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| {{#Wiki_filter:: N L f.. -.UNITED STATESI\l 0 {NCLAR REGULATORYCOMMISSION -* 0 WASHINGTON, D. C. 20555August 23, 1985TO ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING LICENSES,AND HOLDERS OF CONSTRUCTION PERMITS (GENERIC LETTER 85-11)Gentlemen:SUBJECT: AVAILABILITY OF SUPPLEMENTS 2 and 3 TO NUREG-0933, "A PRIORITIZATIONOF GENERIC SAFETY ISSUES"This letter is to inform you that Supplements 2 and 3 to NUREG-0933, "APrioritization of Generic Safety Issues," were published in January andJuly 1985, respectively. These supplements present the priority rankings forgeneric safety issues related to nuclear power plants. The purpose of theserankings is to assist in the timely and efficient allocation of NRC resourcesfor the resolution of those safety issues that have a significant potentialfor reducing risk. The safety priority rankings of HIGH, MEDIUM, LOW, andDROP have been assigned on the basis of risk significance estimates, theratio of risk to costs and other impacts estimated to result if resolutionsof the safety issues were implemented, and the consideration of uncertaintiesand other quantitative or qualitative factors, as discussed in theIntroduction of NUREG-0933. To the extent practical, estimates arequantitative. Although changes to nuclear power plant designs or operationare assumed, the sole purpose in prioritizing the issues is to estimate costsand other impacts that might result if such changes were implemented.The priority rankings in the report are based on generic assessments, i.e.,assessments of plants thought to be typical of a class of plants. Thus, thesafety significance of an issue might be greater (or less) for a specificplant because of features of the design or operation that are different fromthose assumed in the generic assessments.The supplements contain: (1) the issues that have been resolved since thepublication of NUREG-0933 Supplement 1 in July 1984; (2) the issues thathave been removed from further consideration by the NRC (i.e., those issueswith LOW or DROP priority rankings); and (3) the issues that are in theprocess of resolution (i.e., those issues nearly-resolved or with HIGH orMEDIUM priority rankings).NUREG-0933 and its 3 supplements may be purchased by calling (202) 275-2060or (202) 275-2171 or by writing to the Superintendent of Documents, U.SGovernment Printing Office, Post Office Box 37082, Washington, D.C. 20013-7082, or the National Technical Information Service, Department of Commerce,5258 Port Royal Road, Springfield, VA 22161.AIIpD AOC J53bb cl)C99fZ<41) 0227> | | {{#Wiki_filter:: N L f.. -.UNITED STATES I\l 0 {NCLAR REGULATORYCOMMISSION |
| .1 I: %. ; .wI -:a .i ..I ;:K-4A\ This letter does not contain any new requirements or guidanceof operating reactors, applicants for operating licenses, andconstruction permits. No reply is required. If you have anythe subject, please contact Ronald Emrlt on (301) 492-4960.for licenseesholders ofquestions onRugt '.Tho ~on, .baorDi v on of LicensingOffice of Nuclear Reactor Regulationcc: List of Generic Letters/ 't r/ | | -* 0 WASHINGTON, D. C. 20555 August 23, 1985 TO ALL LICENSEES |
| -s I D4-cv§ I.-/9TO ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING LICENSES,AND HOLDERS OF CONSTRUCTION PERMITSGentlemen:SUBJECT: AVAILABILITY OF SUPPLEMENT 2 TO NUREG-0933, "A PRIORITIZATION OFGENERIC SAFETY ISSUES"This letter is to inform you that Supplement 2 to NUREG-0933, "APrioritization of Generic Safety Issues," will be published in January 1985and may be purchased by calling (301) 492-9530 or writing the NRC/GPO SalesProgram, Division of Technical Information and Document Control, U.S.Nuclear Regulatory Commission, Washington, D.C. 20555, or the NationalTechnical Information Service, Department of Commerce, 5258 Port Royal Road,Springfield, VA 22161.The Supplement presents the priority rankings for generic safety issuesrelated to nuclear power plants. The purpose of these rankings is to assistin the timely and efficient allocation of NRC resources for-the resolutionof those safety issues that have a significant potential for reducing risk.The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have beenassigned on the basis of risk significance estimates, the ratio of