Inadvertent Drainages of Spent Fuel PoolsML031150190 |
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/18/1988 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-88-065, NUDOCS 8808120327 |
Download: ML031150190 (10) |
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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, 05000000, Zimmer, 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 [[:05000000]] OR [[:Zimmer]] 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 [[:05000000]] OR [[:Zimmer]] 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 August 18, 1988 NRC INFORMATION NOTICE NO. 88-65: INADVERTENT DRAINAGES OF SPENT FUEL POOLS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors and fuel storage facilities.
Purpose
This information notice is being provided to alert addressees to potential
problems resulting from unintentional draining of spent fuel pools (SFPs).
It is expected that recipients will review the information for applicability
to their facilities and consider actions, as appropriate, to avoid similar
problems. However, suggestions contained in this information notice do not
constitute NRC requirements; therefore, no specific action or written response
is required.
Description of Circumstances
Wolf Creek - On December 22, 1987 the licensee, Kansas Gas and Electric, un- intentionally lowered the level of water in the SFP to an estimated minimum
height of 22 feet above the stored fuel. The licensee determined that a valve
in the return line to the refueling water storage tank (RWST) had been inadver- tently left open two days earlier after operations to clean up the RWST inven- tory through the SFP clean up system. The licensee stopped the drainage by
closing this valve.
The safety-related area radiation monitors near the SFP did not alarm. In
the control room, the SFP level indicator and the low level alarm on the SFP
cooling system pump suction were both inoperable. The control room operators
were alerted to this event by the successive tripping of SFP cooling system
pump A while they were operating the SFP clean up system.
River Bend - On September 20, 1987 the licensee, Gulf States Utilities, while
preparing for refueling, intentionally lowered the level in the upper SFP to
2 feet below the normal level of 185 feet to allow for the expected water dis- placement when the steam dryer assembly would be transferred there. This
caused the level indicator in the control room to go off scale as expected
and the related low level alarm to activate as expected. Pool level indi- cation is provided for a narrow range: 185 feet +/- 12 1/2 inches. The alarm
is set at 184 feet 7 1/2 inches when the level decreases.
8808120327 \ _ D
( X '(g
-' IN 88-65 August 18, 1988 After placing the steam dryer in the pool, the
valves from the condensate storage tank (CST) plant operators opened two
with the intent of then closing
two valves in the SFP purification suction line
minutes, while the four valves were opened, the (see Figure 1). Within 20
5 feet, partially uncovering the dryer assembly. level decreased an additional
monitors at both ends of the pool alarmed and Safety-related area radiation
indicated fields of about
80 mr/hr.
The drainage had been made possible by a procedural
free flow path in conjunction with a nonredundant sequence establishing a
vent pipe under water) in the suction line of antisiphon device (a vertical
antisiphon device had been plugged. the SFP purification system. The
The operator in the control room was not aware
level indicator was off scale. At the time of of the pool draining because the
the SFP area radiation monitor
alarms, however, an operator at an auxiliary equipment
a water level increase in the CST. Realizina control panel noticed
that this combination of signals
meant the SFP was draining, operators closed the
two
purification system suction line to stop the draining. manual valves in the SPF
in about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> using one SFP purification pump They restored the level
drawing suction from the CST.
Discussion:
In addition to the two events discussed above, spent fuel pool occurred at San Onofre 3 on Juneanother partial drainage of the
can cause potentially high radiation doses and 22, 1988. Drainage of SFPs
damage to fuel elements result- ing from the uncovery of spent fuel in storage
Although the consequences of the events describedor, in particular, in transit.
were not significant, they indicate deficiencies in this information notice
refueling operations and SFP safety. in control and management of
At San Onofre, the SFP cooling system design
was apparently properly siphon- protected, but the SFP purification system design
Bend, antisiphon devices in the SFP purification apparently was not. At River
preoperational testing but were not unplugged system were plugged to permit
at the beginning of refueling
operations.
Operating procedures for the interconnected systems
were not sufficiently detailed or were incorrect associated with SFPs either
ments causing unintentional drainage. At River and failed to prevent align- Bend, indication was limited. Detailed operating procedures the range of SFP level
not correct. At Wolf Creek, detailed operating were available but were
procedures did not exist.
Surveillance procedures were not implemented to
instrumentation and control equipment. At Wolf ensure the operability of all
lance procedures for water level instrumentation Creek, there were no surveil- a year. Also, the SFP cooling pump suction alarmthat had been inoperable for
was inoperable.
IN 88-65 August 18, 1988 notice.
No specific action or written response is required by this information
contact one of the techni-
If you have any questions about this matter, please
cal contacts listed below or the Regional Administrator of the appropriate
regional office.
h/aA
HEo osk r
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge, NRR
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments:
1. Figure 1. Simplified Flow Path Diagram of Upper Pool
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
,Normal Water Level 185' O"
72'1"t*oL a_ A.
