NRC Generic Letter 1989-012: Operator Licensing ExaminationsML031200747 |
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, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
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Issue date: |
07/06/1989 |
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From: |
Partlow J Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-89-003 GL-89-012, NUDOCS 8907060026 |
Download: ML031200747 (6) |
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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, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
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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 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 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 [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </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 [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>. |
UNITED STATES
% XNUCLEAR REGULATORY COMMISSION
e :WASHINGTON, D. C. 20555 July 6, 1989 TO: ALL POWER REACTOR LICENSEES AND APPLICANTS FOR AN
OPERATING LICENSE
SUBJECT: OPERATOR LICENSING EXAMINATIONS (GENERIC LETTER 89- 1i Generic Letter (GL) 89-03, dated March 24, 1989, promulgated the United States Nuclear Regulatory Commission's (NRC's) national examination schedule. It assigned each facility two examination dates during the fiscal year based, to the extent possible, upon the examination estimates reported in response to GL
88-13, dated August 8, 1988. It encouraged facilities to target the assigned examination dates in fiscal year 1990, which begins on October 1, 1989, but acknowledged that some deviation from the promulgated schedule would be accommodated to facilitate incremental training schedule revisions. Beginning in fiscal year 1991 (October 1, 1990), replacement examinations will not be rescheduled but deferred until the next regularly scheduled site visit.
To plan its resources for fiscal years 1990 through 1993, the Office of Nuclear Reactor Regulation (NRR) requires your input to update the number of candidates you provided in response to GL 88-13. On the proposed format provided as Enclosure 1, please provide your best estimate of the anticipated number of candidates to be examined during each site visit assigned to you in Generic Letter 89-03. Also, please provide the dates for your scheduled requalification examinations during the same fiscal years in the proposed format provided as Enclosure 2. Your schedules, to be voluntarily submitted on the enclosed suggested formats, should be returned to Mr. Kenneth E.
Perkins, Jr., Chief, Operator Licensing Branch, OWFN-IOD-18, U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a courtesy copy to the appropriate Regional Administrator, by September 1, 1989.
Bear in mind that 10 CFR 55.45 (b)(2)(iv) prohibits the simulation facility portion if the operating test from being administered on other than a certified or an approved simulation facility after May 26, 1991. In anticipation of that deadline, NRR requires your best estimate of the dates on which you expect to certify and/or apply for NRC approval of your simulation facility(ies). A space has been provided for this purpose on the Proposed Operator Licensing Schedule Format, Enclosure 1.
The NRC regional offices, through direct liaison with your training managers, will confirm your examination requests. As stated in GL 89-03, the regional offices will continue to schedule NRC requalification examinations on a case-by-case basis until NRR reconciles the differences between the requalification and replacement examination methodologies in order to allow the concurrent administration of both examinations.
89OO
- 2 - July 6, 1989 Generic Letter 89-12 This request is covered by Office of Management and Budget Clearance Number
3150-0131, which expires March 31, 1992. The estimated average burden is two person-hours per owner response, including assessment of the new recommendations, searching data sources, gathering and analyzing the data, and preparing the required letters. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0131),
Office of Management and Budget, Washington, D.C. 20503.
We appreciate your assistance in this matter and invite you to address any questions concerning this generic letter to Mr. Perkins at (301) 492-1031.
Sincerely, Ja s G. Partlow, Associate Director r Projects Office of Nuclear Reactor Regulation Enclosures:
1. Proposed Operator Licensing Examination Schedule Format
2. Proposed Requalification Examination Schedule Format
3. List of Recently Issued NRC Generic Letters
-2- July 6, 1989 Generic Letter 89-12 and Budget Clearance Number this request is covered by Office of Managementestimated average burden is two The
3150-0131, which expires March 31, 1992. assessment of the new recommendations, person-hours per owner response, including the data, and preparing the searching data sources, gathering and analyzing this burden estimate or any other required letters. Send comments regarding including suggestions for reducing aspect of this collection of information,Management Branch, Division of this burden, to the Records and Reports Resources Management, Information Support Services, Office of Information Reduction Project (3150-0131),
Washington, D.C. 20555; and to the Paperwork D.C. 20503.
Office of Management and Budget, Washington, and invite you to address any We appreciate your assistance in this matter Mr. Perkins at (301) 492-1031.
questions concerning this generic letter to Sincerely, ORIGINAL SIGNED BY JAMES G. PARTLOW
James 6. Partlow, Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures:
1. Proposed Operator Licensing Examination Schedule Format
2. Proposed Requalification Examination Schedule Format
3. List of Recently Issued NRC Generic Letters DISTRIBUTION:
Central Files SCooley TMurley NRC PDR KPerkins JSniezek OLB RF JZwolinski CBerlinger PD RF JWRoe FMiraglia FGuenther JPartlow HSmith
- SEE PREVIOUS PAGE FOR CONCURRENCE
on 6/2/89.