risk tocosts and other impacts estimated to result if resolutions of the safetyissues were implemented, and the consideration of uncertainties and otherquantitative or qualitative factors, as discussed in the Introduction ofNUREG-0933. To the extent practical, estimates are quantitative. Althoughchanges to nuclear power plant designs or operation are assumed, the solepurpose-in prioritizing the issues is to estimate costs and other impactsthat might result if such changes were implemented.The priority rankings in the report are based on generic assessments, i.e.,assessments of plants thought to be typical of a class of plants. Thus, thesafety significance of an issue might be greater (or less) for a specificplant because of features of the design or operation that are different fromthose assumed in the generic assessments.The Supplement contains: (1) the issues that have been resolved since thepublication of NUREG-0933 Supplement 1 in July 1984; (2) the issues thathave been removed from further consideration by the NRC (i.e., those issueswith LOW or DROP priority rankings); and (3) the issues that are in theprocess of resolution (i.e., those issues nearly-resolved or with HIGH or 00MEDIUM priority rankings).85082102- -WOr nateR ..... ;................... .... ............... ...... ..,,,,........ ....,........... ...... ,,,..................... ............... ......... .............SURNAM Ei ........................ ........................ ................ ........ ........................ ........................ ........................ ........................DATt ................. .......................... ......................... .....I.. ........................ .........................t4RC FORM 316 (10 80) NRCM 0240 OFFICIAL RECORD COPY NAC FORM 316 (10 K0) NRCM 0240O FFICIA L R EC O RD C OPYUSGPO 1961-335-964 I" -b1-Of 0LIST OF RECENTLY.ISSUED GENERIC LETTERStGENERICLETTER NO.85-0185-0285-0385-0485-0585-0685-0785-08SUBJECT DATE,Fire Protection Policy Steering.Committee, , .Report; -/9/8S;Staff Recommended Actions .itemmninq From NRCIntegrated Program for the Resolution ofUnresolved Safety Issues Regarding SteamGenerator Tube Integrity 4/15/85Clarificationrof Equivalent Control Capacity V128/85For Standby Liquid Control SystemsOperator Licensing Examinations1/29/85Inadvertent Boron Dilution Events ...-,, '1/31/85Quality Assurance Guidance for ATWSEquipment that is not Safety-RelatedImplementation of Integrated Schedulesfor Plant Modifications10 CFR 20.408 Termination Reports -Format4/16/855/02/855/23/8585-0985-1085-1185-1285-1384-1485-1585-1685-17Technical Specifications for GenericLetter 83-28, Item 4.3-Technical Specifications for GenericLetter 83-28, Items 4.3 and 4.4Completion of Phase II of "Control ofHeavy Loads at Nuclear Power Plants"NUREG-0612Implementation of TMI Action Item II.K.3.5,"Automatic Trip of Reactor Coolant Pumps"Transmittal of NUREG-1154 Regarding theDavis Besse Loss of Main and AuxiliaryFeedwater EventCommercial Storage at Power Reactor Sitesof Low Level Radioactive Waste notGenerated by the Utility5/23/85 ---5/23/856/28/856/28/858/5/858/1/85Information Relating to the Deadlines forCompliance with 10 CFR 50.49, "EnvironmentalQualification of Electric Equipment Importantto Safety for Nuclear Power Plants 8/6/85High Boron ConcentrationsAvailability of Supplements 2 & 3 toNUREG-0933, "A Prioritization ofGeneric Safety Issues8/23/858/23/85 | | OF OPERATING |
| ; IC ' / efK)-2-This letter does not con'tain any new requirements or guidance for licenseesof operating reactors, applicants for operating licenses, and holders ofconstruction permits. No reply is required.m signed bFWugh L-Thmnson, Jr.Hugh L. Thompson, Jr, DirectorDivision of LicensingOffice of Nuclear Reactor Regulationcc: List of Generic LettersVr.ikjbl r(D/OFFCE S p .E B W p ... ......... ................ ..... .. ..................REmrit:s.-J Wners F owsp e TSpei ' ES4s tSU Ai 85 l/8 ................ ..........ArA .... .. ''0 '-'.' ''. 0240 OFFIC'AL RECORD COPY '''. .'' ..... ..H4RC FOAM~ 31t (10 0) NRCM 0240O FFICIA L R EC O RD C OPYUSGPO 19NI-335-960 | | REACTORS, APPLICANTS |
| }} | | FOR OPERATING |
| | LICENSES, AND HOLDERS OF CONSTRUCTION |
| | PERMITS (GENERIC LETTER 85-11)Gentlemen: |
| | SUBJECT: AVAILABILITY |
