NRC Generic Letter 1987-010: Implementation of 10 CFR 73.57, Requirements for FBI Criminal History ChecksML031140365 |
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, Clinch River |
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Issue date: |
06/12/1987 |
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From: |
Miraglia F Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-87-010, NUDOCS 8706150058 |
Download: ML031140365 (5) |
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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, 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 [[: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 [[:Clinch River]] </code>. |
June 12, 1987
-.. f FBI CRIMINAL HISTORY C tS
TO ALL POWER REACTOR LICENSEES /; /7 /;2/77 Gentlemen:
Subject: IMPLEMENTATION OF 10 CFR 73.57, REQUIREMENTS
FOR FBI CRIMINAL HISTORY CHECKS (GENERIC LETTER 87-10)
Generic Letter 87-04 exempted temporary workers from the requirements of 10 CFR
73.57, "Requirements for FBI Criminal History Checks," on an interim basis pending resolution of final screening policy for this category of worker. A recent decision by the NRC to solicit public comment on its policy statement and industry guidelines on access authorization, may postpone this final resolution. The purpose of this generic letter is to authorize use of a temporary access authori- zation program until final screening policy is established.
A licensee may grant an individual temporary access authorization for unescorted facility access or access to Safeguards Information. This temporary access authorization is contingent upon submittal of fingerprints to NRC in accordance with 10 CFR 73.57 and maintenance of all security plan commitments pertaining to employee screening. The criminal history resulting from the FBI check must be considered immediately after receipt in conjunction with other evaluation criteria to determine if unescorted access should be continued or terminated.
This generic letter supersedes any previous generic letter (e.g., 87-04) on this subject. This policy is in effect until further notice by the NRC.
Sincerely, Frank J. Miraglia, Jr.
Associate Director for Projects Office of Nuclear Reactor Regulation RSGB s/f DCarlson LBush BManili GMcPeek RSkelton JGibson RDube RErickson BGrimes JPartlow RStarostecki FMiraglia JSniezek PDwyer, NMSS -rJ'O Crt'Z-
TMurley JZerbe, CRGR RFonner RBurnett, NMSS
- See previous concurrence pages. D\
~,- 4 OFC :RSGB x' :RSGB " :RSGB X :NMSS X :NMSS x :OGC x :DRIS
NAME :JGibson/bc :LBush :RErickson :PDwyer :RBurnett :RFonner :BGrim DATE :6/ /87 :6/ /87 :6/ /87 :6/ /87 :6/ /87 :6/ /87 /87 OFC :DRIS :ADT I:
NAME :JPartlow :RStarostecki: F laa DATE- ---_ --
_ -- --- ---- -- -----._
/87__6/_ - -- --- _ ------ --_6/_ _._ ____ ______ _._ ___ ______ __._
DATE :6/ /87 :6/ /87 :6/ I 87 ::::
LIST OF RECENTLY ISSUED GENERIC LETTERS
Generic Date of Letter No. Subject Issuance Issued To GL 87-09 SECTIONS 3.0 AND 4.0 OF THE 06/04/B7 ALL LlGHT
STANDARD TECHNICAL WATER REACTOR
SPECIFICATIONS ON THE LICENSEES AND
APPLICABILITY OF LCO AND APPLICANTS
SURVEILLANCE REQUIREMENTS
GL 87-08 IMPLEMENTATION OF 10 CFR 73.55 05/11/87 ALL POWER
MISCELLANEOUS AMENDMENTS AND REACTOR
SEARCH REQUIREMENTS LICENSEES
GL 87-07 INFORMATION TRANSMITTAL OF 03/19/87 ALL FACILITY
FINAL RULEMAKING FOR REVISIONS LICENSEES
TO OPERATOR LICENSING-1OCFR55 AND CONFORMING AMENDMENTS
GL 87-06 TESTING OF PRESSURE ISOLATION 03/13/87 ALL OPERATING
VALVES REACTOR
LICENSEES
GL 87-05 REQUEST FOR ADDITIONAL 03/12/87 LICENSEES OF
INFORMATION-ASSESSMENT OF OR'S.
LICENSEE MEASURES TO MITIGATE APPLICANTS FOR
AND/OR IDENTIFY POTENTIAL OL'S, AND
DEGRADATION MKI HOLDERS OF
CP'S FOR BWR
MARK I
CONTAINMENTS
GL 87-04 TEMPORARY EXEMPTION FROM 03/06/87 ALL POWER
PROVISIONS OF THE FBI CRIMINAL REACTOR
HISlORY RULE FOR TEMPORARY LICENCES
WORKERS
GL 87-03 VERIFICATION OF SEISMIC 02/26/87 ALL LICENSEES
ADEQUACY OF MECHANICAL AND NOT SUBJECT TO
ELECTRICAL EQUIPTMENT IN USI A-46 OPERATING REACTORS, USI A-46 REQUIREMENTS
GL 87-02 VERIFICATION OF SEISMIC 02/19/87 ALL HOLDERS OF
ADEQUACY OF MECHANICAL AND OPERATING
ELECTRICAL EQUIPMENT IN LICENSES NOT
OPERATING REACTORS (USI A-46) REVIEWED TO
CURRENT
LICENSING
CRITERIA ON
SEISMIC
QUALIFICATION
OF EQUIPMENT
FBI CRIMINAL HISTORY CA S
TO ALL POWER REACTOR LICENSEES
Gentlemen:
Subject: IMPLEMENIATION OF 10 CFR 73.57, REQUIREMENTS
FOR FBI C IMINAL HISTORY CHECKS (GENERIC LETTER 87- )
Generic Letter 87-04 e empted temporary workers from the r quirements of
10 CFR 73.57, "Requirem nts for FBI Criminal History Chec 5," on an interim basis pending resolution of final screening policy for t is category of worker.
