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| {{#Wiki_filter:I a.-October 31, 1983 TO ALL LICENSEES | | {{#Wiki_filter:aI |
| OF OPERATING | | . - |
| POWER REACTORS AND APPLICANTS | | October 31, 1983 FOR |
| FOR OPERATING
| | ALL LICENSEES OF OPERATING POWER REACTORS AND APPLICANTS |
| LICENSEES (GENERIC LETTER 83-38)SUBJECT: NUREG-0965, "NRC INVENTORY
| | TO LETTER 83-38) |
| OF DAMS" Enclosed for your information is a copy of the subject report which describes in detail the NRC Dam Safety Program. The information provided in this report was obtained from NRC files such as safety analysis reports. The primary purpose of the report is to identify all dams that could, in any way, be considered "NRC dams" in the context of the Guidelines of the Federal Dam Safety Program (Reference
| | OPERATING LICENSEES (GENERIC |
| 1). A secondary purpose is to identify the dams for which the Federal Guidelines may be applicable and for which the NRC might be considered "responsible".
| | DAMS" |
| As stated above this report is provided for information only; however, if you find that some data is incorrect, please inform the Dam Safety Officer, Mr. George E. Lear, via the Project Manager for your plant.rs i. '.''!isenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Reference
| | SUBJECT: NUREG-0965, "NRC INVENTORY OF |
| 1: Federal Coordinating Council for Science, Engineering and Technology, "Federal Guidelines for Dam Safety", June 25, 1979.a. 'ORB#1#P.Tam v# / /ORB#1:DL SVarga *K 09/ /83 AD DL d I D /83 se et 8310310403 scrcsa 6LtGcVr Det N ItL Se-re.O COACI~re4 ct./ | | which describes is a copy of the subject report Enclosed for your information Program. The information provided in this in detail the NRC Dam Safety The obtained from NRC files such as safety analysis reports. any way, report was to identify all dams that ofcould, in primary purpose of the report iscontext of the Guidelines the Federal be considered "NRC dams" in the1). A secondary purpose is to identify the Dam Safety Program (Reference may be applicable and for which the dams for which the Federal Guidelines NRC might be considered "responsible". |
| I t-TO ALL LICENSEES | | if this report is provided for information only; however, As stated above please inform the Dam Safety Officer, you find that some data is incorrect, Manager for your plant. |
| OF OPERATING | | |
| POWER REACTORS AND APPLICANTS | | Mr. George E. Lear, via the Project rs i. '.''!isenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation and |
| FOR OPERATING
| | 1: Federal Coordinating Council for Science, Engineering 25, 1979. |
| LICENSEES (GENERIC LETTER 83- )SUBJECT: NUREG-0965, "NRC INVENTORY | | |
| OF DAMS" Enclosed for your information is a copy of the subject report which describes in detail the NRC Dam Safety Program. The information provided in this report was obtained from NRC files such as safety analysis reports. The primary purpose of the report is to identify all dams that could, in any way, be considered "NRC dams" in the context of the Guidelines of the Federal Dam Safety Program (Reference | | Reference for Dam Safety", June Technology, "Federal Guidelines |
| 1). A secondary purpose is to identify the dams for which the Federal Guidelines may be applicable and for which the NRC might be considered "responsible". | | ' |
| As stated above this report is provided for information only; however, if you find that some data is incorrect, please inform the Dam Safety Officer via the Project Manager for your plant.Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Reference | | a. |
| 1: Federal Coordinating Council for Science, Engineering and Technology, "Federal Guidelines for Dam Safety", June 25, 1979.8310310403.AJ-, ,ofs~r/.ORB#12L PTam/l f iDL/83 AD/OR: DL GLainas 09/ /83 D: DL DEisenhut 09/ /83 Is4 14iLeer-ID 1/PAile/}} | | |
| | 8310310403 scrcsa |
| | 6LtGcVr Det N |
| | ORB#1:DL AD DL d ORB#1# |
| | P.Tam v SVarga *K |
| | 09/ /83 ID /83 |
| | # / / |
| | ItLSe-re.O COACI~re4 ct. se et |
| | / |
| | |
| | I |
| | t- AND APPLICANTS FOR |
| | TO ALL LICENSEES OF OPERATING POWER REACTORS) |
| | OPERATING LICENSEES (GENERIC LETTER 83- SUBJECT: NUREG-0965, "NRC INVENTORY OF DAMS" |
| | the subject report which describes Enclosed for your information is a copy of information provided in this in detail the NRC Dam Safety Program. The safety analysis reports. The report was obtained from NRC files such as all dams that could, in any way, primary purpose of the report is to identifythe Guidelines of the Federal be considered "NRC dams" in the context of purpose is to identify the Dam Safety Program (Reference 1). A secondary applicable and for which the dams for which the Federal Guidelines may be NRC might be considered "responsible". |