CC
o -en(7 D
0~0
-ua
Figure 1. Simpified Flow Path Diagram of Upper Pool so
Purification System at River Bend.
Attachment 2 IN 88-65 August 18, 1988 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
88-64 Reporting Fires in Nuclear 8/18/88 All holders of OLs
Process Systems at Nuclear or CPs for nuclear
Power Plants power reactors.
88-63 High Radiation Hazards 8/15/88 All holders of OLs
from Irradiated Incore or CPs for nuclear
Detectors and Cables power reactors, research reactors
and test reactors.
88-62 Recent Findings Concerning 8/12/88 All holders of NRC
Implementation of Quality quality assurance
Assurance Programs by program approval
Suppliers of Transport for radioactive
Packages material packages.
88-61 Control Room Habitability - 8/11/88 All holders of OLs
Recent Reviews of Operating or CPs for nuclear
Experience power reactors.
88-60 Inadequate Design and 8/11/88 All holders of OLs
Installation of Watertight or CPs for nuclear
Penetration Seals power reactors.
88-04, Inadequate Qualification 8/9/88 All holders of OLs
Supplement 1 and Documentation of Fire or CPs for nuclear
Barrier Penetration Seals power reactors.
88-59 Main Steam Isolation Valve 8/9/88 All holders of OLs
Guide Rail Failure at or CPs for nuclear
Waterford Unit 3 power reactors.
88-58 Potential Problems with 8/8/88 All holders of OLs
ASEA Brown Boveri ITE-51L or CPs for nuclear
Time-Overcurrent Relays power reactors.
88-57 Potential Loss of Safe 8/8/88 All holders of OLs
Shutdown Equipment Due to or CPs for nuclear
Premature Silicon Controlled power reactors.
Rectifier Failure
OL = Operating License
CP = Construction Permit
IN 88-65 August 18, 1988 by this information notice.
No specific action or written response is required contact one of the techni- If you have any questions about this matter, please of the appropriate
cal contacts listed below or the Regional Administrator
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge, NRR
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments: Pool
1. Figure 1. Simplified Flow Path Diagram of Upper
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
CONCURRENCES *PDSNP:DRST:NRR
- C/OGCB:DOEA:NRR*RPB:ARM *D/IMNS:NMSS
CHBerlinger TechEd RCunningham CMiller
-
08/10/88 04/27/88 08/08/88 08/09/88 R *SPLB:DEST:NRR *C/SPLB:DEST:NRR*SAD/DEST:NRR *D/DEST:NRR
JKudrick JCraig AThadani LCShao
VHodge 07/28/88
07/15/88 07/18/88 07/20/88 07/26/88
IN 88-xx
August xx, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge, NRR
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments:
1. Figure 1. Simplified Flow Path Diagram of Upper Fuel Pool
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
, LUt, F'?
LA
L,.} bc 000
- SEE PREVIOUS CONCURRENC rev
D/DOEA:NRR C/OGCB:DO A: NRR*RPB:ARM D/IMNS:NMSS PDSNP:DRST:NRR
CERossi CHBerllnger TechEd RCunningham CMiller
08/ /88 08//0/88 04/27/88 08/O/88 08/01/88
- OGCB:DOEA:NRPt *SPLB:DEST:NRR *C/SPLB:DEST:NRR*SAD/DEST:NRR *D/DEST:NRR
VHodge JKudrick JCraig AThadani LCShao
07/15/88 07/18/88 07/20/88 07/26/88 07/28/88
IN 88-xx
July xx, 1988 notice.
No specific action or written response is required by this information techni- of the
If you have any questions about this matter, please contact one
cal contacts listed below or the Regional Administrator of the appropriate
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge, NRR
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments:
1. Figure 1. Simplified Flow Path Diagram of Upper Fuel Pool
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES
D/DOEA:NRR C/OGCB:DOEA:NRR *RPB:ARM
CERossi CHBerlinger TechEd
07/ /88 07/ /88 04/27/8
- OGCB:DOEA:NRR *SPLB:DEST:NRR *C/SPLB:DEST:NRR SAD/DESTzNR D/DESTfRR/
VHodge JKudrick JCraig AThadani-K LCSh
07/15/88 07/18/88 07/20/88 07f4/88 07/ / 8 8
IN 88-xx
July xx, 1988 Surveillance procedures were not implemented to ensure the operability of all
instrumentation and control equipment. At Wolf Creek, there were no surveil- lance procedures for water level instrumentation that had been inoperable for a
year. Also, the SFP cooling pump suction alarm was inoperable.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate
regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments:
1. Figure 1. Simplified Flow Path Diagram of Upper Fuel Pool
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS PAGE FOR CONCURRENCE
- OGCB:DOEA:NRR *SPLB:DEST:NRR *RPB:ARM C: DST C/OGCB:DOEA:NRR D/DOEA:NRR
VHodge JKudrick TechEd J raig CHBerlinger CERossi
07/15/88 07/18/88 04/27/88 072,,/88 07/ /88 07/ /88
IN 88-xx
July xx, 1988 Antisiphon devices were either not included in the system design, not in- stalled, or were initially placed in service but were not operable when re- quired. At San Onofre, the SFP cooling system design was apparently properly
siphon-protected, but the SFP purification system design apparently was not.
