Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications ML031200738 Person / Time 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 , 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 , Crane Issue date:
01/15/1992 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-92-006 , NUDOCS 9201080305Download: ML031200738 (7)
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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 ,
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 ,
Crane Category:NRC Information Notice
[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 [[: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]] OR [[:Crane]] </code>.
Contents
1 NUCLEAR REGULATORY COMMISSION 2 January 15, 1992 3 OTHER NRC REQUIRED EQUIPMENT NOT CONTROLLED 4 Addressees 5 Purpose 6 Description of Circumstances
6.1 These open switches disabled the automatic AFW flow 6.2 The NRC issued the licensee a Severity 6.3 However, maintenance of this system is 6.4 However, it is important 6.5 January 15, 1992 This information notice requires 6.6 Division of Operational Events Assessment 6.7 R. Evans, RIV 6.8 C. Paulk, RIV 6.9 J. Mauck, NRR 6.10 List of Recently Issued NRC Information Notices 6.11 All holders of OLs or CPs 6.12 All holders of OLs or CPs 6.13 All holders of OLs or CPs 6.14 All holders of OLs or CPs 6.15 Conservation of Energy 6.16 All holders of 0Ls or CPs 6.17 All holders of OL or cps 6.18 All licensees authorized 6.19 All holders of OLc or CPs 6.20 Cooling Water 6.21 All Muclear Regulatory 6.22 Charles E. Rossi, Director 6.23 Office of Nuclear Reactor Regulation 6.24 R. Evans, RIV 6.25 C. Paulk, RIV 6.26 J. Mauck, NRR 6.27 List of Recently Issued NRC Information Notices 6.28 December xx, 1991 This information notice requires 6.29 Charles E. Rossi, Director 6.30 Office of Nuclear Reactor Regulation 6.31 R. Evans, RIV 6.32 C. Paulk, RIV 6.33 J. Mauck, NRR 6.34 List of Recently Issued NRC Information Notices 6.35 December xx, 1991 This information notice requires 6.36 Charles E. Rossi, Director 6.37 Office of Nuclear Reactor Regulation 6.38 R. Evans, RIV 6.39 C. Paulk, RIV 6.40 NRCInorati ion N ot 6.41 December xx, 1991 This information notice requires 6.42 Charles E. Rossi, Director 6.43 Office of Nuclear Reactor Regulation 6.44 R. Evans, RIV 6.45 C. Paulk, RIV 6.46 List of Recently Issued NRC Information Notices
NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON , D.C.
20555
January 15, 1992 NRC INFORMATION NOTICE 92-06: RELIABILITY OF ATWS MITIGATION SYSTEM AND
OTHER NRC REQUIRED EQUIPMENT NOT CONTROLLED BY PLANT TECHNICAL SPECIFICATIONS
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 of the importance of maintaining the reliability of
equipment required by NRC regulations but not addressed in plant technical
specifications.
It is expected that recipients will review this information
for applicability to their facilities and consider actions, as appropriate, to
avoid similar problems. However, suggestions contained in this information
notice are not NRC requirements; therefore, no specific action or written
response is required.
Background In 1983, the Salem Nuclear Generating Station experienced an anticipated
transient without scram (ATWS ) event. Following this event, efforts then
in progress to establish requirements to address ATWS events were completed, and the NRC issued, on June 1, 1984, Section 50.62 of Title 10 of the
Code of Federal Regulations (10 CFR 50.62) , "Requirements for reduction of risk
from anticipated transients without scram (ATWS ) events for light-water-cooled
nuclear power plants." This regulation required that each reactor have equip- ment, diverse from the reactor trip system, that would automatically initiate
actions to mitigate the consequences of an ATWS . The regulation also required
that the equipment for this system be independent from the existing reactor
trip system and be designed to perform its function in a reliable manner. The
NRC did not require licensees to address the operability of this equipment in
plant technical specifications nor did the NRC require that this equipment be
designated as safety-related.