| | OF SUPPLEMENTS |
| | 2 and 3 TO NUREG-0933, "A PRIORITIZATION |
| | OF GENERIC SAFETY ISSUES" This letter is to inform you that Supplements |
| | 2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues," were published in January and July 1985, respectively. |
| | |
| | These supplements present the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors, as discussed in the Introduction of NUREG-0933. |
| | |
| | To the extent practical, estimates are quantitative. |
| | |
| | Although changes to nuclear power plant designs or operation are assumed, the sole purpose in prioritizing the issues is to estimate costs and other impacts that might result if such changes were implemented. |
| | |
| | The priority rankings in the report are based on generic assessments, i.e., assessments of plants thought to be typical of a class of plants. Thus, the safety significance of an issue might be greater (or less) for a specific plant because of features of the design or operation that are different from those assumed in the generic assessments. |
| | |
| | The supplements contain: (1) the issues that have been resolved since the publication of NUREG-0933 Supplement |
| | 1 in July 1984; (2) the issues that have been removed from further consideration by the NRC (i.e., those issues with LOW or DROP priority rankings); |
| | and (3) the issues that are in the process of resolution (i.e., those issues nearly-resolved or with HIGH or MEDIUM priority rankings). |
| | NUREG-0933 and its 3 supplements may be purchased by calling (202) 275-2060 or (202) 275-2171 or by writing to the Superintendent of Documents, U.S Government Printing Office, Post Office Box 37082, Washington, D.C. 20013-7082, or the National Technical Information Service, Department of Commerce, 5258 Port Royal Road, Springfield, VA 22161.AII pD AOC J53bb cl)C99 fZ<41) 0227> |
| | .1 I: %. ; .w I -: a .i ..I ;: K-4 A\ This letter does not contain any new requirements or guidance of operating reactors, applicants for operating licenses, and construction permits. No reply is required. |
| | |
| | If you have any the subject, please contact Ronald Emrlt on (301) 492-4960.for licensees holders of questions on Rugt '.Tho ~on, .baor Di v on of Licensing Office of Nuclear Reactor Regulation cc: List of Generic Letters/ 't r/ |
| | -s I D4-cv§ I.-/9 TO ALL LICENSEES |
| | OF OPERATING |
| | REACTORS, APPLICANTS |
| | FOR OPERATING |
| | LICENSES, AND HOLDERS OF CONSTRUCTION |
| | PERMITS Gentlemen: |
| | SUBJECT: AVAILABILITY |
| | OF SUPPLEMENT |
| | 2 TO NUREG-0933, "A PRIORITIZATION |
| | OF GENERIC SAFETY ISSUES" This letter is to inform you that Supplement |
| | 2 to NUREG-0933, "A Prioritization of Generic Safety Issues," will be published in January 1985 and may be purchased by calling (301) 492-9530 or writing the NRC/GPO Sales Program, Division of Technical Information and Document Control, U.S.Nuclear Regulatory Commission, Washington, D.C. 20555, or the National Technical Information Service, Department of Commerce, 5258 Port Royal Road, Springfield, VA 22161.The Supplement presents the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for-the resolution of those safety issues that have a significant potential for reducing risk.The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors, as discussed in the Introduction of NUREG-0933. |
| | |
| | To the extent practical, estimates are quantitative. |
| | |
| | Although changes to nuclear power plant designs or operation are assumed, the sole purpose-in prioritizing the issues is to estimate costs and other impacts that might result if such changes were implemented. |
| | |
| | The priority rankings in the report are based on generic assessments, i.e., assessments of plants thought to be typical of a class of plants. Thus, the safety significance of an issue might be greater (or less) for a specific plant because of features of the design or operation that are different from those assumed in the generic assessments. |
| | |
| | The Supplement contains: |
| | (1) the issues that have been resolved since the publication of NUREG-0933 Supplement |
| | 1 in July 1984; (2) the issues that have been removed from further consideration by the NRC (i.e., those issues with LOW or DROP priority rankings); |
