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| {{#Wiki_filter:GAN 9 1985 TO ALL POWER REACTOR LICENSEES | | {{#Wiki_filter:GAN 9 1985 TO ALL POWER REACTOR LICENSEES AND ALL APPLICANTS FOR POWER REACTOR LICENSES |
| AND ALL APPLICANTS | | Gentlemen: |
| FOR POWER REACTOR LICENSES Gentlemen: | | SUBJECT: FIRE PROTECTION POLICY STEERING COMMITTEE REPORT |
| SUBJECT: FIRE PROTECTION | | (Generic Letter 85-01) |
| POLICY STEERING COMMITTEE | | Enclosed is a copy of the NRC Fire Protection Policy Steering Committee Report, dated October 26, 1984. The background and purpose of the Steering Committee is described in the report. A notice will be published in the Federal Register in the near future that will provide an opportunity for public comments on this report. No response to this letter is required. |
| REPORT (Generic Letter 85-01)Enclosed is a copy of the NRC Fire Protection Policy Steering Committee Report, dated October 26, 1984. The background and purpose of the Steering Committee is described in the report. A notice will be published in the Federal Register in the near future that will provide an opportunity for public comments on this report. No response to this letter is required.Original signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Enclosure:
| | |
| As stated 1 4/86 8501100621 | | Original signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Enclosure: |
| 1SI 57/ #33 GHol an l/j: /84 Q~ hf i e d/a/ 41V84 OEL &llo &WShields/ 2 /26/84.* / 6/84}} | | As stated |
| | 8501100621 |
| | 1SI |
| | 57/ #33 |
| | 14/86 OEL &llo & |
| | GHol an Q~hf ie d WShields |
| | .* /6/84 l/j: /84 /a/ 41V84 /2 /26/84}} |
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| {{GL-Nav}} | | {{GL-Nav}} |
Latest revision as of 02:18, 24 November 2019
NRC Generic Letter 1985-001: Fire Protection Policy Steering Committee Report| ML031210003 |
| 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: |
01/09/1985 |
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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-85-001 GL-85-001, NUDOCS 8501100621 |
| Download: ML031210003 (1) |
|
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
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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
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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>. |
GAN 9 1985 TO ALL POWER REACTOR LICENSEES AND ALL APPLICANTS FOR POWER REACTOR LICENSES
Gentlemen:
SUBJECT: FIRE PROTECTION POLICY STEERING COMMITTEE REPORT
(Generic Letter 85-01)
Enclosed is a copy of the NRC Fire Protection Policy Steering Committee Report, dated October 26, 1984. The background and purpose of the Steering Committee is described in the report. A notice will be published in the Federal Register in the near future that will provide an opportunity for public comments on this report. No response to this letter is required.
Original signed by Darrell G. Eisenhut Darrell G. Eisenhut, Director Division of Licensing Enclosure:
As stated
8501100621
1SI
57/ #33
14/86 OEL &llo &
GHol an Q~hf ie d WShields
.* /6/84 l/j: /84 /a/ 41V84 /2 /26/84
Template:GL-Nav