review of IE insps of operating PWRs related to followup actions identified in NUREG-0138.Sensitivity analyses recommended. (12 page(s), 12/28/1977)
• ML20065H094 - Notification of ACRS LER Subcommittee 801120 meeting in Washington,DC to discuss progress toward improving NRC use of operational data. (1 page(s), 11/10/1980)
• ML20065H100 - Notification of ACRS LER Subcommittee 801120 meeting in Washington,DC.Schedule encl. (2 page(s), 11/10/1980)
• ML20065H103 - Submits evaluation of recommendations contained in NUREG- 0651, "Evaluation of Steam Generator Tube Rupture Events." Licensees should investigate other techniques to more rapidly determine damage. (26 page(s), 2/17/1981)
• ML20065H107 - Press release discussing dissemination of info to all nuclear power plants re leakage of river water into containment. (2 page(s), 10/27/1980)
• ML20065H109 - Summary of 810311 operating reactor events meeting. Assignment of followup review responsibility discussed. Related info encl. (5 page(s), 3/13/1981)
• ML20065H116 - Summary of 810318 operating reactor events meeting. (4 page(s), 3/24/1981)
• ML20065H120 - Summary of 810325 operating reactor events meeting. (4 page(s), 3/26/1981)
• ML20065H146 - Forwards draft rept, "Potential for Water Hammer During Restart of RHR Pumps for BWR Nuclear Plants." (1 page(s), 3/31/1981)
• ML20065H149 - "Potential for Water Hammer During Restart of RHR Pumps for BWR Nuclear Plants." (14 page(s), 3/31/1981)
• ML20065H159 - Forwards preliminary rept, "Initial Consideration of Potential for Water Hammer in Steam Condensing Mode of RHR Sys Operation for BWR Nuclear Plants." (1 page(s), 3/31/1981)
• ML20065H168 - "Initial Consideration of Potential for Water Hammer in Steam Condensing Mode of RHR Sys Operation for BWR Nuclear Plants." (11 page(s), 3/31/1981)
• ML20065H217 - Summary of 810408 operating reactor events meeting. (4 page(s), 4/15/1981)
• ML20065H219 - Discusses 810225 simultaneous closure of recirculation pump discharge valves.Event occurred while station personnel were attempting to remove ground associated w/A div of 125-volt dc subsystem. (2 page(s), 4/17/1981)
• ML20065H233 - Discusses proposed watch list item,potential common mode failure of diesel generators.AEOD sequence coding & search procedure (SCSP) will be revised to include "fire" as searchable item to enable monitoring of similar events. (2 page(s), 4/24/1981)
• ML20065H243 - Speech entitled "Assessment of Operational Safety Data in NRC" presented at 810427-29 Fourth Symposium on Training of Nuclear Facility Personnel in Gatlinburg,TN. (24 page(s), 4/27/1981)
• ML20065H256 - Summary of 810422 operating reactor events meeting. Related info encl. (10 page(s), 4/29/1981)
• ML20065H263 - "Power Reactor Events,Jan-Feb 1981," Vol 3,Number 2. (16 page(s), 5/31/1981)
• ML20065H323 - Summary of 810506 operating reactor events meeting. (9 page(s), 5/12/1981)
• ML20065H326 - Summary of 810513 operating reactor events meeting. (6 page(s), 5/18/1981)
• ML20065H341 - Forwards IE Bulletin 81-03, "Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel)," for issuance on 810410. (2 page(s), 4/8/1981)
• ML20065H363 - Summary of 810520 operating reactor events meeting. (7 page(s), 5/27/1981)
• ML20065H384 - Summary of 810603 operating reactor events meeting. (7 page(s), 6/9/1981)
• ML20065H431 - Forwards comments & questions re GE response to Ofc for Analysis & Evaluation of Operational Data safety concerns w/ pipe breaks in BWR scram sys,in response to D Eisenhut 810603 request. (2 page(s), 6/14/1981)
• ML20065H444 - Summary of 810610 operating reactor events meeting. (5 page(s), 6/17/1981)
