NRC Generic Letter 1991-019: Information to Addressees Regarding New Telephone Numbers for NRC Offices Located in One White Flint NorthML031140554 |
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, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
12/19/1991 |
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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-91-019, NUDOCS 9112160130 |
Download: ML031140554 (4) |
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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, 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 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 [[: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 [[: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
NUCLEAR REGULATORY COMMISSION
WASHINGTON. D.C. 2O6M
December 19, 1991 TO: ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTION PERMITS FOR
NUCLEAR POWER REACTORS
SUBJECT: INFORMATION TO
ADDRESSEES
REGARDING NEW TELEPHONE NUMBERS FOR
NRC OFFICES LOCATED IN ONE WHITE FLINT NORTH - GENERIC LETTER 91-19 The U.S. Nuclear Regulatory Commission (NRC) is issuing this Generic Letter to alert addressees to new telephone numbers for certain NRC offices located in One White Flint North (OWFN). All offices located in OWFN are affected. No specific action or written response is required.
The new phone system mandated by the General Services Administration (GSA)
will be provided by GSA's Washington Interagency Telecommunication's System (WITS). Enclosed is an NRR organizational listing providing new telephone numbers for key NRR managers. The WITS System is effective at 8:00 p.m.
Eastern Standard Time, on December 13, 1991. Also included for your information are the new telephone numbers for the Chairman, the Commissioners and the Executive Director for Operations.
Chairman Ivan Selin 301 504-1759 Commissioner Kenneth C. Rogers 301 504-1855 Commissioner James R. Curtiss 301 504-1875 Commissioner Forrest J. Remick 301 504-1820
Commissioner Gail dePlanque 301 504-1800
James M. Taylor, Executive Director for Operations 301 504-1700
Also, please note that the telephone numbers for the facsimile machines located in the Central Mail Facility at OWFN will be as follows:
Facsimile Type Telephone Verification No.
3M 9165 301) 504-2260 (301) 504-2261
3M 9165 301) 504-1137 (301) 504-2261 Fujitsu DEX 2400 301) 504-2259 B301 504-2261 Please contact Pam Foust (301) 504-1213, or the appropriate NRC Project Manager, if you have any questions regarding this matter.
Enclosure:
As stated ---7-ZV--e-
- I 6-
9112160130 %In\q
OFFICE OF NUCLEAR REACTOR REOULATION DECEMBER 1991 - REVISED
Director Thornas E. Mudey 12D0 504-1270
Deputy Director Frank J. Mrrglia 12D7 504-2272 Technicdl Assistant Mchoel Cullingford 12E18 504-1275 PROGRAM MANAGEMENT POLICY DEVELOPMENT AND ANALYSIS STAFF (PMASI ASSOCIATE DIRECTOR FOR INSPECTION AND TECHNICAL ASSESSMENT IADTI
Director Frank P. Gillespie 12E21 504-1275 Associate Director William T. Russell 112E23 504-1274 Planning, Program. and Richard H. Wcnsman 12H1 504-1202 Managerment Support Branch (PMS8) DVISION OF OPERATIONAL EVENTS ASSESSMENT IDOEAI
Policy Development and Anthony T. Gody 12E1 504-1257 Director ChHrles E. Rossi 11E1 504-1183 Technical Support Branch (PTSB) Technical Assistant James W. Shcpsker 11 E3 504-1151 Events Asseassent Branch (OEAB) Alfred Chaff" IlEl1 504-1168 Inspection and Lic nsng Anthony T. Gody 12021 504-1243 Generic Cornrnunications Branch (OGCB) Car H. Berlinger 8D19 504-2837 Program Branch (ILP) (Acting) Technical Specifications Christopher Grimes 11 E21 504-1161 Branch (OTSBI
Ageml14ATW frwirTim PFl Poinge"Y iA~niaii Associate Director James G Partlow 12D9 504-1284 DIVISION OF ENGINEERING TECHNOLOGY IDETI
Director Jams E. Richardson 7D25 504-2722 DIVISION OF REACTOR PROJECTS - Vll IDRPE) Deputy Director Boan-Dar IBD.I Li(ew 7023 504-3298 Director Steven A. Verge 14E1 504-1403 Technical Assistant (Acting) Stephen Kosciolny 7G22 504-2726 Tochnical Assistent lMichcol Boyle 14E3 504-1401 Materials and Chemical Ching-Yao Chang 7D3 504-2795 Engineering Branch (EMCB)
A snt Deootor for Redfon I RAectose IADRI) Mechanical Engineering Branch (EMEB) James A. Norberg 7E21 504-3288 Assisdtnt Director Jose A. Calvo 14A4 504-1404 Structural and Geoecience Goutam Bagchi 7H1b 504-2733 Project Directorate 1-1 IPD1M1) Robert A. Cepra 14E11 504-1416 Branch IESGB1 Project Directorate 1.2 (PD1-2) Charles L. Millr 14E19 504-1430
Project Directorate 1-3 (PD1-3) Walter R. Butler 14D3 504-1433 flAyftmfd no *vSW~mt Tre549dmn innOin Project Directorate 1-4 (PD1.4) John F. Stolz 14D7 504-2040 Director Ashok C. Thadani 8E1 504-2884 Deputy Director Gary Holahan 8E3 504-3228 Ass~ Dlreoor Reion WReactors 1ADf2) Technical Assistant Ralph Caruso 8F1 504-1813 Assistant Director Gus C. Linos 14H1 504-1453 Instrumentation and Control Scott Newberry 8H1 504-2821 Project Directorate 1131 IPD2-1i Elinor G. Adens m 14H12 504-1466 Systems Branch (SICS)