| | information only; however, if As stated above this report is provided for inform the Dam Safety Officer you find that some data is incorrect, please via the Project Manager for your plant. |
| | |
| | Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation for Science, Engineering and Reference 1: Federal Coordinating Council June 25, 1979. |
| | |
| | Technology, "Federal Guidelines for Dam Safety", |
| | 8310310403 |
| | .AJ-, ,ofs~r/. Is4 iDL AD/OR: DL D: DL |
| | ORB#12L DEisenhut 14iLeer- PTam/l f GLainas |
| | /83 09/ /83 09/ /83 ID 1/PAile/}} |
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| {{GL-Nav}} | | {{GL-Nav}} |
NRC Generic Letter 1983-038: NUREG-0965, NRC Inventory of Dams.ML031080533 |
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, 05000371, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River, Skagit, Marble Hill |
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Issue date: |
10/31/1983 |
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From: |
Eisenhut D Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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NUREG-0965 GL-83-038, NUDOCS 8310310403 |
Download: ML031080533 (2) |
|
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, 05000371, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River, Skagit, Marble Hill |
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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 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes 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 1995-021995-04-26026 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 [[:05000371]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] OR [[:Skagit]] OR [[:Marble Hill]] </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 [[:05000371]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
aI
. -
October 31, 1983 FOR
ALL LICENSEES OF OPERATING POWER REACTORS AND APPLICANTS
TO LETTER 83-38)
OPERATING LICENSEES (GENERIC
DAMS"
SUBJECT: NUREG-0965, "NRC INVENTORY OF
which describes is a copy of the subject report Enclosed for your information Program. The information provided in this in detail the NRC Dam Safety The obtained from NRC files such as safety analysis reports. any way, report was to identify all dams that ofcould, in primary purpose of the report iscontext of the Guidelines the Federal be considered "NRC dams" in the1). A secondary purpose is to identify the Dam Safety Program (Reference may be applicable and for which the dams for which the Federal Guidelines NRC might be considered "responsible".
if this report is provided for information only; however, As stated above please inform the Dam Safety Officer, you find that some data is incorrect, Manager for your plant.
Mr. George E. Lear, via the Project rs i. '.!isenhut Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation and
1: Federal Coordinating Council for Science, Engineering 25, 1979.
Reference for Dam Safety", June Technology, "Federal Guidelines
'
a.
8310310403 scrcsa
6LtGcVr Det N
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I
t- AND APPLICANTS FOR
TO ALL LICENSEES OF OPERATING POWER REACTORS)
OPERATING LICENSEES (GENERIC LETTER 83- SUBJECT: NUREG-0965, "NRC INVENTORY OF DAMS"
the subject report which describes Enclosed for your information is a copy of information provided in this in detail the NRC Dam Safety Program. The safety analysis reports. The report was obtained from NRC files such as all dams that could, in any way, primary purpose of the report is to identifythe Guidelines of the Federal be considered "NRC dams" in the context of purpose is to identify the Dam Safety Program (Reference 1). A secondary applicable and for which the dams for which the Federal Guidelines may be NRC might be considered "responsible".
information only; however, if As stated above this report is provided for inform the Dam Safety Officer you find that some data is incorrect, please via the Project Manager for your plant.
Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation for Science, Engineering and Reference 1: Federal Coordinating Council June 25, 1979.
Technology, "Federal Guidelines for Dam Safety",
8310310403
.AJ-, ,ofs~r/. Is4 iDL AD/OR: DL D: DL
ORB#12L DEisenhut 14iLeer- PTam/l f GLainas
/83 09/ /83 09/ /83 ID 1/PAile/
Template:GL-Nav