Description of Circumstances To meet the requirements of 10 CFR 50.62, the Houston Lighting and Power
Company, the licensee for the South Texas Project (STP ), installed ATWS
mitigation system actuation circuitry (AMSAC ). In May and June of 1991, a\\\\\\O3O5Z/
IN 92-06 January 15, 1992 the NRC inspected the implementation of this system at STP , Units 1 and 2, and
identified three situations in which the reliability of the ATWS mitigation
system had been compromised.
While inspecting Unit 2, the NRC found that the licensee had left open the
switches for the interface circuit between the AMSAC system and the auxiliary
feedwater (AFW ) system.
These open switches disabled the automatic AFW flow Initiation feature of the AMSAC , an important part of the ATWS mitigation
system. The NRC also found that the licensee had bypassed the automatic
initiation feature of the AMSAC system, causing the system to be inoperable , at
least 15 percent of the time that the system was designed to be operable .
While inspecting Unit 1, the NRC found that the licensee had bypassed the
automatic initiation feature of the AMSAC system 36 percent of the time that
the system was designed to be operable .
The NRC issued the licensee a Severity Level III violation and assessed a civil penalty.
The NRC also issued the licensee for Comanche Peak a Severity Level IV violation
because the ATWS mitigation system was bypassed for approximately 10 days while
the reactor was operating at full power.
Discussion
In April 1985, the staff issued Generic Letter 85-06 , "Quality Assurance
Guidance For ATWS Equipment That Is Not Safety-Related," to provide explicit
quality assurance guidance for the nonsafety-related equipment encompassed by
the ATWS rule_ Although-much of the equipment- required-by-10-cR-50.62-is not- -
designated safety-related, it does perform an important safety function if the
plant's primary reactor protection system fails. The regulation was issued to
reduce the risk posed by such an event. The NRC considers the failure of
licensees to comply with this regulation and to ensure that the ATWS mitigation
system and equipment function reliably to be a significant regulatory concern.
The events described above indicate that licensees may not place an appropriate
level of priority on resolving problems with the ATWS mitigation system because
it is not a safety-related system and because the plant's technical specific- ations do not govern its operability.
However, maintenance of this system is of high priority and appropriate because such action assures the important
safety function of the system and satisfies the requirements of 10 CFR 50.62 for the system to function reliably. Actions taken by licensees to ensure the
reliability of the ATWS mitigation system have included performing timely
surveillance testing, completing repairs and preventive maintenance promptly, implementing necessary modifications, and updating procedures to reflect system
changes.
Plant technical specifications only address the minimum personnel and equipment
requirements for the various modes of plant operations.
However, it is important that licensees maintain equipment and systems required by NRC regulations, to
ensure their reliability, even though they are not addressed by a plant's
technical specifications.
IN 92-06
January 15, 1992 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
arls't. Rossi, Director
/
Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Technical contacts:
R. Evans, RIV (512) 972-2507
C. Paulk, RIV (817) 860-8236
J. Mauck, NRR (301) 504-3248 Attachment:
List of Recently Issued NRC Information Notices Attciment
11 92-06 January IS. 1992 LIST OF RECCEITLY
ISS1ED
SRC INFOWATIOR
WTICES
Information
Date of
Notice no.
Subject
Issuance
Issued to
92-45 Potential Coil Insuletion
02/08/92
All holders of OLs or CPs Breakdown 1 ABB RJDH2 Relays
for nuclear power reactors.
92-04 Potter S Bruefitld Model
01/06/92
All holders of OLs or CPs MtDR
Rotary Relay Failures
for miclear power reactors.
92-03 R ote Trip Function
01/06/92
All holders of OLs or CPs Failures in General Electric
for nuclear power reactors.
F-Frae Molded-Case Circuit
Breakers
92-02 Relp5/NWo3 tComuter Code
01/03/92
All holders of OLs or CPs Error Associated with the
for nuclear power reactors.
Conservation of Energy Equation
92-01 Cable Damage Caused by
01/03/92
All holders of 0Ls or CPs Inadequate Cable Installa- for nuclear power reactors.
tion Procedures and Controls
91-87 Hydrogen Embrittlement of
12/27/91
All holders of OL or cps Raychee Cryofit Couplings
for nuclear power reactors.
91486 kw Reporting Requireents
12/27/91
All licensees authorized for Contauination Events at
to use byproduct materials
Medical Fecilities
for humus
use.