A recent decision by the RC to solicit public comment its policy statement and industry guidelines on0access authorization, may p stpone this final reso- lution. The purpose of thi generic letter is to aut rize use of a temporary clearance program until fina screening policy is es blished.
A licensee may grant an indvi ual temporary clear ce for unescorted facility access or access to Safeguards formation. This emporary clearance is con- tingent upon submittal of finger ints to NRC in ccordance with 10 CFR 73.57 and maintenance of all security p n commitments ertaining to employee screen- ing. The criminal history resulti from the F check must be considered immediately after receipt to determ e if unes rted access should be continued or terminated.
This generic letter supersedes any pre ous eneric letter (e.g., 87-04) on this subject. This policy is in effect unti fu ther notice by the NRC.
Si erely, Frank G. Miraglia, Jr.
Associat Director for Projects Office of Nuclear Reactor Regulation DISTRIBUTION:
RSGE r/f RSGB s/f DC rlson LBush BManili GMcPeek R kelton JGibson RDube RErickson B nimes JPartlow RStarostecki FMiraglia Sniezek PDwyer, M
TMurle JZerbe, CRGR Fonner RBjrne t N S
2fD /Ylr^ A0^ I ow "LWaW
OFC :RSGB :RSGB :RSG :NMS S 5
, :OGC L 1 .DRIS
- -----:-- -- - ---.
NAME :JGibson/bc :LBush :RE on :PDwyer :RBurnett :RFonner :B limes DATE :6/l /87 :6// /87 :6 //7 :6/1 /87 :6/i /87 :6/1 /87 .6/ /87 OFC :DRIS- :ADT :9DP :
_____- wtbY t~~t---- -- -------- ------------ ------------ -----------
NAME :JPartl :RStrost cki:FMiraglia :
DATE :---- t :----- :6/ -/7 :- -------- ------------ ------------ -
DATE :6/ /87 :6/ ,/87 :6/ /87 ::::
I
June 12, 1987 A FBI CRIMINAL HISTORY CH N S
TO ALL POWER REACTOR LICENSEES
Gentlemen:
Subject: IMPLEMENTATION OF 10 CFR 73.57, REQUIREMENTS
FOR FBI CRIMINAL HISTORY CHECKS (GENERIC LETTER 87-10)
Generic Letter 87-04 exempted temporary workers from the requirements of 10 CFR
73.57, "Requirements for FBI Criminal History Checks," on an interim basis pending resolution of final screening policy for this category of worker. A recent decision by the NRC to solicit public comment on its policy statement and industry guidelines on access authorization, may postpone this final resolution. The purpose of this generic letter is to authorize use of a temporary access authori- zation program until final screening policy is established.
A licensee may grant an individual temporary access authorization for unescorted facility access or access to Safeguards Information. This temporary access authorization is contingent upon submittal of fingerprints to NRC in accordance with 10 CFR 73.57 and maintenance of all security plan commitments pertaining to employee screening. The criminal history resulting from the FBI check must be considered immediately after receipt in conjunction with other evaluation criteria to determine if unescorted access should be continued or terminated.
This generic letter supersedes any previous generic letter (e.g., 87-04) on this subject. This policy is in effect until further notice by the NRC.
Sincerely, Frank J. Miraglia, Jr.
Associate Director for Projects Office of Nuclear Reactor Regulation DISTRIBUTION:
RSGE r/f RSGB s/f DCarlson LBush BManili GMcPeek RSkelton JGibson RDube RErickson BGrimes JPartlow RStarostecki FMiraglia JSniezek PDwyer, NMSS
TMurley JZerbe, CRGR RFonner RBurnett, NMSS
- See previous concurrence pages.
OFC :RSGB x :RSGB x :RSGB x :NMSS x :NMSS x :OGC x :DRIS
____________ ____________ ____________ ____
____________ _ _ __ _ _ _ _ _
NAME :JGibson/bc :LBush :RErickson :PDwyer :RBurnett :RFonner :BGrim
____________ ____________ ____________ ____
____________ --- -----
DATE :6/ /87 :6/ /87 :6< /87 :6/ /87 :6/ /87 :6/ /87 : /87 OFC :DRIS :ADT
NAME :JPartlow :RStarostecki: a :
DATE :6/ /87 :61 /87 6/IT7
t
AO ,UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555 June 12, 1987 TO ALL POWER REACTOR LICENSEES
Gentlemen:
Subject: IMPLEMENTATION OF 10 CFR 73.57, REQUIREMENTS
FOR FBI CRIMINAL HISTORY CHECKS (GENERIC LETTER 87-10)
Generic Letter 87-04 exempted temporary workers from the requirements of 10 CFR
73.57, "Requirements for FBI Criminal History Checks," on an interim basis pending resolution of final screening policy for this category of worker. A recent decision by the NRC to solicit public comment on its policy statement and industry guidelines on access authorization, may postpone this final resolution. The purpose of this generic letter is to authorize use of a temporary access authori- zation program until final screening policy is established.
A licensee may grant an individual temporary access authorization for unescorted facility access or access to Safeguards Information. This temporary access authorization is contingent upon submittal of fingerprints to NRC in accordance with 10 CFR 73.57 and maintenance of all security plan commitments pertaining to employee screening. The criminal history resulting from the FBI check must be considered immediately after receipt in conjunction with other evaluation criteria to determine if unescorted access should be continued or terminated.
This generic letter supersedes any previous generic letter (e.g., 87-04) on this subject. This policy is in effect until further notice by the NRC.
Sincerely, Frank J.
Associate Director for Projects Office of Nuclear Reactor Regulation
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