| | and (3) the issues that are in the process of resolution (i.e., those issues nearly-resolved or with HIGH or 00 MEDIUM priority rankings). |
| | 85082102- -W Or nateR ..... ;................... |
| | .... ............... |
| | ...... ..,,,,........ |
| | ....,........... |
| | ...... ,,,..................... |
| | ............... |
| | ......... |
| | ............. |
| | SURNAM Ei ........................ |
| | ........................ |
| | ................ |
| | ........ ........................ |
| | ........................ |
| | ........................ |
| | ........................ |
| | DATt ................. |
| | .......................... |
| | ......................... |
| | .....I.. ........................ |
| | ......................... |
| | t4RC FORM 316 (10 80) NRCM 0240 OFFICIAL RECORD COPY NAC FORM 316 (10 K0) NRCM 0240 O FFICIA L R EC O RD C OPY USGPO 1961-335-964 I" -b1-Of 0 LIST OF RECENTLY.ISSUED |
| | GENERIC LETTERS t GENERIC LETTER NO.85-01 85-02 85-03 85-04 85-05 85-06 85-07 85-08 SUBJECT DATE ,Fire Protection Policy Steering.Committee, , .Report; -/9/8S;Staff Recommended Actions .itemmninq From NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
| | 4/15/85 Clarificationrof Equivalent Control Capacity V128/85 For Standby Liquid Control Systems Operator Licensing Examinations |
| | 1/29/85 Inadvertent Boron Dilution Events ...-,, '1/31/85 Quality Assurance Guidance for ATWS Equipment that is not Safety-Related Implementation of Integrated Schedules for Plant Modifications |
| | 10 CFR 20.408 Termination Reports -Format 4/16/85 5/02/85 5/23/85 85-09 85-10 85-11 85-12 85-13 84-14 85-15 85-16 85-17 Technical Specifications for Generic Letter 83-28, Item 4.3-Technical Specifications for Generic Letter 83-28, Items 4.3 and 4.4 Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 Implementation of TMI Action Item II.K.3.5,"Automatic Trip of Reactor Coolant Pumps" Transmittal of NUREG-1154 Regarding the Davis Besse Loss of Main and Auxiliary Feedwater Event Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste not Generated by the Utility 5/23/85 ---5/23/85 6/28/85 6/28/85 8/5/85 8/1/85 Information Relating to the Deadlines for Compliance with 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants 8/6/85 High Boron Concentrations Availability of Supplements |
| | 2 & 3 to NUREG-0933, "A Prioritization of Generic Safety Issues 8/23/85 8/23/85 |
| | ; I C ' / ef K)-2-This letter does not con'tain any new requirements or guidance for licensees of operating reactors, applicants for operating licenses, and holders of construction permits. No reply is required.m signed bF Wugh L-Thmnson, Jr.Hugh L. Thompson, Jr, Director Division of Licensing Office of Nuclear Reactor Regulation cc: List of Generic Letters Vr.ikjbl r(D/OFFCE S p .E B W p ... ......... ................ |
| | ..... .. .................. |
| | REmrit:s.-J |
| | Wners F owsp e TSpei ' ES4s t SU Ai 85 l/8 ................ |
| | .......... |
| | ArA .... .. ''0 '-'.' ''. 0240 OFFIC'AL RECORD COPY '''. .'' ..... ..H4RC FOAM~ 31t (10 0) NRCM 0240 O FFICIA L R EC O RD C OPY USGPO 19NI-335-960}} |
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NRC Generic Letter 1985-017: Availability of Supplements 2 and 3 to NUREG-0933, a Prioritization of Generic Safety IssuesML031140418 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
08/23/1985 |
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From: |
Thompson H L Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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GL-85-017, NUDOCS 8508210259 |
Download: ML031140418 (5) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Category:NRC Generic Letter
