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Category:NRC Generic Letter
MONTHYEARML0612805172006-05-10010 May 2006
NRC Generic Letter 2006-XX: Post-fire Safe-shutdown Circuit Analysis Spurious Actuations
NRC Generic Letter 2006-012006-01-20020 January 2006
NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications
ML0823509351999-06-0303 June 1999
Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal
NRC Generic Letter 1998-011999-01-14014 January 1999
NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
NRC Generic Letter 1998-051998-11-10010 November 1998
NRC Generic Letter 1998-005: Boiling Water Reactor Licensees Use of BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds
ML0311101601998-08-0303 August 1998
Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data
NRC Generic Letter 1998-041998-07-14014 July 1998
NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-021998-05-28028 May 1998
NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NRC Generic Letter 1997-061997-12-30030 December 1997
NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-051997-12-17017 December 1997
NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
ML0312007011997-10-0808 October 1997
Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions
NRC Generic Letter 1997-041997-09-30030 September 1997
NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
NRC Generic Letter 1997-021997-05-15015 May 1997
NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
NRC Generic Letter 1997-011997-04-0101 April 1997
NRC Generic Letter 1997-001: Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Clossure Head Penetrations
NRC Generic Letter 1995-061997-01-31031 January 1997
NRC Generic Letter 1995-006: Changes in Operator Licensing Program
NRC Generic Letter 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves1996-09-18018 September 1996
NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
NRC Generic Letter 1996-041996-06-26026 June 1996
NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 1996-021996-02-13013 February 1996
NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat
NRC Generic Letter 1996-031996-01-31031 January 1996
NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
NRC Generic Letter 1989-101996-01-24024 January 1996
NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors
NRC Generic Letter 1996-011996-01-10010 January 1996
NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits
NRC Generic Letter 1995-101995-12-15015 December 1995
NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
ML0310701501995-10-31031 October 1995
Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval
NRC Generic Letter 1993-031995-10-20020 October 1995
NRC Generic Letter 1993-003: Verification of Plant Records
NRC Generic Letter 1981-351995-08-31031 August 1995
NRC Generic Letter 1981-035: Safety Concerns Associated with Pipe Breaks in the BWR Scram System
NRC Generic Letter 1995-071995-08-17017 August 1995
NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
NRC Generic Letter 1995-051995-08-0303 August 1995
NRC Generic Letter 1995-005: Voltage Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking
NRC Generic Letter 1995-031995-04-28028 April 1995
NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes
NRC Generic Letter 1995-041995-04-28028 April 1995
NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues
NRC Generic Letter 1995-021995-04-26026 April 1995
NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59
ML0312004431994-09-0202 September 1994
Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data
ML12047A2431994-09-0202 September 1994
Withdrawn - NRC Generic Letter 94-04: Voluntary Reporting of Additional Occupational Radiation Exposure Data
NRC Generic Letter 1994-031994-07-25025 July 1994
NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
NRC Generic Letter 1994-021994-07-11011 July 1994
NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors
NRC Generic Letter 1994-011994-05-31031 May 1994
NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators
NRC Generic Letter 1993-081993-12-29029 December 1993
NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits
NRC Generic Letter 1993-071993-12-28028 December 1993
NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans
NRC Generic Letter 1993-061993-10-25025 October 1993
NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas.
NRC Generic Letter 1993-051993-09-27027 September 1993
NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
NRC Generic Letter 1993-041993-06-21021 June 1993
NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f)
NRC Generic Letter 1993-021993-03-23023 March 1993
NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication
NRC Generic Letter 1993-011993-03-0303 March 1993
NRC Generic Letter 1993-001: Emergency Response Data System Test Program
NRC Generic Letter 1992-091992-12-31031 December 1992
NRC Generic Letter 1992-009: Limited Participation by NRC in IAEA International Nuclear Event Scale
NRC Generic Letter 1992-081992-12-17017 December 1992
NRC Generic Letter 1992-008: Thermo-Lag 330-1 Fire Barriers
NRC Generic Letter 1992-071992-10-20020 October 1992
NRC Generic Letter 1992-007 - Office of Nuclear Reactor Regulation Reorganization
NRC Generic Letter 1983-281992-10-0707 October 1992
NRC Generic Letter 1983-028, Supplement 1: Required Actions Based on Generic Implications of Salem ATWS Events.
ML0311304121992-09-16016 September 1992
Withdrawn NRC Generic Letter 1992-006 - Operator Licensing National Examination Schedule
NRC Generic Letter 1992-051992-09-0404 September 1992
NRC Generic Letter 1992-005: NRC Workshop on the Systematic Assessment of Licensee Performance (SALP) Program
NRC Generic Letter 1992-041992-08-19019 August 1992
NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
NRC Generic Letter 1992-031992-03-19019 March 1992
NRC Generic Letter 1992-003 - Compilation of Current Licensing Basis: Request for Voluntary Participation in Pilot Program
2006-05-10
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u*_mitD SrAn NUCLEAR REGULATORY
COMMISSION
WASH itaTCT0F 0. Q 3KW* ad..wq. JAN7t !it ALL LICMNSUS OF OFEPRATING
PLANTS AND OLSEiS OF CO4NSTRUCT&CN
P EN1Ts GCenzlenen:
jUSMECT: ANALYSIS, MNCLUSICNS, AND RECM-1GENDAITNS
CONC.iRN'(G
CPS.A7CR LIU0NSITIG (OENEUzC LETTER .No. °1-02)In A fetter da:ed .1arcm 2a, 198. from H. R. Denton we Inforned you of the revised cri:eria to be used by the staff in evaluating reactor operator training and licensing tat. could be imolemented under the curren-regula:lons.
we also advised you tna: Conmiss fan review in the area of oper2:ar :raining and Qua;ificatlon was continuing and it could be expec-td to result in additional criteria.As par-. of our con:tnulng review. we Issued a contrict (xRR-8O-ll7)
to Analysis I Tecnoloy, Inc., to concuc: i study of :ne requirements for operator licensing.
