Letter Sequence Request |
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MONTHYEARNRC Generic Letter 1984-141984-05-11011 May 1984 NRC Generic Letter 1984-014: Replacement and Requalification Training Program Project stage: Request ML20091M6131984-05-31031 May 1984 Forwards Info Re Commitments & Plans Presented at Commission 840529 Meeting on Steam Generator Tube Failure Incident on 840516 & Insps Project stage: Request ML20092H4911984-06-18018 June 1984 Forwards Response to 840511 Request for Addl Info Re 840531 Generation Package for Emergency Procedures Project stage: Request ML20133P0901984-06-18018 June 1984 Forwards Draft Steam Generator Tube Rupture Incident Rept, in Response to Insp Rept 50-285/84-13.Approval to Leave Refueling Shutdown & Proceed to Power Operation Requested. Final Rept Expected by 840619 Project stage: Draft Other ML20133P3031984-06-30030 June 1984 Draft Steam Generator Tube Rupture Incident Rept Project stage: Draft Other ML20090D4151984-07-0909 July 1984 Proposed Tech Specs Re Steam Generator Operability Project stage: Other ML20090D4111984-07-0909 July 1984 Application for Amend to Licenses DPR-42 & DPR-60,changing Tech Specs Re Steam Generator Operability,Per NRC 840706 Request,To Allow Continued Operation W/Three Defected Tubes Until Next Refueling Outage Project stage: Request ML20090D4061984-07-0909 July 1984 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Revising Tech Specs Re Steam Generator Tube Operability to Allow Continued Operation W/Three Defected Tubes Until Next Refueling Outage.Fee Encl Project stage: Request 1984-06-18
[Table View] |
NRC Generic Letter 1984-014: Replacement and Requalification Training ProgramML031180008 |
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: |
05/11/1984 |
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From: |
Eisenhut D Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-84-014, NUDOCS 8405110055 |
Download: ML031180008 (3) |
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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 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes 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>. |
toREGLe,,
- UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555
-May 11, 1984 TO ALL OPERATING POWER REACTOR LICENSEES
Gentlemen:
SUBJECT: REPLACEMENT AND REQUALIFICATION TRAINING PROGRAM
(Generic Letter No. 84-14)
One of the most important follow-up actions that has been identified as part of the operator licensing program reviews is to ensure that there is an accurate description of each licensee's requalification training program and replacement operator training program. This information is needed to ensure that candidates for operator licensing examinations have completed the necessary qualifications and training prior to examination and to ensure that requalifi- cation program audits by the Regions are based on the requalification training program as implemented.
Some utilities have provided a description of the program as part of the updated FSAR which was submitted in accordance with the requirements of 10 CFR
50.71(e)4. Other utilities, in the updated FSAR, have referenced the program, but have not provided the details or a description. In these latter instances, the regulatory staff finds it very difficult to prepare a proper audit.
The regulations, 10 CFR Part 50.54(i-1), require that licensees have a program in effect which meets the requirements of Appendix A to Part 55 and that changes to the approved program that decrease the scope, time allotted for the program or frequency in conducting different parts be approved. Therefore, we are requesting that the next annual update to the FSAR either include the current program or provide explicit reference, including date, to the submittal which is the program of record.
Licensees have submitted proposed changes to their replacement and requalifi- cation training programs and some proposed chances were submitted directly to the NRR technical review branches and Regional Offices. Proposed chances to training programs should be submitted to the Director, Division of Licensing, not the Regional Offices or technical review branches. All such proposed changes should be clearly identified and include appropriate fees.
' ~~Sgo
-2 -
We are also aware that a number of licensees are either in the process of ordering, or have already taken delivery on, plant-referenced simulators.
When these new simulators are available, revisions should be made to the replacement and requalification training programs to reflect their use. When the revision to the program involves only the identification of a plant- referenced simulator, no approval is required; therefore, no fee is required.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation DISTRIBUTION
Central Files FMiragl ia LQB Reading PHungerbuhler DHFS Reading-2 GMeyer HBooher TJCarter/HLefevre JPersensky GHolahan DMorisseau JZwolinski JAxelrad DEisenhut/RPurple JLeiberman This request has been approved by 0MB Clearance Number 3150-0018, which expires February 29, 1987.
- PREVIOUS CONCURRENCES OBTAINED
DHFS:LQB* DHFS:LQB* DHI:S:LQB* DHFS:OLB* DHFS:DD* DHFS*YVI 4 IE* OELD*
DMorisseaLa JPersensky HB(,oher DBeckham WRussell HThompso JAxelrad JLeiberman
3/30/84 3/30/84 30/84 42//84 4/2/84 4/2/84 4/2/84 4/9/84 DL* DL:ORAw DL: ORA'X M
JCarter JZwol nski GHolaha glia) flsenhut seni4
5/3/84 5/1 /84 5/1 /84 5k3Y84 ( 5/,6/84
- 2 -
We are also aware that a number of licensees are either in the process of ordering, or have already taken delivery on, plant-referenced simulators.
When these new simulators are available, revisions should be made to the replacement and requalification training programs to reflect their use. When the revision to the program involves only the identification of a plant- referenced simulator, no approval is required; therefore, no fee is required.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation DISTRIBUTION
Central Files FMiragl ia LQB Reading PHungerbuhler DHFS Reading-2 GMeyer HBooher TJCarter/HLefevre JPersensky GHolahan DMorisseau DEisenhut/RPurple J. elrad JLeiberman
- PREVIOUS CONCURRENCES OBTAINED
DHFS:LQB* DHFS:LQB* DHFS:LQB* DHFS:OLB* DHFS:DD* DHFS*
(-i rf1 IE* OELD*
DMorisseau JPersensky HBooher DBeckham WRussell HThompson JAxelrad JLeiberman
3/30/84 3/30/84 3/30/84 4/2/84 4/2/84 4/2/84 4/2/84 4/9/84 DLCI DL:ORAB DL:AD:SA DL: D
JC~ rter GHolahan FJMiragl ia DEisenhut
5/5,/84 5/ /84 5/ /84 5/ /84
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