At River Bend, anitsiphon devices in the SFP purification system were plugged
to permit preoperational testing but were not unplugged at the beginning of
refueling operations.
Operating procedures for the interconnected systems associated with SFPs either
were not sufficiently detailed or were incorrect and failed to prevent align- ments causing unintentional drainage. At River Bend, the range of SFP level
indication was limited. Detailed operating procedures were available but were
not correct. At Wolf Creek, detailed operating procedures did not exist.
Surveillance procedures were not implemented to ensure the operability of all
instrumentation and control equipment. At Wolf Creek, there were no surveil- lance procedures for water level instrumentation that had been inoperable for a
year. Also, the SFP cooling pump suction alarm was inoperable.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the techni- cal contacts listed below or the Regional Administrator of the appropriate
regional office.
Charl es E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Vern Hodge
(301) 492-1169 J. Kudrick, NRR
(301) 492-0871 Attachments:
1. Figure 1. Simplified Flow Path Diagram of Uppe r Fuel Pool
Purification System at River Bend
2. List of Recently Issued NRC Information Notices
OGCB:DOEA:NRR SPL :NRR RPB:ARM OhM' C/OGCB :DOEA:NRR D/DOEA:NRR
VHodge JKu k TechEd CHBerli i nger CERossi
07/1?/88 07/\ 8 Otf 2-9/88 b\ 07/ /I38 07/ /88
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list | - Information Notice 1988-01, Safety Injection Pipe Failure (27 January 1988, Topic: Unidentified leak, Water hammer)
- Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds (2 February 1988, Topic: Stolen)
- Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals (5 February 1988, Topic: Fire Barrier, Fire Watch, Stolen)
- Information Notice 1988-05, Fire in Annunciator Control Cabinets (12 February 1988, Topic: Stolen)
- Information Notice 1988-06, Foreign Objects in Steam Generators (29 February 1988, Topic: Stolen)
- Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations (7 March 1988, Topic: Stolen)
- Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents (14 March 1988, Topic: Process Control Program, Stolen)
- Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors (18 March 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) (23 December 1988)
- Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. (23 December 1988, Topic: Fatality, Overexposure)
- Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts (7 April 1988)
- Information Notice 1988-12, Overgreasing of Electric Motor Bearings (12 April 1988)
- Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves (18 April 1988)
- Information Notice 1988-14, Potential Problems with Electrical Relays (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine (18 April 1988)
- Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities (22 April 1988, Topic: Water hammer)
- Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. (22 April 1988, Topic: Safe Shutdown, Weld Overlay, Feedwater Heater, Through-Wall Leak, Water hammer)
- Information Notice 1988-18, Malfunction of Lockbox on Radiography Device (25 April 1988, Topic: Overexposure)
- Information Notice 1988-19, Questionable Certification of Class Ie Components (26 April 1988, Topic: Water hammer)
- Information Notice 1988-19, Questionable Certification of Class IE Components (26 April 1988)
- Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities (5 May 1988)
- Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants (9 May 1988, Topic: Shutdown Margin)
- Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations (12 May 1988)
- Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident (12 May 1988)
- Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems (13 May 1988)
- Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts (16 May 1988, Topic: Earthquake)
- Information Notice 1988-26, Falsified Pre-Employment Screening Records (16 May 1988)
- Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components (18 May 1988)
- Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage (19 May 1988, Topic: Coatings)
- Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies (24 May 1988)
- Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update (25 May 1988)
- Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency (25 May 1988)
- Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material (25 May 1988)
- Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device (27 May 1988)
- Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors (31 May 1988)
- Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation (8 June 1988)
- Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components (14 June 1988, Topic: Ultimate heat sink)
- Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers (15 June 1988)
- Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event (15 June 1988)
- Information Notice 1988-40, Examiners' Handbook for Developing Operator Licensing Examinations (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) (22 June 1988)
- Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) (22 June 1988)
- Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts (23 June 1988, Topic: Loctite)
- Information Notice 1988-43, Solenoid Valve Problems (23 June 1988, Topic: Stroke time)
- Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers (24 June 1988)
- Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination (7 July 1988, Topic: Safe Shutdown)
- Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers (8 July 1988)
- Information Notice 1988-47, Slower-than-Expected Rod-drop Times (14 July 1988)
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