Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action EstimatesML031110137 |
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 |
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Issue date: |
06/03/1999 |
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From: |
Matthews D Division of Regulatory Improvement Programs |
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To: |
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References |
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AL-99-002, NUDOCS 9906030181 |
Download: ML031110137 (8) |
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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 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 [[: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>. |
Text
Withdrawn NRC Administrative Letter 1999-02, Operating Reactor Licensing Action Estimates, dated June 3, 1999, has been withdrawn.
ADAMS Accession Number: ML031110137 See Federal Register notice dated October 25, 2016 81 FR 73448
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 June 3, 1999 NRC ADMINISTRATIVE LETTER 99-02: OPERATING REACTOR LICENSING ACTION ESTIMATES Addressees All power reactor licensees.
Purpose The U.S. Nuclear Regulatory Commission (NRC) is issuing this administrative letter to ask that licensees, on a voluntary basis, provide information pertaining to estimates of the number of licensing actions that will be submitted for NRC review in upcoming fiscal years. The submittal of this information is strictly voluntary. No specific action or written response is required.
Backaround In recent years, the NRC has undertaken a series of initiatives to improve the Commission's planning process. Beginning with the NRC Strategic Assessment and Rebaselining initiative in 1995, the NRC has implemented an integrated planning, budgeting, and performance measurement system to ensure that the business principles of goal setting, strategy development, resource assessment, and performance measurement undergird NRC activities.
These initiatives meet the requirements of the Government Performance and Results Act of 1993. Among other things, the integrated process results in an agency budget that is strongly tied to individual performance measures. To ensure that certain individual performance measures and resulting resource forecasts are as accurate as possible, the NRC periodically assesses the currency of the information and assumptions used in the performance plan and the budget development process.
One element in the strategic planning process with significant resource implications is the number of licensing actions reviewed by the Office of Nuclear Reactor Regulation (NRR) in a budget cycle. For planning purposes, licensing actions may be defined as requests for license amendment or extension, exemption, relief, review of a topical report submitted by a specific licensee, notice of enforcement discretion, or other licensee request requiring NRC review and approval before it can be implemented by the licensee. To improve the accuracy of the resource forecasts, the NRC is asking that all power reactor licensees, including those that have determined to permanently cease operations and have submitted certification pursuant to 10 CFR 50.82(a)(1), provide, on a voluntary basis, estimates of the number of new licensing action requests they plan to submit in upcoming fiscal years.
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AL 99-02 June 03, 1999 Page 2 of 3 Specifically, licensees are asked to provide an estimate of the number' of licensing actions expected to be submitted in Fiscal Years (FY) 20002 and 2001. To adequately capture the larger resource impact of certain licensing reviews, licensees are asked to identify by brief title those licensing actions that are expected to generate complex reviews, such as power uprate requests, license renewal requests, and dry cask storage applications.
Administrative Letter 98-03, Operating Reactor Licensing Action Estimates," issued May 6, 1998, asked for similar licensing action estimates. In the future, the NRC expects to ask for licensing action estimates on a semi-annual basis. The next solicitation will likely be issued in the fall of 1999 and will include voluntary submittals for the remainder of FY 2000 and 2001, and for FY 2002.
Licensees are asked to voluntarily provide their estimates of licensing action submittals to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555-0001, with a copy to Michael Boyle, U.S. Nuclear Regulatory Commission, Mail Stop 0-13E4, Washington, D.C. 20555-0001, within 45 days of receipt of this letter.
Paperwork Reduction Act Statement The voluntary information collections contained in this solicitation are covered by the Office of Management and Budget clearance number 3150-0011, which expires September 30, 2000.
The public reporting burden for this voluntary collection of information is estimated to average 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden, including suggestions for reducing this burden, to the Records Management Branch, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555-0001, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0011), Office of Management and Budget, Washington, D.C. 20503.
To assist in counting numbers of licensing actions, use the following example: a licensee submits a licensing action request covering three individual plants concerning a single subject. Although the NRC will review a single subject, NRC would open one work task for each plant, therefore counting this single request as three licensing actions.
2 NRC's fiscal year runs from October through September. FY 2000 will start October 1, 1999, and end September 30, 2000
AL 99-02 June 03, 1999 Page 3 of 3 This administrative letter requires no specific action or written response. If you have any questions about this letter, please contact Michael Boyle, NRR, by telephone (301-415-1401),
by e-mail (MLB40-nrc.aov). or by the appropriate NRR project manager.