MONTHYEARML23200A1832023-08-0303 August 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17067A2782017-04-18018 April 2017 Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools for the Armed Forces Radiobiology Research Institute, Docket No. 50-170 (CAC No. A11010) ML17067A4042017-04-17017 April 2017 Washington State University GL 2016-01 Closeout Form Letter for Rtrs with No Credited NAM NRC Generic Letter 2007-012007-02-0707 February 2007 NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients NRC Generic Letter 2006-012006-01-20020 January 2006 NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications NRC Generic Letter 1999-021999-08-23023 August 1999 NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal NRC Generic Letter 1983-111999-06-24024 June 1999 NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis 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 ML0311101371999-06-0303 June 1999 Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates NRC Generic Letter 1999-011999-05-0303 May 1999 NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities 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 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 1998-031998-06-22022 June 1998 NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs 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 NRC Generic Letter 1996-061997-11-13013 November 1997 NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions 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 1997-031997-07-0909 July 1997 NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees NRC Generic Letter 1997-021997-05-15015 May 1997 NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report NRC Generic Letter 1995-061997-01-31031 January 1997 NRC Generic Letter 1995-006: Changes in Operator Licensing Program NRC Generic Letter 1996-081996-12-15015 December 1996 NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators NRC Generic Letter 1996-051996-09-18018 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 1995-091996-04-0505 April 1996 NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials 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 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 1995-031995-04-28028 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 NRC Generic Letter 1995-011995-01-26026 January 1995 NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities ML0312004431994-09-0202 September 1994 Withdrawn - NRC Generic Letter 1994-004: 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 2023-08-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
- N L f.. -.UNITED STATES I\l 0 {NCLAR REGULATORYCOMMISSION
-* 0 WASHINGTON, D. C. 20555 August 23, 1985 TO ALL LICENSEES
OF OPERATING
REACTORS, APPLICANTS
FOR OPERATING
LICENSES, AND HOLDERS OF CONSTRUCTION
PERMITS (GENERIC LETTER 85-11)Gentlemen:
SUBJECT: AVAILABILITY
OF SUPPLEMENTS
2 and 3 TO NUREG-0933, "A PRIORITIZATION
OF GENERIC SAFETY ISSUES" This letter is to inform you that Supplements
2 and 3 to NUREG-0933, "A Prioritization of Generic Safety Issues," were published in January and July 1985, respectively.
These supplements present the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors, as discussed in the Introduction of NUREG-0933.
To the extent practical, estimates are quantitative.
Although changes to nuclear power plant designs or operation are assumed, the sole purpose in prioritizing the issues is to estimate costs and other impacts that might result if such changes were implemented.
The priority rankings in the report are based on generic assessments, i.e., assessments of plants thought to be typical of a class of plants. Thus, the safety significance of an issue might be greater (or less) for a specific plant because of features of the design or operation that are different from those assumed in the generic assessments.
The supplements contain: (1) the issues that have been resolved since the publication of NUREG-0933 Supplement
1 in July 1984; (2) the issues that have been removed from further consideration by the NRC (i.e., those issues with LOW or DROP priority rankings);
and (3) the issues that are in the process of resolution (i.e., those issues nearly-resolved or with HIGH or MEDIUM priority rankings).
NUREG-0933 and its 3 supplements may be purchased by calling (202) 275-2060 or (202) 275-2171 or by writing to the Superintendent of Documents, U.S Government Printing Office, Post Office Box 37082, Washington, D.C. 20013-7082, or the National Technical Information Service, Department of Commerce, 5258 Port Royal Road, Springfield, VA 22161.AII pD AOC J53bb cl)C99 fZ<41) 0227>
.1 I: %. ; .w I -: a .i ..I ;: K-4 A\ This letter does not contain any new requirements or guidance of operating reactors, applicants for operating licenses, and construction permits. No reply is required.
