Letter Sequence Request |
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MONTHYEARML20261C2971983-09-0707 September 1983 One Line Diagram:4160 Volt System. Sheet 2 Project stage: Other ML20261C3011984-01-0707 January 1984 One Line Diagram:480 Volt System. Sheet 1 Project stage: Other ML20261C3061984-01-24024 January 1984 One Line Diagram:480 Volt System. Sheet 8 Project stage: Other ML20261C3191984-02-0505 February 1984 One Line Diagram:120 Volt AC System. Sheet 1 Project stage: Other ML20261C3151985-04-0505 April 1985 One Line Diagram:125 Volt DC System Project stage: Other ML20261C3111985-04-0505 April 1985 One Line Diagram:480 Volt System. Sheet 8A.Rev Date Illegible Project stage: Other ML20129C2481985-07-12012 July 1985 Forwards Revised Response to Generic Ltr 81-12 Re Alternative Shutdown Capability for Computer & Control Room, Per 850506,13 & 20 Telcons & 850618 Meeting Project stage: Meeting ML20128K7491985-07-12012 July 1985 Summary of Operating Reactor Events Meeting 85-11 on 850701. List of Attendees,Events Discussed,Significant Elements of Events & Assignment of Followup Review Responsibility Encl Project stage: Request ML0311507181985-09-27027 September 1985 Withdrawn NRC Generic Letter 1985-018: Operator Licensing Examinations Project stage: Request ML20137W1741985-09-27027 September 1985 Forwards Addl Clarifying Info to 850712 Response to Generic Ltr 81-12 Re Alternative Shutdown Capability for Computer & Control Room Project stage: Other ML20138M9991985-10-30030 October 1985 Submits Addl Info Re Alternative Shutdown Capabililty for Computer & Control Room.Procedure C.13B to Change Pressurizer Level as Required by Analysis Will Be Revised by 860201 Project stage: Other ML20198C2341985-11-0707 November 1985 Forwards Revised Requests for Exemptions from Requirements of 10CFR50,App R,Including Update of Previous Requests List of Required Mods & Respective Schedule for Installation & Addl Request Re Lack of Suppression in Control Room Project stage: Other ML20206F8651986-05-19019 May 1986 Forwards Exemption from Subsection Iii.L of 10CFR50,App R Re Capability to Achieve Cold Shutdown in 72 H & Safety Evaluation Supporting Util Request for Exemption from Subsection of 10CFR50,App R Project stage: Approval 1985-10-30
[Table View] |
Withdrawn NRC Generic Letter 1985-018: Operator Licensing ExaminationsML031150718 |
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: |
09/27/1985 |
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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-85-018, NUDOCS 8509240248 |
Download: ML031150718 (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, 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 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 [[: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>. |
Text
Withdrawn NRC Generic Letter 1985
-18, "Operator Licensing Examinations," dated September 27, 1985, has been withdrawn.
ADAMS Accession Number: ML031150718 See Federal Register notice 81 FR 31969, dated May 20, 2016
UNITED STATES e 8NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 September 27, 1985 TO ALL POWER REACTOR LICENSEES AND APPLICANTS FOR AN OPERATING LICENSE Gentlemen:
Subject:
OPERATOR LICENSING EXAMINATIONS (Generic Letter 85-18)To update the schedules you provided in response to Generic Letter 85-04, please provide the best estimate of your needs for operator licensing examinations for fiscal years FY 1986, FY 1987, FY 1988 and FY 1989 (October 1 to September 30 of each year). You are also requested to provide requalification examination schedules for this same time period. Please identify the dates you have scheduled requalification examinations and anticipated requests for licensing examination site visits and the numbe' of examinations for each visit. This information is needed to plan our resource requirements consistent with your operator licensing needs.Because of continued budget limitations, we will attempt to limit examinations to two visits per site each year. To meet this goal the regional offices may be required to redistribute the requested facility operator examination visits across the entire fiscal year to even out the examination work load and eliminate high demand periods. Therefore, your submittal of this schedule does not guarantee the number or date of examinations requested.
