Withdrawn NRC Generic Letter 1989-017: Planned Administrative Changes to the NRC Operator Licensing Written Examination ProcessML031140236 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, Clinch River |
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Issue date: |
09/06/1989 |
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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-89-017, NUDOCS 8909060260 |
Download: ML031140236 (6) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 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 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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 [[: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 [[: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 [[: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 [[:Clinch River]] </code>. |
Text
Withdrawn NRC Generic Letter 1989-17, Planned Administrative Changes to the NRC Operator Licensing Written Exam Process, dated September 6, 1989, has been withdrawn.
ADAMS Accession Number: ML031140236 See Federal Register notice dated October 25, 2016 81 FR 73448
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555
- September 6, 1989 TO: ALL HOLDERS OF OPERATING LICENSES OR CONSTRUCTION PERMITS FOR PRESSURIZED WATER REACTORS (PWRs) AND BOILING WATER REACTORS (BWRs) AND ALL LICENSED OPERATORS.
SUBJECT:
PLANNED ADMINISTRATIVE CHANGES TO THE NRC OPERATOR LICENSING WRITTEN EXAMINATION PROCESS - GENERIC LETTER 89-17 A review of the operator licensing process identified significant improvements that could be realized by modifying the way in which the written examination is administered. One improvement is the separate administration of the section of the written examination that tests the examinees' knowledge of the fundamental principles applicable to all PWR or BWR plants.
This separate section of the written examination will be referred to as the Generic Fundamentals Examination Section (GFES) of the initial licensing examination. The GFES is designed to test the knowledge of material contained in the Components and Theory section of the initial written license examinations that were administered between February 1, 1982, and October 1, 1989, to both Reactor Operator (RO) and Senior Reactor Operator (SRO) applicants.
The NRC administered a pilot testing program for the GFES to both PWR and BWR volunteers in all five regions. These examinations were constructed from a bank of questions generated jointly by NRC and the Institute of Nuclear Power Operations JINPO), designed to support the GFES. The examinations were designed to be totally objective and machine-gradable, thereby allowing a prompt turnaround time for grading the examinations and generating individual item statistics. In addition, the NRC sent out feedback forms to all applicants who took the first pilot GFES, as well as to facility trainers and testing specialists. The results of a review of the item statistics and the feedback forms were used as constructive feedback to modify individual questions and validate the reliability of the GFES examination process.
Individuals participating in the GFES pilot program were allowed to either accept their score on the GFES and have it substituted for their score on the applicable section of their licensing written examination, or to take the full three sections of the written licensing examination. The NRC has concluded the pilot program for validating the GFES and will implement the GFES to test license applicants' knowledge of fundamental theory and components beginning after October 1, 1989.
For implementation of the new GFES, the NRC will modify the timing of steps to be taken for applying for a Reactor Operator or a Senior Reactor Operator license to operate a PWR or BWR reactor. Applicants for an Operator or Senior Operator License at Fort St. Vrain and non-power reactors will not be affected by the implementation of the GFES.
iU5OZ6O-
Generic Letter 89-17 September 6, 1989 After October 1, 1989, the first step in applying for a license under 10 CFR Part 55, Subpart D - Applications (55.31(a)(3)), will be for an authorized representative of the facility to submit a written request that the GFES of the written examination be administered to the applicant. The NRC will not be administering the fundamentals section (Section 1 for RO and Section 4 for SRO) in conjunction with the site-specific written examination after October 1, 1989, except as negotiated with the NRC regional offices up to but not beyond November 1, 1989.
NRC will also establish within the Operator Licensing Examiner Standards (NUREG-1021) eligibility requirements for taking the GFES.
Personnel wishing to register for the GFES must be enrolled in a facility-sponsored training program, the completion of which will satisfy the eligibility requirements for a Reactor Operator or a Senior Reactor Operator license.
The examinee will be allowed to take the GFES of the written licensing examination before completion of all training required for a license.
