Exemptions from Requirements of Section 70.24 of Title 10 of the Code of Federal RegulationsML031050073 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
10/10/1997 |
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From: |
Roe J Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-077, NUDOCS 9710090217 |
Download: ML031050073 (7) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 October 10, 1997 NRC INFORMATION NOTICE 97-77: EXEMPTIONS FROM THE REQUIREMENTS OF
SECTION 70.24 OF TITLE 10 OF THE CODE OF
FEDERAL REGULATIONS
Addressees
All holders of operating licenses for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees about actions the staff plans to take regarding enforcement actions and the granting
of exemptions from the requirements of Section 70.24 of Title 10 of the Code of Federal
Reaulations (10 CFR 70.24). This information notice does not transmit or imply any new or
changed requirements or staff positions. No specific action or written response Is required.
Descrintion of Circumstances
Regulations in 10 CFR 70.24 require that each licensee authorized to possess more than a
small amount of special nuclear material maintain in each area in which such material is
handled, used, or stored a criticality monitoring system that will energize alarm systems if
accidental criticality occurs. The staff has issued approximately 20 notices of violation for
failures by licensees to meet the provisions of 10 CFR 70.24. Since the issuance of these
notices of violation, the staff has found it appropriate to exercise enforcement discretion
pursuant to Section V\1 B.6 of the Enforcement Policy, NUREG-1600, 'General Statement of
Policy and Procedure for NRC Enforcement Actions."
Discussion
As stated in a policy issue information paper, dated July 21, 1997, from the Executive Director
for Operations, NRC, to the NRC Commissioners (SECY-97-155), the staff has determined that
it is appropriate to exercise enforcement discretion in this case because the safety significance
of the failure to meet 10 CFR 70.24 is minimal provided controls are in place to ensure
compliance with general design criteria (GDC) 62. Also, enforcement discretion is appropriate
because the NRC staff did not recognize the need for an exemption during the licensing
process; because the NRC previously took a position on this matter, as reflected in its
Mt_9710090217J~~ PMg ig. Ie-01alto01 s,¢k l
?mo onIlDInlXDO!V!
IN 97-77 October 10, 1997 letter of May 11, 1988, to the Tennessee Valley Authority (NRC Accession No. 8902240029)
concerning the lack of a need for an exemption at the Browns Ferry Nuclear Plant; and because
of the staffs intent to embark on rulemaking to amend 10 CFR 70.24.
The staff intends to withdraw the previously issued violations. As specified in SECY-97-155, the
staff does not intend to take further enforcement action for failure to meet 10 CFR 70.24 provided licensees obtain an exemption from this regulation before the next receipt of fresh fuel
or before the next planned movement of fresh fuel. The criteria that the staff is using to
evaluate exemptions from 10 CFR 70.24 are given in SECY-97-155 and are presented for
information in the attachment to this notice.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate regional office.
Jack W. Roe, Acting Director
4t Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact G. Wunder, NRR
301-415-1494 E-mail: gfw@nrc.gov
Attachments:
1. Staff Criteria for Evaluating Exemptions from 10 CFR 70.24
2. List of Recently Issued NRC Information Notices
Attachment I
IN 97-77 October 10, 1997 STAFF CRITERIA FOR EVALUATING EXEMPTIONS FROM 10 CFR 70.24 AS STATED IN SECY-97-155
1. Plant procedures do not permit more than [1 PWR or 3 BWRJ new fuel
[assembly/assemblies] to be in transit between their associated shipping cask and dry
storage rack at one time.
2. The k-effective of the fresh fuel storage racks filled with fuel of the maximum permissible
U-235 enrichment and flooded with pure water does not exceed 0.95, at a 95 imerrent
probability, 95 percent confidence level.
3. If optimum moderation of fuel in the fresh fuel storage racks occurs when the fresh fuel
storage racks are not flooded, the k-effective corresponding to this optimum moderation
does not exceed 0.98, at a 95 percent probability, 95 percent confidence level.
4. The k-effective of spent fuel storage racks filled with fuel of the maximum permissible
U-235 enrichment and filled with pure water does not exceed 0.95, at a 95 percent
probability, 95 percent confidence level.
5. The quantity of forms of special nuclear material, other than nuclear fuel, that are stored
on site in any given area is less than the quantity necessary for a critical mass.
6. Radiation monitors, as required by GDC 63, are provided in fuel storage and handling
areas to detect excessive radiation levels and to initiate appropriate safety actions.
7. The maximum nominal U-235 enrichment is 5 wt percent.
I Attachment 1 IN 97-77 October 10, 1997 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-76 Crediting of Operator 10/14197 All holders of OLs for
Actions in Place of nuclear power reactors
Automatic Actions and except those who have
Modifications of Operator permanently ceased
Actions, Including Response operations and have
Times certified that fuel has
been permanently removed
from the reactor vessel
97-75 Enforcement Sanctions 09/24197 All U.S. Nuclear
Issued as a Result of Regulatory Commission
Deliberate Violations licensees
of NRC Requirements
97-74 Inadequate Oversight 09/24/97 All holders of OLs for
of Contractors During nuclear power reactors
Sealant Injection except those who have
Activities permanently ceased
operations and have
certified that fuel
has been permanently
removed from the
reactor vessel
97-73 Fire Hazard in the Use 09123/97 All holders of OLs for
of a Leak Sealant nuclear power reactors
except those who have
permanently ceased
operations and have
certified that fuel
has been permanently
removed from the
reactor vessel
OL = Operating License
CP = Construction Permit
J K)
IN 97-77 October 10, 1997 letter of May 11, 1988, to the Tennessee Valley Authority (NRC Accession No. 8902240029)
concerning the lack of a need for an exemption at the Browns Ferry Nuclear Plant; and because
of the staff's intent to embark on rulemaking to amend 10 CFR 70.24.