• ML20065H468 - Summary of 810617 operating reactor events meeting. (4 page(s), 6/23/1981)
• ML20065H512 - Forwards summary of NUREG/CR-1682, "Electrical ref Insulators in Reactor Accident Environ," used as ref in Ofc of Nuclear Regulatory Research comments on safety concerns re pipe breaks in BWR scram sys. (5 page(s), 6/26/1981)
• ML20065H526 - Summary of 810708 operating reactor events meeting.Next meeting scheduled on 810715. (8 page(s), 7/13/1981)
• ML20065H564 - Discusses plans for managing NRPDS per 810708 telcon.Data & repts from data base will continue to be made available to NRC.Meeting scheduled on 810721. (5 page(s), 7/9/1981)
• ML20065H584 - Summary of 810723 operating reactor events meeting.Next meeting scheduled for 810805. (8 page(s), 7/29/1981)
• ML20065H624 - "Power Reactor Events,Mar-Apr 1981," Vol 3,Number 3. (18 page(s), 8/31/1981)
• ML20065H655 - "Operational Safety Data Review," Chapter 0515. (8 page(s), 8/12/1981)
• ML20065H662 - Summary of 810806 operating reactor events meeting.Related info encl.Next meeting scheduled for 820812. (16 page(s), 8/10/1981)
• ML20065H674 - Summary of 810819 operating reactor events meeting.Status of followup review responsibility assignments encl. (5 page(s), 8/24/1981)
• ML20065J175 - Forwards draft rept entitled "Characteristics of LER Reporting Sys." (1 page(s), 8/31/1981)
• ML20065J180 - Draft rept entitled "Characteristics of LER Reporting Sys." (43 page(s), 8/28/1981)
• ML20065J197 - Advises that SECY 81-494 will be discussed at 810909 subcommittee meeting on evaluation of LERs. (2 page(s), 9/2/1981)
• ML20065J216 - Provides presentation schedule for 810909 subcommittee meeting for evaluation of LERs. (3 page(s), 9/2/1981)
• ML20065J239 - Comments on LER Subcommittee 810909 meeting.Ofc for Analysis & Evaluation of Operational Data could benefit from analytical models used in other fields & other stages of data analysis. (2 page(s), 9/11/1981)
• ML20065J248 - Discusses methods for preventing recurrence of LERs. Attention should be given to matl suppliers & architect engineers as LER originators. (1 page(s), 9/6/1981)
• ML20065J308 - Forwards draft proposed rule re integrated operational experience reporting,for comment. (9 page(s), 9/18/1981)
• ML20065J316 - Forwards SECY-81-505 re systematic assessment of licensee performance,first rept on licensee assessments.W/o encl. Contains facility ratings for operating power reactor licensees & CP holders. (1 page(s), 9/21/1981)
• ML20065J325 - Summary of 810916 operating events meeting.List of attendees encl. (9 page(s), 9/21/1981)
• ML20065J335 - Forwards D Moeller & Z Zudans comments on LER sys. (1 page(s), 9/30/1981)
• ML20065J345 - Comments on LER reporting sys.LER cover sheets contain misleading info re facility in question.LERs should not be grouped in packets w/o appropriate subj heading. (1 page(s), 9/19/1981)
• ML20065J358 - "Power Reactor Events,May-June 1981," Vol 3,Number 4. (16 page(s), 10/31/1981)
• ML20065J396 - Topical rept evaluations of Revision 2 to WCAP-9558, "Mechanistic Fracture Evaluation of Reactor Coolant Pipe..." & WCAP-9787, "Tensil & Toughness Properties of Primary Piping Weld Metal for Use in..." (26 page(s), 6/28/1982)
• ML20065J413 - Summary of 811007 operating reactor events meeting.Status of previous assignments encl. (9 page(s), 10/13/1981)
• ML20065J446 - Summary of 811021 operating reactor events meeting.List of attendees,events discussed & assignments encl. (6 page(s), 10/29/1981)
• ML20065J454 - Discusses proposed rule dealing w/LER sys.Features will include compatibility of sys w/10CFR50.72. (1 page(s), 11/2/1981)