Submittal of a complete application for a license (NRC Form 398) before taking this section of the examination will not be required. However, the NRC will require a written request from an authoFTied representative of the ac-ility licensee by which the applicant will be employed that the fundamentals section of the written examination be administered.
The second step in applying for a license will be for the applicant to demonstrate proficiency in the material tested by the GFES. The applicant will be able to demonstrate this proficiency by having passed either of the two following examinations for the reactor type for which a license is sought.
- 1. An NRC-administered GFES on PWRs or BRMs.
- 2. An NRC written licensing examination for PWRs or BWRs administered between February 1, 1982, and October 1, 1989, completion of which resulted in licensing as a Reactor Operator or Senior Reactor Operator.
PLEASE NOTE: This requirement does not include NRC-administered Instructor Certification Examinations or Requalification Examinations.
The third step will be submittal of a license application (NRC Form 398).
Applicants for an operator or senior operator license will be required to document successful completion of the GFES on their application, NRC Form 398 (date passed), or successful completion of the fundamentals section of an NRC written examination administered between February 1, 1982, and October 1, 1989, as a result of which he or she received an NRC license.
Generic Letter 89-17 September 6, 1989 Following submittal of a license application (NRC Form 398), the applicant will be required to pass the site specific section of the initial licensing written examination, which test the candidate on material required for the safe, day-to-day operation of the specific plant for which a license is sought.
This section of the initial licensing examination will be referred to as the Site-Specific Examination Section (SSES) of the written examination and will test the material currently tested in Sections 2 and 3 (for RO applicants) or Sections 5 and 6 (for SRO applicants) of the written licensing examination.
Implementation of the GFES will have no effect on the operating test portion of the licensing process. The passing grade for the GFES of the written examination will be 80 percent. The passing grade for the SSES of the written examination will remain at 80 percent. The grade for the GFES will not be averaged into the SSES grade.
NRC will administer BWR and PWR GFESs three times annually, on Wednesday of the first full week in February, June, and October. The next GFESs will be administered Wednesday, October 4, 1989, in five regional locations.
This generic letter will be followed by a change to the Operator Licensing Examiner Standards (NUREG-1021) promulgating the sequencing of the steps to be taken in the licensing written examination process, including specifics on submitting names for registration and procedures for implementation.
Sincerely, Jam s G. Partlow, Associate Director f r Projects Office of Nuclear Reactor Regulation
Enclosure:
List of Most Recently Issued NRC Generic Letters Technical Contact: P. Doyle, Jr., NRR (301) 492-1047