However, a best estimate of your needs for examinations will allow us to propose budget modifications, if necessary.
Please keep us informed of significant changes in your estimates as they occur, so we can keep our data base current.Your schedules, in the enclosed suggested formats, should be returned to Mr. Bruce Boger, Acting Chief, Operator Licensing Branch, AR-5221, Washington, DC 20555, with a courtesy copy to the appropriate Regional Administrator within 30 days of the receipt of this letter and in no event later than November 1, 1985. We appreciate your assistance.
If you have any questions concerning this request or your response, please call Mr. Bruce Boger, Acting Chief, Operator Licensing Branch, at (301) 492-4868.This request was approved by the Office of Management and Budget under clearance number 3150-0131 which expires August 31, 1988. Comments on burden DO240 and duplication may be directed to Reports Management, Room 3208, New D.C. 20503.the Office of Management and Budget, Executive Office Building, Washington, Sincerely,'9 H L. Thompson Jr irector D sion of Licensi
Enclosures:
- 1. Operating Licensing Examination Schedule 2.. Requalification Examination Schedule 3. List of Generic Letters et9WsAt ' SA* I r I .or I or. .I I \ J .p *' $ 4 v Enclosure I OPERATOR LICENSING EXAMINATION SCHEDULE Facility NRC Region FY 1986 FY 1987 FY 1988 FY 1989 1. Date__ Date Date Date#RO#SRO_-_____
- SRO Upgrade#Instructor Certification
- SRO Limited to Fuel Handling--
- 2. Date Date Date Date#RO_-__#SRO#SRO Upgrade#Instructor Certification
- SRO Limited to Fuel Handling., 3. Date Date Date Date#RO___._.__
- SRO__#SRO Upgrade -#Instructor Certification
- SRO Limited to Fuel Handling .-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
(**) (e.g., Unit One is in operation and Unit Two is approaching fuel load. Three RO candidates with no previous license are to be examined on both Units One and Two and five RO candidates with licenses on Unit One are to be examined to extend their licenses to Unit Two. Indicate (2/15/85, RO 3,5**)).
Enclosure 2 REQUALIFICATION EXAMINATION SCHEDULE Facility__
__FY 1986 NRC Region_FY 1987 FY 1988 FY 1989 1.2.3.4.Date Date Date Date_Date Date_Date Date Date Date Date_Date Date_Date Date Date Kv LIST OF RECENTLY ISSUED GENERIC LETTERS GENERIC LETTER NO.85-03 85-04 85-05 85-06 85-07 85-08 85-09 85-10 85-11 85-12 85-13 84-14 85-15 85-16 85-17 85-18 85-19 SUBJECT DATE Clarification of Equivalent Control Capacity 1/28/85 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 4/16/85 Implementation of Integrated Schedules 5/02/85 for Plant Modifications 10 CFR 20.408 Termination Reports -Format 5/23/85 Technical Specifications for Generic Letter 83-28, Item 4.3 5/23/85 Technical Specifications for Generic Letter 83-28, Items 4.3 and 4.4 5/23/85 Completion of Phase II of "Control of 6/28/85 Heavy Loads at Nuclear Power Plants" NUREG-0612 Implementation of TMI Action Item II.K.3.5,"Automatic Trip of Reactor Coolant Pumps" 6/28/85 Transmittal of NUREG-1154 Regarding the Davis Besse Loss of Main and Auxiliary Feedwater Event 8/5/85 Commercial Storage at Power Reactor Sites of Low Level Radioactive Waste not Generated by the Utility 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 8/23/85 Availability of Supplements 2 & 3 to NUREG-0933, "A Prioritization of Generic Safety Issues 8/23/85 Operator Licensing Examinations 9/27/85 Reporting Requirements on Primary Coolant 9/27/85 Iodine Spikes