Distribution of Sources & Devices Without AuthorizationML031050015 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
12/29/1997 |
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From: |
Cool D NRC/NMSS/IMNS |
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To: |
|
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References |
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IN-97-089, NUDOCS 9712220015 |
Download: ML031050015 (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, 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 Contamination2006-07-13013 July 2006 E-mail from M. 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 [[: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 [[: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>. |
. I
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 December 29, 1997 NRC INFORMATION NOTICE 97-89: DISTRIBUTION OF SOURCES AND DEVICES
WITHOUT AUTHORIZATION
Addressees
All sealed source and device manufacturers and distributors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to the situation of unauthorized sources and devices being distributed to specific
and general licensees, and the breakdown of the vendor's regulatory program that allowed such
distribution. This notice provides information that vendors of sources and devices may consider
to avoid distribution of products that have not been authorized. It is expected that recipients will
review the information for applicability to their licensed activities and consider actions, as
appropriate, to avoid similar problems. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action nor written response is required.
Description of Circumstances
A routine inspection of a vendor authorized to distribute products to specific and general
licensees revealed that the vendor distributed products that had not been distributed in
accordance with its license or certain commitments made in support of its application for safety
evaluation and registration of the products. After the inspection, a Confirmatory Action Letter
was issued, to the vendor, indicating the vendor's commitment to review all past distributions of
sources and devices to determine if the products were in accordance with its license and the
registration certificate, and to verify whether commitments made in support of its application for
safety evaluation and registration had been met. The vendor's investigation identified that:
(a) there were several hundred instances where products were distributed contrary to the
conditions in the registration certificate; and (b) certain of the vendor's commitments had not
been met. The deviations from the registration certificate identified by the licensee varied from
minor modifications to essentially complete redesigns. In addition, a number of the deviations
indicated potential health and safety concerns that required further review.
Several factors contributed to the improper distributions and commitments not being met.
These included: (a) the vendor's not having and maintaining a program sufficient to identify and
prevent distribution of products containing deviations from the registration certificate;
INOl5 T*1
.Gl
JT'qj 8
- 97-89 December 29, 1997 (b) uncertainty as to interpretations of information contained in the registration certificate and
the information submitted in support of the safety evaluation and registration of the product; and
(c) a lack of oversight and communication between the vendor and the manufacturer of the
products. The root cause of these factors seems to be not implementing an effective quality
assurance and quality control (QANQC) program.
The vendor's QA/QC program failed to ensure that products were distributed in accordance with
the approved designs, for several reasons. These included: (1) the vendor failed to verify the
validity of design information, submitted by former distributors, vis a vis the current design of
the products; (2) the vendor's audits of the manufacturer were not sufficiently In-depth to
identify changes in product design; and (3) the vendor relied on the manufacturer to compare
the actual design of the product being distributed with the design contained in the registration
certificate. As a result, the vendor committed to designs that, in some cases, did not accurately
reflect the current designs of the products. In addition, the manufacturer based its reviews on
the current designs of the products and not on the designs contained in the registration
certificates, and was unclear about the types of changes that should be identified to the
licensee. Therefore, the manufacturer did not identify differences between the previous designs
and the current designs and did not notify the vendor of all design changes that should have
been identified.
Subsequent to the inspection of the vendor, that identified the improper distributions, several
similar inspections of other vendors were performed. These inspections concentrated on the
QAJQC programs of the vendors and whether the vendors had distributed products that were
not authorized. Several of these inspections identified similar problems where a lack of an
effective QA/QC program or not following the QA/QC program led to a vendor distributing
products not in accordance with its license and/or the registration certificate for the product.
Discussion
Persons who distribute products that have been issued registration certificates must ensure that
distributed products are in accordance with the statements and representations contained in
their applications, as well as the provisions of the registration certificates for the products. This
requirement is codified in 10 CFR 32.210. Specifically, 10 CFR 32.210 requires, in part, that
applicants submit information concerning their quality control programs to the regulatory
authorities for review. This information must provide reasonable assurance to the reviewer that
the quality control programs are sufficient to ensure that distributed products are in accordance
with the approved designs. To this extent, a vendor's QANQC program should ensure that all
changes to the product are reviewed for safety implications, before implementing the change;
that changes which require amendment to the registration certificate are submitted .to the
regulatory authority for review; and that the changes submitted to the regulatory authority are
approved and included in the registration certificate before distribution of products that include
the change. Deviations from the approved design and processes may cause the product to be
unable to survive its intended conditions of use or may cause the radiation safety features of
the product to be ineffective.
When establishing QA/QC programs, manufacturers and distributors should be certain that they
contain the essential elements needed to ensure that products are distributed in accordance
K- 9789 December 29, 1997 with the approved designs. In addition, QANQC programs should periodically be reviewed, to
determine their effectiveness and to identify needed modifications or updates to reflect changes
such as new technology, manufacturing processes, and corporate reorganizations. Examples
of elements that are considered critical to an adequate QA/QC program include: design control;
a process to identify and address deviations; inspection and testing programs (performed on a
continuous or periodic basis); and periodic audits of the QA/QC program and the programs and
processes of suppliers, to ensure they remain effective. Additional guidance on what are
considered essential elements necessary for the establishment of an adequate QA/QC program
is contained in Regulatory Guide 6.9, "Establishing Quality Assurance Programs for the
Manufacture and Distribution of Sealed Sources and Devices Containing Byproduct Material.
