Inadequate or Inappropriate Interim Fire Protection Compensatory MeasuresML070180068 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
07/09/1997 |
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From: |
Slosson M M Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-97-048, NUDOCS 9707020308 |
Download: ML070180068 (11) |
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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 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 [[: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>. |
9. '5UN.TED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001July 9, 1997NRC INFORMATION NOTICE 97-48:INADEQUATE OR INAPPROPRIATE INTERIM FIREPROTECTION COMPENSATORY MEASURESAll holders of operating licenses or construction permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) Is Issuing this Information notice to alertaddressees to potential problems associated with the Implementation of interim compensatorymeasures for degraded or Inoperable plant fire protection features or degraded or Inoperableconditions associated with post-fire safe-shutdown capability. It is expected that recipientswill review the informatioit for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained In this informationnotice are not NRC requiremnents; therefore, no specific action or wdtten response isrequired.
Description of Circumstances
The NRC foresaw cases in which fire protection features would be inoperable and allowedlicensees, through plant technical specifications (TS) or approved fire protection planscontrolled by license conditions, to implement alternative actions to compensate for theinoperable condition or component until permanent corrective actions are implemented. Ingeneral, the combination of appropriate compensatory measures and the defense-in-depthfire protection features provides an adequate level of fire protection until the licenseescomplete the corrective actions, For common types of deficiencies (e.g., an Inoperable firesuppression system), the specific compensatory measures are generally noted in either theTS or in the NRC-approved fire protection program. For unique plant-specific situations (e.g.,Inadequate cable separation), the appropriate compensatory measures are determined by thelicensee on a case-by-case basis. (This is discussed further later in the information notice.)NRC reviews of licensees' corrective actions to address degraded or Inoperable conditionsassociated with a plant's abilities to achieve and maintain post-fire safe shutdown have notedsome weaknesses in the interim compensatory measures. For example, some licenseeshave relied exclusivoly on the 1-hour roving fire watch as an interim compensatory measurefor deficiencies that affect their abilities to achieve and maintain post-fire safe shutdown andhave not considered or Implemented other appropriate interim compensatory measures, suchas briefing operators on degraded post-fire, safe-shutdown-system conditions; temporaryrepair procedures; temporary fire barriers; or detection or suppression systems. In addition,____ ?DE q=TE 91-011 911o(A(9707020308 dQV11111111111111111011 IN 07.48July 9, 197o MC kIspectlons of fire protection programs have found weaknesses In kliensees' fle watcht'Org programs and In the conduct of fire watch dutiee. Specific examples documented InNRC Inspection reports Include the following:ODutig a November 1996 Inspection at Waterford Generating Station (Inspection ReportW0-382/95-020, Accession No. 9603260040), NRC Inspectors found that the licensee'sprocedures redefined the
Intent
of a continuous fire watch. The licensees' procedurerequired a 15-minute roving fire watch, with a margin of 5 minutes, In lieu of a continuousfir watch. In addition, required fire watches were not performed in areas In which firedetection equipment was out of service and In areas In which fire barriers were degraded.This Issue Is currently under review by the NRC for disposition.* During an April 1996 Inspection at Palisades Nuclear Plant (Inspection Report 60-255/96-004, Accession No. 9805290105). the NRC Inspector noted that the licensee relied onfire watches as compensatory measures for a number of post-fire, safe-shutdown-designdeficiencies Identified by the licensee pursuant to Appendix R to Part 50 of T ", 10 of theCode f Federal Regulations (10 CFR Part 50) while long-term corrective actlukns werebeing evaluated. The licensee did not alert the operators to these deficient conditions nordid It provide interim shutdown strategies to operators on how to ouccossfully deal withpotential fire damage to required safe-shutdown components. The potential conse-quences could have been extensive since placing and maintaining the plant in post-firehot standby could only have bean achieved by significant operator actions, trouble-shooting, and repair activities to compensate for the post-fire, safe-shutdown-designdeficiencies. The sole use of a fire watch for a safe shutdown function which Is notadequately protected against fire damage is an Inappropriate application of acompensatory measure. This problem resulted in a Severity Level III Violation.* On October 17, 1998, Arkansas Nuclear One had an event involving a fire in a reactorcoolant pump (RCP) and inadequacies associated with the RCP oil collection system.The licensee's initial compensatory measures placed the lift olK pumps in the "stop"condition. This action enhanced the fire protection annunciator procedures by givingadditional guidance to the operators when responding to the RCP smoke detector alarm.However, the licensee did not propose Interim plant operational measures which wouldhelp operators identify and mitigate the consequence of potential oil leakage from theRCP oil system sites not protected by the RCP oil collection system. This problemresulted in a Severity Level III Violation.Discussion]In accordance with 10 CFR 50.48, "Fire protection," each operating nuclear power plant musthave a fire protection plan that satisfies Criterion 3 of Appendix A to 10 CFR Part 50.Licensees of plants licensed to operate before January 1, 1979, are required to satisfy theprovisions of Appendix R to 10 CFR Part 50, Section Ill.G, "Fire protection of safe shutdownI' .