If you have any the subject, please contact Ronald Emrlt on (301) 492-4960.for licensees holders of questions on Rugt '.Tho ~on, .baor Di v on of Licensing Office of Nuclear Reactor Regulation cc: List of Generic Letters/ 't r/
-s I D4-cv§ I.-/9 TO ALL LICENSEES
OF OPERATING
REACTORS, APPLICANTS
FOR OPERATING
LICENSES, AND HOLDERS OF CONSTRUCTION
PERMITS Gentlemen:
SUBJECT: AVAILABILITY
OF SUPPLEMENT
2 TO NUREG-0933, "A PRIORITIZATION
OF GENERIC SAFETY ISSUES" This letter is to inform you that Supplement
2 to NUREG-0933, "A Prioritization of Generic Safety Issues," will be published in January 1985 and may be purchased by calling (301) 492-9530 or writing the NRC/GPO Sales Program, Division of Technical Information and Document Control, U.S.Nuclear Regulatory Commission, Washington, D.C. 20555, or the National Technical Information Service, Department of Commerce, 5258 Port Royal Road, Springfield, VA 22161.The Supplement presents the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for-the resolution of those safety issues that have a significant potential for reducing risk.The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors, as discussed in the Introduction of NUREG-0933.
To the extent practical, estimates are quantitative.
Although changes to nuclear power plant designs or operation are assumed, the sole purpose-in prioritizing the issues is to estimate costs and other impacts that might result if such changes were implemented.
The priority rankings in the report are based on generic assessments, i.e., assessments of plants thought to be typical of a class of plants. Thus, the safety significance of an issue might be greater (or less) for a specific plant because of features of the design or operation that are different from those assumed in the generic assessments.
The Supplement contains:
(1) the issues that have been resolved since the publication of NUREG-0933 Supplement
1 in July 1984; (2) the issues that have been removed from further consideration by the NRC (i.e., those issues with LOW or DROP priority rankings);
and (3) the issues that are in the process of resolution (i.e., those issues nearly-resolved or with HIGH or 00 MEDIUM priority rankings).
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GENERIC LETTERS t GENERIC LETTER NO.85-01 85-02 85-03 85-04 85-05 85-06 85-07 85-08 SUBJECT DATE ,Fire Protection Policy Steering.Committee, , .Report; -/9/8S;Staff Recommended Actions .itemmninq From NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity
4/15/85 Clarificationrof Equivalent Control Capacity V128/85 For Standby Liquid Control Systems Operator Licensing Examinations
1/29/85 Inadvertent Boron Dilution Events ...-,, '1/31/85 Quality Assurance Guidance for ATWS Equipment that is not Safety-Related Implementation of Integrated Schedules for Plant Modifications
10 CFR 20.408 Termination Reports -Format 4/16/85 5/02/85 5/23/85 85-09 85-10 85-11 85-12 85-13 84-14 85-15 85-16 85-17 Technical Specifications for Generic Letter 83-28, Item 4.3-Technical Specifications for Generic Letter 83-28, Items 4.3 and 4.4 Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 Implementation of TMI Action Item II.K.3.5,"Automatic Trip of Reactor Coolant Pumps" Transmittal of NUREG-1154 Regarding the Davis Besse Loss of Main and Auxiliary Feedwater Event Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste not Generated by the Utility 5/23/85 ---5/23/85 6/28/85 6/28/85 8/5/85 8/1/85 Information Relating to the Deadlines for Compliance with 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants 8/6/85 High Boron Concentrations Availability of Supplements
2 & 3 to NUREG-0933, "A Prioritization of Generic Safety Issues 8/23/85 8/23/85
- I C ' / ef K)-2-This letter does not con'tain any new requirements or guidance for licensees of operating reactors, applicants for operating licenses, and holders of construction permits. No reply is required.m signed bF Wugh L-Thmnson, Jr.Hugh L. Thompson, Jr, Director Division of Licensing Office of Nuclear Reactor Regulation cc
- List of Generic Letters Vr.ikjbl r(D/OFFCE S p .E B W p ... ......... ................
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