Project Directorate 11.2(PD2-2) Herbert H. Berkow 14H20 504 1485 Electrical System Branch (SELO) Faust Rove 7E1 504-2774 Project Directorate 13.3(PD2-3) David B. Matthews 14D19 504-1490 Plant Systems Branch (SPLB) Conrad E. McCracken 8D3 504-2873 Project Directorate 11-4(PD2-4) Frederick J. H bdon 14H14 504-2024 Reactor System Branch (SRXB) Robert C. Jones 8E21 5042895 DIVISION OF REACTOR PROJECTS - MI.IV. V (DRPW) DIVISION OF REACTOR INSPECTION AND SAFEGUARDS (DRISI
Director Bruce A. Bogar 13E1 504-1354 Director Brian K. Grimes 9E 504-2903 Technical Assistant Eric Leeds 113H25 504 1336 Deputy Director Vacant 9E3 504 2969 Special Assistant Leonard 1.Cobb 9A4 504-2972 Aeslaturt Dfeotor for Raion Reactors (AMD3 Vendor Inspection Branch (RVIB) Leid J. Norrholm 903 504-2961 Assistant Director John A. Zwolinaki 13H24 504-1335 Safeguards Branch (RSGB) Phillip F. McKee 9D25 504 2933 Project Directorate 111-1(PD3-11 Ladyard B. Marsh 13D17 5041340 Special Inspection Branch IRSIB) Eugene V. Irnbro 9E7 504 2967 Project Directorate 111-2(PD3-2) Richard J. Barrett 13D3 504 1395 Project Directorate Ilt33 (PD3-3) John N. Hannon 13E19 504-1389 DIVISION1 OF RADIATiON PROTECTION AND BfERGEN4CY PREPAREDNESS (DRMP
Director Frank J. Congel 10E1 5041088 A idow~ Ofrmnor for Radon IV & V R11eactors IADR4-51 Deputy Director Edward J. Butcher 10E13 504-1088 Assistant Director Martin J. Virgilio 13E3 504-1353 Technical Assistant Charol A. Wllis 10E3 5041091 Project Directorate IV-1 (PD4-I) John T. Larkins 13H1 504 1302 Emergency Preparedness Branch (PEPB) Robert A. Erickson 9H16 504-3924 Project Directorate IV-2 (PD4-2) Suzanne Black 13H14 5041318 Risk Applications Branch IPRAB) William D. Becknor 10E7 504-1089 Project Director V IPD5) Theodore RLQuay 13E17 5041372 Radiation Protection Branch (PRPB) Lmrnoine Cunningham 1003 5041086 DIVSINM OF ADVANCED REACTORS OhSPECIAL PROJECTS IOAR) DIVISION OF LICENSEE PERFORMANCE AND QUAUTY EVALWATION (ILPQ)
Director Dennis M. Crutchfiotd 11H20 5041199 Director Jack W. Roo 11OH1 5041004 Deputy Director William D. Trevers 11H11 5041117 Deputy Director Cecil 0. Thomas 1OH2 504-2548 Technical Assistant Joseph G. Giitter IlB15 5041113 Performance and Quality William Brach 108 5041017 Standardization Project Robert C. Pierson 11HI 5041118 Evaluation Branch ILPEB)
Directorate (PDST) Human Factors Ass nt Jared S. Wormiel 10H2 504-2180
Non-Power Reoctors. Soymour H. Wiss 11H1O 504-2170 Branch (LHFB)
Deconn rnsioning & Environrnantal Operator Licensing Branch (LOLB) Robert M. Gallo 10D19 5041031 Project Directorate (PDNPI
License Renewal Project John W. Craig 110D3 504M1183 Directorate (PDLA)
Advanced Reactors Project Jarnes E. Dyer 11ID21 504-1111
CONTACT
- Nancy Olson 5041275 Directorate IPOAR)
December 19, 1991 TO: ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTION PERMITS FOR
NUCLEAR POWER REACTORS
SUBJECT: INFORMATION TO
ADDRESSEES
REGARDING NEW TELEPHONE NUMBERS FOR
NRC OFFICES LOCATED IN ONE WHITE FLINT NORTH - GENERIC LETTER 91-19 The U.S. Nuclear Regulatory Commission (NRC) is issuing this Generic Letter to alert addressees to new telephone numbers for certain NRC offices located in One White Flint North (OWFN). All offices located in OWFN are affected. No specific action or written response is required.
The new phone system mandated by the General Services Administration (GSA)
will be provided by GSA's Washington Interagency Telecommunication's System (WITS). Enclosed is an NRR organizational listing providing new telephone numbers for key NRR managers. The WITS System is effective at 8:00 p.m.
Eastern Standard Time, on December 13, 1991. Also included for your information are the new telephone numbers for the Chairman, the Commissioners and the Executive Director for Operations.
Chairman Ivan Selin 301) 504-1759 Commissioner Kenneth C. Rogers 301) 504-1855 Commissioner James R. Curtiss 301) 504-1875 Commissioner Forrest J. Remick 301) 504-1820
Commissioner Gail dePlanque 504-1800
James M. Taylor, EDO (t3015)5u4-1700
Also, please note that the telephone numbers for the facsimile machines located in the Central Mail Facility at OWFN will be as follows:
Facsimile Type Telephone Verification No.
3M 9165 (301) 504-2260 (301) 504-2261
3M 9165 (301) 504-1137 (301) 504-2261 Fujitsu DEX 2400 (301) 504-2259 (301) 504-2261 Please contact Pam Foust (301) 504-1213, or the appropriate NRC Project Manager, if you have any questions regarding this matter.
Sincerely, Original signed by Steven A. Varqa for:
James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:
As stated tv()4 jDISTRIBUTION:
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