IN 97-48July 9, 1997 capability;" Section Ill.J, "Emergency lighting;" and Section 111.0, "Oil collection system forreactor coolant pump;" and the provisions of Appendix A to the Branch Technical Position ofthe Auxiliary Power Conversion Systems Branch (BTP APCSB) 9.5-1, "Guidelines for FireProtection for Nuclear Power Plants Docketed Prior to July 1, 1978." Licensees of plantslicensed to operate after January 1, 1979, are required to satisfy the fire protection provisionsof their operating licenses. Generally, these plants have fire protection programs that satisfythe provisions of NUREG-0800, "Standard Review Plan (SRP)," Section 9.5.1; "FireProtection Program," July 1981.Appendix A to BTP APCSB 9.5-1 specifies that licensees should establish administrativecontrols for normal and abnormal conditions or such other anticipated operations asmodifications (e.g., breaking fire stops/penetration seals, Impairment of fire dete,'tion andsuppression systems) and refueling activities. The controls should be reviewed byappropriate levels of licensee management, and appropriate special actions and procedures,such as fire watches or temporary fire barriers, should be implemented to ensure adequatefire protection and reactor safety.On November 7, 1991, the NRC issued Generic Letter 91-18, "Information to LicenseesRegarding Two NRC Inspection Manual Sections on Resolution of Degraded andNonconforming Conditions and on Operability" (Accession No. 9111040293). This genericletter contained two sections, "Resolution of Degraded and Nonconforming Conditions" and"Operable/Operability: Ensuring the Functional Capability of a System or Component," to beincluded in Part 9900, "Technical Guidance," of the NRC Inspection Manual. These additionsare based upon previously issued guidance.With respect to fire protection and post-fire, safe-shutdown capability, the licensee maydiscover a previously unanalyzed condition. Under these conditions, Part 9900, "TechnicalGuidance: Resolution of Degraded and Nonconforming Conditions," Section 4.4, "Discoveryof an Existing But Previously Unanalyzed Condition or Accident," notes that the licensee,upon discovering an existing but previously unanalyzed condition that significantlycompromises plant safety, shall report that condition in accordance with 10 CFR 50.72 andshall place the plant in a safe condition. Once a degraded or nonconforming condition ofspecific structures, systems, or components (SSCs) is Identified, an operability determinationshould be made as soon as possible, consistent with the safety Importance of the SSCaffected. For SSCs that are outside plant TS, engineering judgment must be used todetermine safety significance.Part 9900, "Technical Guidance: Resolution of Degraded and Nonconforming Conditions,"Section 4.8, "Reasonable Assurance of Safety," states that for SSCs which are not expresslysubject to TS and which are determined to be Inoperable, the licensee should assess thereasonable assurance of safety. If the assessment assures safety, then the facility maycontinue to operate while prompt corrective action is taken. As stated in Part 9900, thefollowing items are to be considered for such assessments: the availability of redundant orbackup equipment, compensatory measures (including limited administrative controls), andthe conservatism and margins.