Enclosure LIST OF RECENTLY ISSUED GENERIC LETTERS Generic Date of Letter No. Subject Issuance Issued To 89-17 PLANNED ADMINISTRATIVE 09/06/89 ALL HOLDERS OF CHANGES TO THE NRC OPERATOR OPERATING LICENSES LICENSING WRITTEN EXAMINA- OR CONSTRUCTION TION PROCESS - GENERIC PERMITS FOR PWRS LETTER 89-17 AND BWRS AND ALL LICENSED OPERATORS 89-16 INSTALLATION OF A HARDENED 09/01/89 ALL GE PLANTS WETWELL VENT (GENERIC LETTER 89-16) 88-20 GENERIC LETTER 88-20 08/29/89 ALL LICENSEES SUPPLEMENT 1 SUPPLEMENT NO. 1 HOLDING OPERATING (INITIATION OF THE INDIVIDUAL LICENSES AND PLANT EXAMINATION FOR SEVERE CONSTRUCTION VULNERABILITIES 10 CFR 50.54(f)) PERMITS FOR NUCLEAR POWER REACTOR FACILITIES 89-15 EMERGENCY RESPONSE DATA 08/21/89 ALL HOLDERS OF SYSTEM GENERIC LETTER NO. OPERATING LICENSES 89-15 OR CONSTRUCTION PERMITS FOR NUCLEAR POWER PLANTS CORRECT ACCESSION NUMBER IS 8908220423 89-07 SUPPLEMENT 1 TO GENERIC 08/21/89 ALL LICENSEES OF LETTER 89-07, NPOWER REACTOR OPERATING PLANTS, SAFEGUARDS CONTINGENCY APPLICANTS FOR PLANNING FOR SURFACE OPERATING LICENSES, VEHICLE BOMBS" AND HOLDERS OF CONSTRUCTION PERMITS 89-14 LINE-ITEMS TECHNICAL SPECIFI- 08/21/89 ALL LICENSEES OF CATION IMPROVEMENT - REMOVAL OPERATING PLANTS, OF 3.25 LIMIT ON EXTENDING APPLICANTS FOR SURVEILLANCE INTERVALS OPERATING LICENSES, (GENERIC LETTER 89-14) AND HOLDERS OF CONSTRUCTION PERMITS 89-13 GENERIC LETTER 89-13 7/18/89 LICENSEES TO ALL SERVICE WATER SYSTEMS POWER REACTORS PROBLEMS AFFECTING BWRS, PWRS, AND SAFETY-RELATED EQUIPMENT VENDORS IN ADDITION TO GENERAL CODES APPLICABLE TO GENERIC LETTERS
Generic Letter 89-1i September 6, 1989 Following submittal of a license application (NRC Form 398), the applicant will be required to pass the site specific section of the initial licensing written examination, which test the candidate on material required for the safe, day-to-day operation of the specific plant for which a license is sought.
This section of the initial licensing examination will be referred to as the Site-Specific Examination Section (SSES) of the written examination and will test the material currently tested in Sections 2 and 3 (for RO applicants) or Sections 5 and 6 (for SRO applicants) of the written licensing examination.
Implementation of the GFES will have no effect on the operating test portion of the licensing process. The passing grade for the GFES of the written examination will be 8° percent. The passing grade for the SSES of the written examination will remain at 80 percent. The grade for the GFES will not be averaged into the SSES grade.
NRC will administer BWR and PWR GFESs three times annually, on Wednesday of the first full week in February, June, and October. The next GFESs will be administered Wednesday, October 4, 1989, in five regional locations.
This generic letter will be followed by a change to the Operator Licensing Examiner Standards (NUREG-1021) promulgating the sequencing of the steps to be taken in the licensing written examination process, including specifics on submitting names for registration and procedures for implementation.
Sincerely, ORIGINAL SIGNED BY JAMES PARTLO%
List of Most Recently Lssettr Issued James G. Partlow, Associate Director LissuedM~ NRcGeneric for Projects Office of Nuclear Reactor Regulation Issued NRC Generic Letters Technical Contact: P. Doyle, Jr., NRR (301) 492-1047 DISTRIBUTION:
OLE RF PVDoyle DJLange KEPerkin Central Files TLSzymanski RACooley JWRoe WVJohnson AFGibson HJMiller LJCallan RZimnerman RMGallo TPeebles GWright JPJaudon DFKlrsch PEsselgroth RConte KBrockman CCasto TBurdick MJordan JPellet LMiller JMLanning DOYLE - 10 *SEE PREVIOUS PAGE FOR CONCURRENCE OFC : OLB:DLPQ : OLB:DLPQ : OLB:DLPQ : TECH EDITOR : RIR OGC NAME : PVDoyle:pvd* : DJLange* : KEPerkins*% : BCalure* :(WRoe* : RSmith*
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DATE : 7/11/89 : 7/11/89 : 7/12/89 : 7/13/89 : 7/21/89 : 8/02/89 OFC : GGB:NRR : ADT:NRR ADP:N -:
NAME : CBerlinger* : nliragl : JPartlo :
DATE : 7/27/89 : 8/5//89 : i//89 : :
Qf OFFICIAL FILE COPY f I' 4:3;