Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection PumpsML031050514 |
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, 05000349, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
06/24/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-038, NUDOCS 9706200203 |
Download: ML031050514 (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, 05000349, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[:05000349]] 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 [[:05000349]] 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 June 24, 1997 NRC INFORMATION NOTICE 97-38: LEVEL-SENSING SYSTEM INITIATES COMMON-
MODE FAILURE OF HIGH-PRESSURE-INJECTION
PUMPS
Addressees
All 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 alert
addressees to a recent incident in which two high-pressure-injection (HPI) pumps were
damaged as a result of an inaccurate letdown storage tank (LDST) level-sensing system.
The inaccuracy was caused by a drained reference leg. As a result, an incorrect level was
displayed, permitting the pumps to take suction from an empty tank. It is expected that
recipients will review this information for applicability to their facilities and consider actions, as
appropriate. However, suggestions contained in this information notice are not NRC
requirements; therefore, no specific action or written response is required.
Descdrition of Circumstances
On May 3, 1997, the licensee for Oconee Unit 3 was conducting a planned shutdown to
inspect an HPI line. During cooldown of the plant, HPI pump 3B was operating in the reactor
coolant system (RCS) makeup mode. The pump's discharge pressure dropped to the "low'
pressure setpoint initiating the automatic start of standby HPI pump 3A. The operators later
secured pump 3A when reactor coolant pump (RCP) seal injection flow indicated "high". The
HPI header pressure decreased again. HPI pump 3A automatically restarted. The pump's
motor current began oscillating. The operators secured HPI pump 3B because of an
indication of low motor current. Shortly afterwards, HPI pump 3A was also secured when its
motor current decreased sharply. The licensee issued a Notification of an Unusual Event
because of the loss of two of the three HPI pumps.
The licensee later concluded that both HPI pumps became hydrogen bound and possibly
damaged when they took suction from an empty LDST even though adequate tank inventory
was indicated.
De4e NOrTLdE 1-0o3' 970o6 4 U(WH)oLA .B~O~ 31O1 lMa rz I c - reP
Undi aqquafac @)
IN 97-38 June 24, 1997 Discussion
The HPI pumps at Oconee perform the dual functions of RCS makeup and high-pressure
safety injection. These pumps normally take suction from the LDST (also referred to as the
makeup or volume control tank by other vendors). A 25-psi (172.4 kPa) hydrogen
overpressure is maintained in this tank to scavenge oxygen from the RCS.
During this event, two level transmitters monitored tank level. These transmitters produce
level alarms in the control room. The alarms alert operators to initiate makeup to the LDST.
Both level transmitters shared a common reference leg. Because the shared reference leg
was partially drained, the indicated letdown tank level remained at 9 inches above the
low-level alarm setpoint. The tank was actually empty, its contents having been depleted
during normal charging. Letdown tank level was investigated only after both HPI pumps
developed problems.
Indicated level in the control room was derived from the equivalent pressure difference
between the drained reference leg and the back pressure from the 25 psi hydrogen
overpressure in the LDST. Because both level instruments shared the common reference
leg, both gave the same erroneous indication. Therefore, operators failed to provide makeup
inventory to the LDST. Two of the three HPI pumps became gas-bound, cavitated, and, as a
result, were structurally damaged.
If an actual safety injection actuation occurs, the suction isolation valve to the LDST remains
open while the suction isolation valve to the borated water storage tank (BWST) opens on the
safety injection signal. All three HPI pumps receive a start signal and take suction on both
the LDST and the BWST. With the two tanks cross-tied, the potential existed for this event to
have caused the loss of all HPI pumps as a result of gas binding. Loss of all three HPI
pumps could prevent the successful mitigation of a loss of coolant accident. During normal
operations, loss of all HPI pumps would result in the loss of reactor coolant pump seal
injection, normal RCS makeup, and normal boration.
The level transmitters were last calibrated in February 1997. Sometime between that last
calibration and the event, a leak developed from a scored cap on a test connection that
drained the reference leg. The cap was used to isolate the test connection. A drained
reference leg or a reference leg with entrained air can result in incorrect level indication.
Incorrect level indication will prevent appropriate setpoints being reached when process
conditions demand, defeat critical automatic safety functions, and could mislead plant
operators into taking less than conservative actions.