Reviewed by B. Calure, Technical Editor, GUENTHER - 20 Ad
- DDIR:DLPQ :DIR:DLPQ :AWDT
OFC :OLB:DLPQ DOLB:DLPQ :OLB:DLPQ:BC - -
'---------- %,Is ------
________________
______----- ________--------------:-- :FMir
- KPerkins* :JZ v hnki :J3f NAME :FGuenther:rh* :SCooley* ____- ___- __ ___ -- - __-- __- ----------- -------------
______________- _____-
______* _______ ______
- /7A'89 : 6/ 7'/89 : (063/89 DATE :5/25/89 :5/25/89 :5/25/89
- : :
UFC
- e -
NAME :CBerlinger :JPart ow DATE : klj~/T89 (e / /89 *
Enclosure 1 PROPOSED OPERATOR LICENSING EXAMINATION SCHEDULE FORMAT
Facility NRC Region FY 199U FY 1991 FY 1992 FY 1993
(10/1/89-9/30/90) (10/1/90-9/30/91) J10/1/91-9/30/92) (1u/1/92-9/30/93)
1. Assigned Date (GL 89-03)
ERO
fSRO Instant ISRU Upgrade ISRO Limited
2. Assigned Date (GL 89-03)
IRO
- SRO Instant_
- SRO Upgrade
- SRO Limited_
Please indicate Initial cold license examinations by placing an asterisk (*) by the date. Please indicate examinations intended to extend an operator's license to a second or subsequent unit with two asterisks (**). tfor example, if Unit
1 is in operation and Unit 2 is approaching fuel load, and three RO candidates with no previous license are to be examined on both Units 1 and 2, and five RO candidates licensed on Unit 1 are to be examined to extend their licenses to Unit 2, then indicate "RO 3,5**.")
Enclosure 2 FORMAT
PROPOSED REQUALIFICATION EXAMINATION SCHEDULE
NRC Region Facility Date Planned Simulation Facility Certification/Approval FY 1993 FY 1992 FY 1993 FY 1990 FY 1991 (10/1/92-9/30/93)
(10/1189-9/30/90) (10/1/90-9130/91) (10/1/91-9/30/92)
Date Date Date
1. Date Date Date Date
2. Date Date Date., Date
3. Date Date Date Date
4. Date Date Date Date-
5. Date
ENCLOSURE 3 LIST OF RECENTLY ISSUED GENERIC LETTERS
Generic Date of Letter No. Subject Issuance Issued To
89-12 GENERIC LETTER 89-12: 7/6/89 LICENSE TO ALL
OPERATOR LICENSING POWER REACTORS
EXAMINATIONS BWRS, PWRS, AND
VENDORS IN ADDITION
TO GENERAL CODES
APPLICABLE TO
GENERIC LETTERS
89-11 GENERIC LETTER 89-11: 6/30/89 ALL BWR PLANTS &
RESOLUTION OF GENERIC ISSUE ALL LISTINGS
101 WBOILING WATER REACTOR APPLICABLE TO
WATER LEVEL REDUNDANCYN GENERIC LETTERS &
VENDORS, ETC.
89-10 GENERIC LETTER 89-10: 6/28/89 LICENSEES TO ALL
SAFETY-RELATED MOTOR-OPERATED POWER REACTORS,
VALVE TESTING AND SURVEILLANCE BWRS, PWRS, AND
VENDORS IN ADDITION
TO GENERAL CODES
APPLICABLE TO
GENERIC LETTERS
89-09 ASME SECTION III COMPONENT 5/8/89 ALL HOLDERS OF LIGHT
REPLACEMENTS WATER REACTOR
OPERATING LICENSES
89-08 ISSUANCE OF GENERIC LETTER 5/2/89 LICENSEES TO ALL
89-08: EROSION/CORROSION - POWER REACTORS,
INDUCED PIPE WALL THINNING - BWRS, PWRS, AND
10 CFR §50.54(f) VENDORS IN ADDITION
TO GENERAL CODES
APPLICABLE TO
GENERIC LETTERS
89-07 GENERIC LETTER 89-07, POWER 4/28/89 LICENSEES TO ALL
REACTOR SAFEGUARDS CONTINGENCY BWRS, PWRS, AND
PLANNING FOR SURFACE VEHICLE VENDORS IN ADDITION
BOMBS TO GENERAL CODES
APPLICABLE TO
GENERIC LETTERS
89-06 TASK ACTION PLAN ITEM I.D.2 - 4/12/89 LICENSEES OF ALL
SAFETY PARAMETER DISPLAY POWER REACTORS,
SYSTEM - 10 CFR §50.54(f) BWRS, PWRS, HTGR,
AND NSSS VENDORS
IN ADDITION TO
GENERAL CODES
APPLICABLE TO
GENERIC LETTERS
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