It should be noted that vendors who do not have QA/QC programs that are adequate to ensure
that products are manufactured and distributed in accordance with the design and processes
approved by the regulatory authority, or that fail to follow their approved QAIQC programs, may
be subject to enforcement actions, including revocation of the approvals contained in their
registration certificates.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed below
or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Douglas Broaddus, NMSS
301-415-5847 E-mail: dab@nrc.gov
Attachments: # A1 § 44
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 97-89.IN
attachmenVendosure 'E -Copy with atachnent/enclosure
To receive a copy of this document, Indicate In the box: "CTa Copy wthWou vW No copy
OFFICE IMAB E IMAB C Tech Editor N IMOB E IMe
NAME DBroaddus ILCamper EKraus via FAX JPiccone Dot6--
DATE 12/10/97 12/ /97 12/10197 12/14/97 ILIWZ97 OFFICIAL RECORD COPY
1-~
IN 97-XX
December XX, 1997 When establishing QAIQC programs, manufacturers and distributors should be certain that
they contain the essential elements needed to ensure that products are distributed in
accordance with the approved designs. In addition, QA/QC programs should periodically be
reviewed, to determine their effectiveness and to identify needed modifications or updates to
reflect changes such as new technology, manufacturing processes, and corporate
reorganizations. Examples of elements that are considered critical to an adequate QA/QC
program include: design control; a process to identify and address deviations; inspection and
testing programs (performed on a continuous or periodic basis); and periodic audits of the
QA/QC program and the programs and processes of suppliers, to ensure they remain
effective. Additional guidance on what are considered essential elements necessary for the
establishment of an adequate QAIQC program is contained in Regulatory Guide 6.9, uEstablishing Quality Assurance Programs for the Manufacture and Distribution of Sealed
Sources and Devices Containing Byproduct Material."
It should be noted that vendors who do not have QAIQC programs that are adequate to
ensure that products are manufactured and distributed in accordance with the design and
processes approved by the regulatory authority, or that failpo follow their approved QA/QC
programs, may be subject to enforcement actions, includirfg revocation of the approvals
contained in their registration certificates.
This information notice requires no specific actionr nor written response. If you have any
questions about the information in this notice,,Rplease contact the technical contact listed
below or the appropriate regional office. /
Donald A. Cool, Director
Division of Industrial and
/ Medical Nuclear Safety
a* Office of Nuclear Material Safety
//' and Safeguards
Technical contact: pXglas Broaddus, NMSS
(301) 415-5847 E-mail: dabenrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME. :\WPDOCS\GENERIC.COM\97-XX.lN
To receive a copy of this document, Indlcate In the box: Tc" a Copy without ttachmnendcosure "E Copy with attach sncbure " = No copy
OFFICE IMAe E TIMAB 1 Tech Editor N EIMNS
NAME DBrEgtdus I-CamptEirEKraus via FAX t e DCool
DATE 12/10/97 12/ q /97 12/10/97 12/)497 / /97 O-RECORD COPY
- A,
kCoKment 1 IN 97-89 December 29, 1997 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-87 Second Retrofit to Industrial 12/12/97 All industrial radiography
Nuclear Company IR100 licensees
Radiography Camera, to
Correct Inconsistency in
10 CFR Part 34 Compatibility
97-86 Additional Controls for Transport 12/12/97 Registered users of the Model
of the Amersham Model No. 660 No. 660 series packages, and
Series Radiographic Exposure Nuclear Regulatory Commission
Devices industrial radiography licensees
97-75 Enforcement Sanctions Issued 09/24/97 All U.S. Nuclear Regulatory
as a Result of Deliberate Commission licensees
Violations of NRC Requirements
97-72 Potential for Failure 09/22/97 All holders of OLs or CPs
of the Omega Series for nuclear power reactors
Sprinkler Heads and fuel cycle facilities
97-65 Failures of High-Dose- 08/15/97 All high-dose-rate remote
Rate Remote Afterloading afterloader licensees
Device Source Guide Tubes, Catheters, and Applicators
97-64 Potential Problems 08/13/97 All U.S. Nuclear Regulatory
Associated with Loss Commission medical tele- of Electrical Power therapy licensees
in Certain Teletherapy
Units
97-61 U.S. Department of 08/06/97 All U.S. Nuclear Regulatory
Health and Human Commission medical
Services Letter, to licensees, veterinarians, Medical Device Manu- and manufacturers/distri- facturers, on the butors of medical devices
Year 2000 Problem
97-58 Mechanical Integrity of 07/31/97 Holders of and Applicants
In-Situ Leach Injection for Licenses for In-Situ
Wells and Piping Leach Facilities
V..-dthment 2 IN 97-89
. - December 29, 1997 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject - Issuance Issued to
97-88 Experiences During Recent 12/16/97 All holders of OLs for pressurized- Steam Generator Inspections water reactors except those who
have permanently ceased
operations and have certified that
fuel has been permanently
removed from the reactor
97-87 Second Retrofit to 12/12/97 All industrial radiography
Industrial Nuclear Company licensees
IR 100 Radiography Camera, to Correct Inconsistency in
10 CFR Part 34 Compatibility
97-86 Additional Controls for 12/12/97 Registered users of the Model
Transport of the Amersham No. 660 series packages, and
Model No. 660 Series Nuclear Regulatory Commission
Radiographic Exposure Devices industrial radiography licensees
97-85 Effects of Crud Buildup 12/11/97 All holders of OLs for pressurized- and Boron Deposition on water reactors, except those
Power Distribution and licensees who have permanently
Shutdown Margin ceased operations and have
certified that the fuel has been
permanently removed from the
reactor vessel
97-84 Rupture in Extraction 12/11/97 All holders of OLs for nuclear
Steam Piping as a power reactors except those
Result of Flow-Accelerated who have permanently ceased
Corrosion operations and have certified
that fuel has been permanently
removed from the reactor vessel
95-49, Seismic Adequacy of 12/10/97 All holders of OLs for nuclear
Sup. 1 Thermo-Lag Panels power reactors
OL = Operating License
CP = Construction Permit
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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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