Pressure and level sensors, in any safety-related application, that rely on a reference leg for
a differential pressure reading, are sensitive to changes in reference leg level. Normal
surveillances that Include only channel checks with other instruments sharing the reference
leg or transmitter calibrations with external hydrostatic test sets will not reveal the true
condition of the reference leg. In the absence of an automatic reference leg fill system, periodic verification of reference leg level based on the plant-specific environment is needed
to ensure the operational integrity of the critical systems that are relied upon for manual and
automatic functions.
IN 97-38 June 24, 1997 This information notice requires no specific action or written response. If you have any
questions about information in this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Thomas Koshy, NRR
301-415-1176 E-mail: txkenrc.gov
Nick Fields, NRR
301-415-1173 E-mail: enfenrc.gov
Attachment: List of Recently Issue Information Notices
4' ln.44
I
Attachment
IN 97-38
.June 24, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-53, Retrofit to Amersham 660 06/23/97 All industrial radiography
Supp. 1 Posilock Radiography licensees
Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility
97-37 Main Transformer Fault 06/20/97 All holders of OLs or CPs
with Ensuing Oil Spill for nuclear power reactors
into Turbine Building
97-36 Unplanned Intakes by 06/20/97 All holders of OLs and CPs
Worker of Transuranic permits. All licensees of
Airborne Radioactive of nuclear power reactors
Materials and External in the decommissioning
Exposure Due to Inadequate stage and fuel cycle
Control of Work
97-35 Retrofit to Industrial 06/18/97 All industrial radiography
Nuclear Company (INC) licensees
IR100 Radiography Camera
to Correct Inconsistency
in 10 CFR Part 34 Compatibility
97-34 Deficiencies in Licensee 06/12/97 All holders of OLs or CPs
Submittals Regarding for test and research
Terminology for Radio- reactors
logical Emergency Action
Levels in Accordance
With the New Part 20
OL = Operating License
CP = Construction Permit
I
KU
IN 97-38 June 24, 1997 This information notice requires no specific action or written response. If you have any
questions about information in this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
original signed by S.H. Weiss for
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Thomas Koshy, NRR
301-415-1176 E-mail: txk@nrc.gov
Nick Fields, NRR
301-415-1173 E-mail: enf@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor has reviewed and concurred on 5/14197 DOCUMENT NAME: G:XNICKIOCONEE.IN *SEE PREVIOUS CONCURRENCES
To receive a co of this document. indicate In the box C=Coov wlo attachmentlendosure E=Coov with attachment/endosure N = No coy
OFFICE Tech x HICB* x PECB* DRPM
Contacts*
NAME NFields JWermiel AChaffee MSlosson 5
___ __ __ TK oshy _ _ _ _ _ _ _ _ _ _
DATE 06/09/97 06/09/97 06/12/97
-
V07 OFFICIAL KRCORU COPY
I
S . -
K-
-4 IN 97-xx
June xx, 1997 This information notice requires no specific action or written response. If you have any
questions about information in this notice, please contact one of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Thomas Koshy, NRR
301-415-1176 E-mail: txk@nrc.gov
Nick Fields, NRR
301-415-1173 E-mail: enfenrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:%NICKkOCONEE.IN *SEE PREVIOUS CONCURRENCES
To receive a conv of this document indicate in the box C=Coov wlo attachmentlenclosure E=Coov with attachmentlenclosure N = No copy
OFFICE Tech x HICB* l x PECB* DRPM
Contacts* ll
NAME NFields JWermiel AChaffee MSlosson
TKoshy
DATE 06/09/97 06/09/97 06112/97 4/ /97 OFFICIAL RECORD COPY
~ 6171k
K'J
IN 97-xx
- I June xx, 1997 This information notice requires no specific action or written response. If you have any
questions about information in this notice, please contact on6 of the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Thomas Koshy, NRR
301-415-1176 e-mail:txk@nrc.gov
Nick Fields, NRR
301-415-1173 e-mail:enfenrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\NICK\OCONEE.IN
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OFFICE Tech x HICB x PECB DRPM
Contacts l
4.5-A C)l
NAME NFields AT JWermiel J A haffee MSlosson
. TKoshyA UW P
67 DATE 61 /97 OF FICAL 7 41 /97 OFFICIAL 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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