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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Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds ML0311101601998-08-0303 August 1998 Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data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1997 NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming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.Q3KW
.. wq.
JAN7t !it ALL LICMNSUS OF OFEPRATING PLANTS AND
OLSEiS OF CO4NSTRUCT&CN PEN1Ts 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 revised cri:eria to be used by the of the training and licensing tat.could staff in evaluating reactor operator regula:lons. we also advised you be tna:
imolemented under the curren- oper2:ar :raining and Qua;ificatlon Conmiss fan review in the area was continuing and it could be of expec-td to result in additional criteria.
As par-. of our con:tnulng review. we Analysis I Tecnoloy, Inc., to concuc: Issued a contrict (xRR-8O-ll7) to operator licensing. Analyss. I Techinology i study of :ne requirements for on Yovemer 0,G19£0 (NURES/CR-175O). submieted their rtport to US
This persnec:ive :o tne U.S. Nuclear Regulatory report provides an indecendent resuirements and orac:1ces for control Comnmssion regarding the conclusions and recIM ndatiOns Are room ooera:or licensing. Analysts, provIded In the following areas:
- Selec:ton, training and certification ocertors . of control room
- E.'ec:iveness of the ?XRC operator licensing
- .Me*hccs *^ assare continued :omFe:ence program,
- Yetncds for' aintalming a ilghlj of ocenor's, Mtivated and dedicated ocerntor work force.
- "Pgracing zf presen:ty licensed operatzrs rtcuI-re n = . to mnee:.mrzcosed
- TrAining nc ;uallfication of non-lfcersed
.main:enance and tec.nnical succor- ocerating,
- 'ua1fications of Operator Licensing ersonnel, and Iranci (CLB) examiners.
3ased on our review of :.his report we
-fcr te recuirements for operiatr lfcensing. intend to develco additional criteria de woul Ioorec'lae it if ycu would ycu :ellfeve accrzcria:e to assist review this report and ofer any Zcrnents
- ne Ocers:zr hIItns'ng :rogrim. Ytur in us the develocent:f 'imcrovegmes f.in rtszcnse :z :tis recues: 'f dC':nt.r.
fs 1 @52I 30 /8
3" T V.
S
Me~ MOi iaa Ui&U3L a.-1"aL
Atomic LergyCo-miuso grats *eqnpment August: ower ELai Metropolitan Edisoa Is near
'. )0 lcense. December. First commer*
f gudergant QIII and balkruptcy.
c power generated
,
1073 -JUJar. Ytnor rudl&.
don lnk shuts plant dow.
- bsan wrl for ht 17 per. -4O ftog Anodstad Pro=s AUCs u Leab in esmeamenentr 19791-Septemben Elogt-month ma Unfled PnTIn tsmaft-4 ew~ort tubes cause shutdow. shutdw for rtfueling. j- _
T
slips
1174 - Consumers Power CM.
Qmillion firm thst bult ador equpped lawsit on five maIntenance and testing Novem- ber.NRC fines Corsumers SSO.000
for permttng two mdlUon-con.
I
L tol valves to be open for 18
1175 - Aprik Plant sun up mont aafter cmaoth. shutdow. JuIy tm - JZul &ln-edyShutdown Lowievel radloacltve waer'.a to rplace filter caslng 'huzu J acctdeully released into 1k. error caum crucial watercool.
December. Three-month shut. tg contrl valve to be left open down :o refuel nd check gener for 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> August Two torptps. accidental releses of ndlobctlyt-
-1171- Starch.i Couers dElsd. tyac wetk apart. December .?NRC
punes p four workers who reftue to rates plants perforace well work It plat they claim It Is below aveLap.
unsafe. October. Shutdown to m 1Wst-Jonuar Power Mad.
r pairltea vertoly left on to sysem opert.
sIT7 - ?ant's available cape. Lug =mrenqywarn1u system-
3
.3- a3- a
m0, E. a I ... ... Z**
An crerator Msinak th~e control toot at Pafieudea nudlear P~lant.
I
Key safety role I
011 C:eratorpolices nuke fuel The =C=Sq CH bjab a atom. of clasroom studies and on-the- go polats out To prepare the lc owi ;aI hst1Le.tnsctoroper&. obtreactor tunitng in a plant and reactor4perator traizee for tor.'e concots the rate At which /or in fat lites maintained by all emergences. he Says. compu:e- f the ::c!car fuel s wed. the reaceor matnUct ers. Then slmulators are used to ran them Whle the 29wir Cpa t azi NRC ex&a=ner conducs a wrt. tzo ughs tose sors ofprobltems."
lec, s 3d t ' the federal tet and oral licewizg test in the tnder aregulauh Issued after
! government ectdes if hi can plnrtscontral rocm. the Thee Mie Island Ic.C e t.:te
- , :ejj!"y ;r ; ormt hs ybet.
- The licens. which reVlres re. .RC says tat Me eacor operator
- . ri"J"cslly ez~xW a Ncc!ear * :ettg every year. isgood only for mut be cked up bye*sh: :.dch Regulato.7 CommiCon (.NRC) the parncuar ploat i which the tucal adv*err i the control romm.
sckesman., a ret. or operator is a operaor semployed. The adver. at ned reac.or I: .sd=at e w*th I\ost reactor operators hAve a operator hznelf 'paprovdes per.
- =x..=:::cl aCd tegieerint pretTy rounee txstence: there's spectlve and bok at what's gotg
'. f b c He takes a year or more lot much gog oMO the spokes. on overWlL
_
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