The staff intends to withdraw the previously issued violations. As specified in SECY-97-155, the
staff does not intend to take further enforcement action for failure to meet 10 CFR 70.24 provided licensees obtain an exemption from this regulation before the next receipt of fresh fuel
or before the next planned movement of fresh fuel. The criteria that the staff is using to
evaluate exemptions from 10 CFR 70.24 are given in SECY-97-155 and are presented for
information in the attachment to this notice.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate regional office.
original signed by D.B.Matthews for
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: G. Wunder, NRR
301-415-1494 E-mail: gfw@nrc.gov
Attachments:
1. Staff Criteria for Evaluating Exemptions from 10 CFR 70.24
2. List of Recently Issued NRC Information Notices
- See previous concurrence DOCUMENT NAME: G:\NICK\7024.lN2 To receive a copv of this document indicate in the box C=Copy wlo attachment/endosure E=Oopy with attachmentlenclosure N = No copy
=
OFFICE PM:PDII ]l PD:PDII D:OE I PECBII
NAME GWunder* SBajwa* JLieberman* RLDennig*
DATE 10/08197 10/08/97 10/08197 10/08/97 OFFICE C:PECB I D:DRPE I D:DRPM I I
NAME SARichards* BBOGER* JWROE[ I
DATE 10/09/97 10/08/97 110_-__II
OFFICIAL RECORD OPY
K>
IN 97-xx
October xx, 1997 letter of May 11, 1988, to the Tennessee Valley Authority (NRC Accession No. 8902240029)
concerning the lack of a need for an exemption at the Browns Ferry Nuclear Plant; and because
of the staff's intent to embark on rulemaking to amend 10 CFR 70.24.
The staff intends to withdraw the previously issued violations. As specified in SECY-97-155, the staff does not intend to take further enforcement action for failure to meet 10 CFR 70.24 provided licensees obtain an exemption from this regulation before the next receipt of fresh fuel
or before the next planned movement of fresh fuel. The criteria that the staff is using to
evaluate exemptions from 10 CFR 70.24 are given in SECY-97-155 and are presented for
information in the Attachment to this notice.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate regional office.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
G. Wunder
301-415-1494 E-mail: gfwvnrc.gov
Attachments:
1. List of Recently Issued NRC Information Notices
2. Staff Criteria for Evaluating Exemptions from 10 CFR 70.24
- See previous concurrence DOCUMENT NAME: G:WNICKX7024.IN2 To receive a copy of this document, Indicate In the box C=Copy wlo attachmentlenclosure E=Copy with attachmentenclosure N = No copy --I
OFFICE PM:PDI ] PD:PDII D:OE PECB
NAME GWunder* SBajwa JLieberman RIDennig
DATE 1 0/08/97 10/08/97 10108/97 10/08/97 OFFICE C:PECB D:DRPE D:DRPM l
NAME SARichards* BBOGER* JWROE
DATE 10109/97 10108197 10/ 97 OFFICIAL RECORD COPY
<2 IN 97-xx
October xx, 1997 letter of May 11, 1988, to the Tennessee Valley Authority (NRC Accession No. 8902240029)
concerning the lack of a need for an exemption at the Browns Ferry Nuclear Plant; and because
of the staffs intent to embark on rulemaking to amend 10 CFR 70.24.
The staff intends to withdraw the previously issued violations. As specified in SECY-97-155, the staff does not intend to take further enforcement action for failure to meet 10 CFR 70.24 provided licensees obtain an exemption from this regulation before the next receipt of fresh fuel
or before the next planned movement of fresh fuel. The criteria that the staff is using to
evaluate exemptions from 10 CFR 70.24 are given in SECY-97-155 and are presented for
information in the Attachment to this notice.
This information notice requires no specific action or wriftenresponse. If you have any
questions about the information in this notice, please contact he person listed below or the
appropriate regional office.
Jack W. Roe, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
G. Wunder
301-415-1494 E-mail: gfw@nrc.gov
Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:VN1CKX7024.lN2 To receive a copy of this document. Indicate In te box C=Copy wlo attachment/enclosure E=Copy with attachmentlenpr, NNo cpy
OFFICE PM:PDII PD:PDII D:Ol
NAME GWunder SBajwa JCie man RLDennig
DATE J100197 j 10f'/97 10/6/97 101 /97 OFFICE C:PECB l J ID:DRPE l D:DRPM 1 NAME SARichards; BBOGEF/ ' JWROE
DATE 10/9/97 10/4/97 l10/ /97 O FICIAL RECORD COPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
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