NRC Generic Letter 1990-001: Request for Voluntary Participation in NRC Regulatory Impact SurveyML031140548 |
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: |
01/18/1990 |
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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-90-001, NUDOCS 9001120274 |
Download: ML031140548 (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 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 [[: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
v0A vNUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C.20555 January 18, 1990
TO: ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING
LICENSES, AND HOLDERS OF CONSTRUCTION PERMITS FOR LIGHT WATER
REACTOR NUCLEAR POWER PLANTS
SUBJECT: REQUEST FOR VOLUNTARY PARTICIPATION IN NRC REGULATORY IMPACT
SURVEY (GENERIC LETTER NO.90-01)
In 1981 the NRC conducted a survey of utility views of the impact of NRC
regulatory programs and initiatives on utility operations and resources.
As a result of that survey, the NRC made a number of changes in its organization and practices. To assess the effectiveness of those changes and to inquire into the impact of current NRC practices, the NRC recently conducted Regulatory Impact Surveys at 13 utilities throughout the country.
At each of the 13 utilities, senior managers from NRC headquarters and regional offices held group discussion sessions with a wide spectrum of individuals from the operator and engineer level up to senior corporate management. The NRC is currently evaluating the information gathered from these discussions to determine what changes, if any, should be made to the NRC's regulatory approach to enhancing the safe operation of nuclear power plants.
In order to augment the information gained from the survey of 13 utilities, the NRC is requesting that nuclear utilities, on a voluntary basis, complete the questionnaire provided in the enclosure to this letter. The purpose of this questionnaire is to provide the NRC with insight on the time which key nuclear power plant managers spend in responding to the various operational (or construction) inspections and audits (including those conducted by the company itself) that are Imposed upon them.
Your voluntary submittal of the completed questionnaire by March 1, 1990
will be greatly appreciated. Input from a broad base of licensees is needed to ensure that the results of this survey are representative of conditions across the industry. The information provided will not be directly associated with a particular nuclear power plant. A copy of the final survey report will be provided to you upon completion.
This request is covered by Office of Management and Budget Clearance Number
3150-0011 which expires January 31, 1991. The estimated average burden hours is 60 person hours per licensee response, including searching data sources, gathering and analyzing the information, and the requested reports.
Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch, Division of Information Support
1( 901120274 Z
- 2 - January 18, 1990
Services, Office of Information and Resources Management, U.S.
Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, D.C. Washington,
20503.
Sincerely, J ms G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures:
1. General Instructions/Questionnaire
2. List of Recently Issued Generic Letters
ENCLOSURE 1 NRC Regulatory Impact Survey General Instructions Item Number Instruction
1. A separate Questionnaire Sheet should be completed for each of the following applicable types of operational/
construction inspection, audit or evaluation:
- NRC Team Inspections - OSHA
- Other NRC Resident, - DOT
Regional and Headquarters - State/Local Authorities inspections/audits - NRC-Required QA Audits
- INPO Evaluations/Visits - Other Self-Assessments
- Insurers (ANI) - Other (Specify)
- EPA
2. Based upon actual experience over the past several years, in about how often is each of the activities identified Item #1 conducted? Answers need not be precise, but should provide general statements of recent experience, or such as "Two NRC Regional Office Inspections per Month"
"INPO Plant and Corporate Evaluations every 18 months."
3. Provide a brief description of the operations/construction These areas which are reviewed by the various activities.
descriptions need not be provided for NRC inspections and audits, INPO Evaluations, and NRC-required QA audits.
or
4. Provide information on the extent of the inspection, audit group evaluation in terms of the typical size of the review For and the length of time required to conduct the review.
consist example "NRC Regional Office inspections typically of two inspectors who are onsite for one work week."
5. This question seeks information on the extent to which the available time of key managers is necessarily devoted to in dealing with each of the specific review activities listed Item #1. For multiple positions, such as Plant Department Heads, provide an average annualized percentage for the group and the number of Department Heads included.
NRC Requlator ImpacSurvey Questionnaire Sheet
1. Type of inspection, audit or evaluation:
2. Based on actual experience over the past several years, about how often is this activity conducted?
3. Operations/Construction areas covered:
4. Extent of the activity (how many people, for how long)
5. Approximate percentage of total time (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item 4l.
a. Plant Department Heads (number involved)
b. Plant Manager c. Corporate Department Heads (number involved)
d. Corporate Vice Presidents (number involved)
e. Chief Nuclear Officer
LIST OF RECENTLY ISSUED GENERIC LETTERS
Generic Date of I'
Letter No. Subject Issuance - IssiUed To . f
89-23 NRC STAFF RESPONSES TO 10/23/89 ALL HOLDERS'"OF ,
QUESTIONS PERTAINING TO OPERATING LICENSEES
IMPLEMENTATION OF 10 CFR AND CONSTRUCTION
PART 26 - GENERIC LETTER PERMITS FOR NUCLEAR
89-23 POWER PLANTS
89-22 POTENTIAL FOR INCREASED ROOF 10/19/89 ALL LICENSEES OF
LOADS AND PLANT AREA FLOOD OPERATING REACTORS AND
RUNOFF DEPTH AT LICENSED HOLDERS OF CONSTRUCTION
NUCLEAR POWER PLANTS DUE TO PERMITS (EXCEPT BYRON
RECENT CHANGE IN PROBABLE BRAIDWOOD, VOGTLE,
MAXIMUM PRECIPITATION SOUTH TEXAS, AND RIVER
CRITERIA DEVELOPED BY THE BEND)
NATIONAL WEATHER SERVICE
(GENERIC LETTER 89-22)
89-21 REQUEST FOR INFORMATION 10/19/89 ALL HOLDERS OF
CONCERNING STATUS OF OPERATING LICENSES
IMPLEMENTATION OF UNRESOLVED AND CONSTRUCTION
SAFETY ISSUE (USI) REQUIREMENTS PERMITS FOR NUCLEAR
POWER REACTORS
89-20 PROTECTED AREA LONG-TERM 09/26/89 ALL FUEL CYCLE
HOUSEKEEPING FACILITY LICENSEES
WHO POSSESS, USE,
OR PROCESS FORMULA
QUANTITIES OF
STRATEGIC SPECIAL
NUCLEAR MATERIAL
89-19 REQUEST FOR ACTION RELATED TO 09/20/89 ALL LICENSEES OF
RESOLUTION OF UNRESOLVED OPERATING REACTORS,
SAFETY ISSUE A-47 "SAFETY APPLICANTS FOR
IMPLICATION OF CONTROL OPERATING LICENSES
SYSTEMS IN LWR NUCLEAR AND HOLDERS OF
POWER PLANTS" PURSUANT TO CONSTRUCTION PERMITS
10 CFR 50.54(f) FOR LIGHT WATER
REACTOR NUCLEAR
POWER PLANTS
89-18 RESOLUTION OF UNRESOLVED 09/06/89 ALL HOLDERS OF
SAFETY ISSUE A-17, "SYSTEMS OPERATING LICENSES
INTERACTIONS IN NUCLEAR OR CONSTRUCTION
POWER PLANTS PERMITS FOR NUCLEAR
POWER PLANTS
-2 - January 18, 1990
Services, Office of Information and Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503.
Sincerely, Odginal signed us James G.Partlow James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures:
1. General Instructions/Questionnaire
2. List of Recently Issued Generic Letters DISTRIBUTION:
Central Files ADP Reading GL Files PD32:DRSP (VPD32:DRSP PMAS:NRRk ADP:NRI
SSands:sam JWCraig HSmiith JGPart'
01/lI /90 01/11 /90 01/1/90
Template:GL-Nav