• ML20065J461 - Forwards info re selection of LERs worthy of AO rept status. (2 page(s), 10/24/1981)
• ML20065J473 - Summary of 811028 operating reactor events meeting.List of attendees,events discussed & review assignments encl. (5 page(s), 11/3/1981)
• ML20065J480 - Revised draft rept, "Compressed Air & Backup Nitrogen Sys in Nuclear Power Plants." (80 page(s), 11/13/1981)
• ML20065J486 - Forwards background matl for 811208 reactor operations subcommittee meeting on proposed rule & reg guide re LER rulemaking. (1 page(s), 11/19/1981)
• ML20065J492 - Draft Reg Guide 1.XXX,Revision 3, "LER Sys." (22 page(s), 11/16/1981)
• ML20065J515 - Discusses Zudans comments re ACRS LER subcommittee 810909 meeting.Change in connectivity function of sequence coding proposed.Fundamental change involved. (1 page(s), 11/20/1981)
• ML20065J534 - Summary of 811112 operating reactor events meeting.List of attendees,events discussed & review assignments encl. (6 page(s), 11/23/1981)
• ML20065J551 - Discusses 811107 ltr re LERs & AO repts per SECY 81-598 & SECY 81-602.Meeting to discuss proposed LER rule scheduled for 811208. (2 page(s), 11/24/1981)
• ML20065J570 - Requests info re notification of ACRS concerning proposed rule change for immediate notification of significant events per SECY 81-598. (1 page(s), 11/7/1981)
• ML20065J585 - "Summary of Ofc of Analysis & Evaluation of Operational Data Analysis & Evaluation of Browns Ferry Unit 3 Partial Failure to Scram Event of 800628." (22 page(s), 11/30/1981)
• ML20065J594 - "Background Reading for Discussion of Program & Methods for Screening & Analysis of Operational Info at NRC," presented to IAEA Advisory Group on 811123-27. (25 page(s), 11/23/1981)
• ML20065J623 - Summary of 811202 operating reactor events meeting.List of attendees,events discussed & status of previous assignments encl. (8 page(s), 12/7/1981)
• ML20065K409 - Summary of 811216 operating reactor events meeting.List of attendees,events discussed & status of assignments encl. (10 page(s), 12/28/1981)
• ML20065K424 - "Power Reactor Events,Jul-Aug 1981," Vol 3,Number 5. (14 page(s), 1/31/1982)
• ML20065K453 - Discusses Zudans input re sequence coding & search sys,per 810930 memo.Implementation of approach would require major revision to sys. (1 page(s), 10/22/1981)
• ML20065K548 - Forwards comments re potential consequences of load drop in LWRs,providing understanding & background of scope of current regulatory review for accidents. (13 page(s), 2/16/1982)
• ML20065K551 - Summarizes investigation of LER 50-336/81-26 re relative frequency of valve overtravel abnormalities that could result in potential centrifugal pump runout exceeding NPSH. (4 page(s), 2/22/1982)
• ML20065K557 - Discusses inadequate switchgear cooling at facility. Implications of event suggest that loss of ventilation sys could have potential safety significance requiring addl generic review by NRC. (2 page(s), 2/23/1982)
• ML20065K560 - Responds to request for review of LERs on steam generator leaks.Distribution of problems from 1976 to 1981 provided. (3 page(s), 3/5/1982)
• ML20065K569 - Responds to 820324 request for assessment of reactor coolant pump studs.General rept on all mechanisms of bolting degeneration in progress.Visual insp of reactor coolant sys bolts recommended. (5 page(s), 4/5/1982)
• ML20069G582 - Comments on "Learning Function in Nuclear Reactor Operation & Implications for Siting Policy." Analysis does not support finding that adding reactors to existing sites enhanced learning. (5 page(s), 3/15/1982)