David B. Matthews, Director Division of Regulatory Improv ent Programs Office of Nuclear Reactor Regulation
Attachment:
List of Recently Issued NRC Administrative Letters
Attachment AL 99-02 June 3, 1999 Page 1 of I LIST OF RECENTLY ISSUED NRC ADMINISTRATIVE LETTERS Administrative Date of Letter No. Subject Issuance Issued to 99-01 Reoriganization of the Office 4/9/99 All holders of operating licenses of Nuclear Reactor Regulation or construction permits for reactor facilities 95-05, Rev. 1 Revisions to Staff Guidance for 2/19/99 All holders of operating licenses Implementing NRC Policy on for nuclear reactors Enforcement Discretion 98-10 Dispositioning of Technical 12129/98 All holders of operating licenses Specifications That are Insufficient To Assure Plant Safety 98-09 Priority for NRR Review of 10/30/98 All holders of operating licenses Risk-informed Licensing Actions for nuclear power reactors 98-08 Availability of Revised NRC 10/09/98 All NRC licensees Form 3, "Notice to Employees" and Closure of NRC Walnut Creek Field Office 98-07 Interim Suspension of the 10/02/98 All holders of operating licenses Systematic Assessment of for nuclear power reactors Licensee Performance (SALP)
Program 98-06 Electronic Availability of 10/02/98 All holders of licenses for nuclear 10 CFR Part 21 and 10 CFR 50.55(e) power reactor and vendors for Notifications nuclear power reactors 98-05 Availability of Summarize 8/3/98 All holders of operating licenses In Electronic Format of Technical for nuclear power reactors Reports by the Office for Analysis and Evaluation of Operational Data OL = Operating License CP = Construction Permit
AL 99-02 June 03, 1999 Page 3 of 3 This administrative letter requires no specific action or written response. If you have any questions about this letter, please contact Michael Boyle, NRR, by telephone (301-415-1401),
by e-mail (MLB40-nrc.aov). or by the appropriate NRR project manager.
Original /s/'d by S.F. Newberry David B. Matthews, Director Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
Attachment:
List of Recently Issued NRC Administrative Letters DOCUMENT NAME: S:\DRPMSEC\99-02.al To receive a copy of this document, indicate in the box C=Copy w/o attachment/enclosure E=Copy with attachmentlenclosure N = No copy
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- OFFICE RlE REXiI_l jC:REXB I D:DLPM I D ;RIPI NAME MBoyle* WBurton* JLyons* LMarsh* JZwolinski* DM hek DATE 04/15/99 04/15/99 05/05/99 05/27/99 05/20/99 b/I21r*9 OFFICIAL RECORD COPY
AL 99-xx May xx, 1999 Page 3 of 3 This administrative letter requires no specific action or written response. If you have any questions about this letter, please contact Michael Boyle, NRR, by telephone (301-415-1401),
by e-mail (MLB4(&inrc.qov), or by the appropriate NRR project manager.
David B. Matthews, Director Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation
Attachment:
List of Recently Issued NRC Administrative Letters DOCUMENT NAME: G:\REXB\wvfb\ALLA.wpd To receive a copy of this document, indicate in the box C=Copy w/o attachment/enclosure E=Copy with attachment/enclosure N = No copy J See previous concurrence _ _ _ __ _ __ _ _ _ _ _ I_______
OFFICE REXB l RECB C:REXB D:DLP l D:DRIP NAME MBoyle* WBurton* JLyons* LMarsh JZwolin-ki DMatthews DATE 04/15/99 04/15/99 05/05/99 9PA99 /A 1 /A 9 9 I /99 OFFICIAL RECORD COPY
AL 99-xx May xx, 1999 Page 3 of 3 This administrative letter requires no specific action or written response. If you have any questions about this letter, please contact Michael L. Boyle, NRR, by telephone (301-415-1401), by E-mail (MLB4@nrc.gov), or by the appropriate Office of NRR project manager.
David B. Matthews, Director Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation List of Recently Issued NRC Administrative Letters DOCUMENT NAME: G:\WFB\ALLA2 To receive a copy of this document, indicate in the box C=Copy wlo attachmentienclosure E=Copy with attachment/enclosure N = No copy OFFICE Z ll REXB lI R W I C:REXB l D:DLPM I NAME MBoyle maa'WBurton V., il-Wnx TMarsh JZwolinski DATE 4499 I__ 1 s/,,99 , / 99 __ _ __99 ADPT D:DRIP I BSheron DMatthews
/ /99 1 /99 OFFICIAL RECORD COPY