Analyss. I Techinology submieted their rtport to US on Yovemer 0,G 19£0 (NURES/CR-175O).
This report provides an indecendent persnec:ive
- o tne U.S. Nuclear Regulatory Comnmssion regarding the resuirements and orac:1ces for control room ooera:or licensing.
Analysts, conclusions and recIM ndatiOns Are provIded In the following areas:* Selec:ton, training and certification of control room ocertors .* E.'ec:iveness of the ?XRC operator licensing program,* .Me*hccs *^ assare continued
- omFe:ence of ocenor's,* Yetncds for' aintalming a ilghlj Mtivated and dedicated ocerntor work force.* "Pgracing zf presen:ty licensed operatzrs to mnee:.mrzcosed rtc u I -re n = .* TrAining nc ;uallfication of non-lfcersed ocerating,.main:enance and tec.nnical succor- ersonnel,* 'ua1fications of Operator Licensing Iranci (CLB) examiners.
and* Or;ani:atfon of the CL3.3ased on our review of :.his report we intend to develco additional criteria-fcr te recuirements for operiatr lfcensing.
de woul I oorec'lae it if ycu would review this report and ofer any Zcrnents ycu :ellfeve accrzcria:e to assist us in the develocent
- f 'imcrovegmes f.in:ne Ocers:zr hIItns'ng
- rogrim. Ytur rtszcnse :z :tis recues: 'f dC':nt.r.fs 1 @52I 30 /8
3" T V.S'. )0 Atomic LergyCo-miuso grats lcense. December.
First commer*c power generated 1073 -JUJar. Ytnor rudl&., don lnk shuts plant dow.u AUCs Leab in esmeamenentr tubes cause shutdow.1174 -Consumers Power CM.slips Qmillion lawsit on five T firm thst bult ador equpped L 1175 -Aprik Plant sun up a after cmaoth. shutdow. JuIy Lowievel radloacltve waer'.a J acctdeully released into 1k.December.
Three-month shut.down :o refuel nd check gener torptps.-1171- Starch.i Couers dElsd.p punes four workers who reftue to work It plat they claim It Is unsafe. October. Shutdown to m r pairltea sIT7 -?ant's available cape.*eqnpment August: ower ELai f gudergant QIII and-bsan wrl for ht 17 per.19791-Septemben Elogt-month shutdw for rtfueling.
maIntenance and testing Novem-ber.NRC fines Corsumers SSO.000 for permttng two mdlUon-con.
tol valves to be open for 18 mont tm -JZul &ln-edy Shutdown to rplace filter caslng 'huzu error caum crucial watercool.
tg contrl valve to be left open for 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> August Two accidental releses of ndlobctlyt- tyac wetk apart. December .?NRC rates plants perforace well below aveLap.1Wst-Jonuar Power Mad.vertoly left on to sysem opert.Lug =mrenqywarn1u system-Me~ MOi iaa Ui&U3L a.-1 "aL Metropolitan Edisoa Is near balkruptcy.
-4O ftog Anodstad Pro=s ma Unfled PnTIn tsmaft-4 ew~ort j- _I 3.3-a3-a I I 011 m0, E. a... ...** Z An crerator Msinak th~e control toot at Pafieudea nudlear P~lant.Key safety role I C:erator polices nuke fuel The =C=Sq CH bjab a atom.lc owi ;aI hst1Le.tnsctoroper&.
tor. 'e concots the rate At which f the ::c!car fuel s wed.Whle the 29wir Cpa t lec, s 3d t ' the federal! government ectdes if hi can:, :ejj!"y ; ;r ormt hs ybet.:. ri"J"cslly ez~xW a Ncc!ear Regulato.7 CommiCon (.NRC)sckesman., a ret. or operator is a I: .sd=at e w*th: =x..=:::cl aCd tegieerint
'. f b c He takes a year or more of clasroom studies and on-the-obt reactor tunitng in a plant and/or in fat lites maintained by all the reaceor matnUct ers. Then azi NRC ex&a=ner conducs a wrt.tet and oral licewizg test in the plnrtscontral rocm.* The licens. which reVlres re.* :ettg every year. is good only for the parncuar ploat i which the operaor s employed.I\ost reactor operators hAve a pretTy rounee txstence:
there's lot much gog oMO the spokes.go polats out To prepare the reactor4perator traizee for emergences.
he Says. compu:e-slmulators are used to ran them tzo ughs tose sors of probltems." tnder a regulauh Issued after the Thee Mie Island Ic.C e t.: te.RC says tat Me eacor operator mut be cked up bye *sh: : .dch tucal adv*err i the control romm.The adver. a t ned reac.or operator hznelf 'paprovdes per.spectlve and bok at what's gotg on overWlL_T;,r~eo,r ,VeW5 1ea
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