UIN 97-48July 9, 1997 This Information notice requires no specific action or written response. If you have anyquestions about the Information In this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager."Mi ee M. solosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Darrell Schrum, Rill(630) 828-9741E-mail: dls3@nrc.govRogello Mendez, Rill(630) 829-9745E-mail: rxm@nrc.govPatrick Madden, NRR301-415-2854E-mail: pmmMnrc.govAttachment: List of Recently Issued NRC Information Notices
AttachmentIN 97-48July 9, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformationNotice No.Date ofIssuanceSubjectIssued to97-4797-4696-44,Supp. 197-4597-4497-4397-42Inadequate PunctureTests for Type BPackages Under 10 CFR71.73(c)(3)Unisolable Crack inHigh-PressureInjection PipingFailure of ReactorTrip Breaker fromCracking of PhenolicMaterial In SecondaryContact AssemblyEnvironmentalQualificationDeficiency forCables and Contain-ment PenetrationPigtailsFailures of GammaMetrics Wide-RangeLinear Neutron FluxChannelsLicense ConditionComplianceManagement WeaknessesResulting In Failureto Comply with ShippingRequirements for SpecialNuclear Material06/27/9707/09/9707/02/9707/02/9707/01/9707/01/9706/27/97All "users and fabricators"of type B transportationpackages [as defined In10 CFR 171.11(60)(8)]All holders of OLs or CPsfor nuclear power reactorsAll holders of OL permitsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor test and researchreactorsAll holders of OLs or CPsfor nuclear power reactorsAll fuel cycle conversion,enrichment, and fabricationfacilitiesOL -Operating LicenseCP -Construction Permit
IN 97-48July 9, 1997 This information notice requires no specific action or written response. If you have anyquestions about the Information In this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.original signed by S.H. Weiss forMarylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Darrell Schrum, RIIl(630) 828-9741E-mail: dis3@nrc.govRogelio Mendez, RIIl(630) 829-9745E-mail: rxmonrc.govPatrick Madden, NRR301-415-2854E-mail: pmm@nrc.govAttachment: List of Recently Issued NRC Information NoticesTech Editor has reviewed and concurred on 01/28/97* -See pervious concurrenceDOCUMENT NAME: 97-48.1NTo Ituveasm pof Agocufm k ot s Inb am born T, a Copy W~outischment/.ncioswe *I a Copy w/o I Ichment/ancdoeure N" a No CopyOFFICE TECH CONTS IC/PECB:DRPM AD:DRPMI NAME TGreen* AChaffee* MSIosson*PMadden*DTF 02/03/97 062397 0/ 9702/04/97 ................. Z "IIUNI!LIAL KLLUXU LUPY
IN 97-June ,1997 This information notice requires no specific action or written response. If you have anyquestions about the Information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Darrell Schrum, Rill(630) 828-9741E-mail: dls3@nrc.govRogello Mendez, Rill(630) 829-9745E-mail: rxm@nrc.govPatrick Madden, NRR301-415-2854E-mail: pmm@nrc.govAttachment: List of Recently Issued NRC Information Notices'- See pervious concurrenceLOFC PECB:DRPM SPLB:DSSA DIDSSA C/PECB:DRPMNAME T. Greene* P. Madden* G. Holahan' Chaffee C4DATE 2/03/97 2/04/97 5/25/97 "97I,OFC D/DRPMNAME M. SlossonDATE 6/ 197I'll --) (0/0? W
IN 97-June ,1997 )DOCUMENT NAME: G:\TAGYINFIRE.TAG
IN 97-May ,1997 )DOCUMENT NAME: G:\TAG\INFIRE.TAG
IN 97-April .1997 This Information notice requires no specific action or written response. If you have anyquestion about the information In this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts:Darrell Schrum, Rill(630) 828-9741E-mail: dls3@nrc.govRogello Mendez, Rill(630) 829-9745E-mail: rxm~nrc.govPatrick Madden, NRR(301) 415-2854E-mail: pmm@nrc.govAttachment: List of Recently Issued NRC Information Notlcas* -See pervious concurrenceOFC PECB:DRPM SPLB:DSSA DqW ' ' C/PECB:DRPMNAM T. Greene* P. Madden* lahan A. ChaffeeE -__-DATE 2/03/97 2104/97 1 7 2/ /97OFC D/DRPMNAM -rh~nEDATE 2/ /97[OFFICIAL RECORDDOCUMENT NAME:COPY)G:ATAG\INFIRETAG
IN 97-febre , 1997 ]DOCUMENT NAME: G:\TAG\INFIRE.TAG
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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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