(10 tFR 30.10)
9145 Potential Failures of
12/26/91
All holders of OLc or CPs Thermostatic Control valves
for nuclear power reactors.
for Diesel generator Jacket
Cooling Water 9144 Problems uith Criticality
12/26/91
All Muclear Regulatory Alarm Cot onents/Systems
Commission (NRC) fuel
cycle licensees. interim
spent fuel atorage licens- ees and critical mass
licnsees.
OL
CP
IN 92-06 January 15,
1992 This information notice requires
you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Orig /s/'d by CERossi
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
R. Evans, RIV (512) 972-2507
C. Paulk, RIV (817) 860-8236
J. Mauck, NRR (301) 504-3248 Attachment:
List of Recently Issued NRC Information Notices D/ OE~rtR51
C/SICB:IYST:NRR *SC/SICB:DST:NRR CHBerlinger
TechEd
SNewberry
JMauck
01/06/92
11/26/91
12/20/91
12/20/91
JLBirmingham
REvans
CPaulk
TWesterman
SCollins
12/17/91
12/17/91
12/17/91
12/18/91
12/18/91 DOCUMENT NAME:
IN 92-06
IN 91-XX
December xx, 1991 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
R. Evans, RIV (512) 972-2507
C. Paulk, RIV (817) 860-8236
J. Mauck, NRR (301) 504-3248 Attachment:
List of Recently Issued NRC Information Notices Document Name: ATWS-IN.RFT
SEE PREVIOUS CONCURRENCES/ D/DOEA:NRR
C/OGC 1fldLA:NRR*RPB:ADM
CERossi W'-'
CHBerlinger
TechEd
01/ /92 4
01/VP/92
11/26/91
JLBirmingham
REvans
CPaulk
12/17/91
12/17/91
12/17/91
SNewberry
12/20/91
TWesterman
12/18/91
JMauck
12/20/91
SCollins
12/18/91
IN 91-XX
December xx, 1991 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
R. Evans, RIV (512) 972-2507
C. Paulk, RIV (817) 860-8236 L.t tIc
NRCInorati ion N ot List of R ecent W Issuel NRC Information Notices
/A
Attachment:
Document Name:
ATWS-IN.RFT
SEE PREVIOUS CONCURRENCES D/DOEA:NRR
C/OGCB:DOEA:NRR*RPB:ADM
CERossi
CHBerlinger
TechEd
12/ /91
12/ /91
11/26/91
JLBirmingham
REvans
CPaulk
12/17/91
12/17/91
12/17/91 C/SICB ST:NRR
SNe fry&sk45
12
/91 C12
S:RIV
TWesterman
12/18/91 J
12/ /91
SCollins
12/18/91
IN 91-XX
December xx, 1991 This information notice requires you have any questions about the
of the technical contacts listed
Reactor Regulation (NRR ) project
no specific action or written response. If
information in this notice, please contact one
below or the appropriate Office of Nuclear
manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contacts:
R. Evans, RIV (512) 972-2507
64'J
a4--CL
C. Paulk, RIV (817) 860-8236 Attachment:
List of Recently Issued NRC Information Notices Document Name:
ATWS-IN.RFT
SEE PREVIOUS CONCURRENCES OGCB:DOEA:NRR
Jirming ym
12/17/91 RESINSP:RIY
REvans,,
f
12/17/1e
D/DOEA:NRR
CERossi
12/ /91 DRS:RIV
CPaulk iJd
12/l/91
/DPl
C/OGCB:DOEA:NRR*RPB:ADM
CHBerlinger
TechEd
12/ /91
11/26/91 SC/DRS:RIV
D/DRS:RIV
TWesterman V
SCollins
12/1I/91 o
12/;r/91 (
list Information Notice 1992-01, Cable Damage Caused by Inadequate Cable Installation Procedures and Controls 3 January 1992 Information Notice 1992-02, Relap5/MOD3 Computer Code Error Associated with the Conservation of Energy Equation 3 January 1992 Topic Overspeed Information Notice 1992-02, Relap5/Mod3 Computer Code Error Associated with the Conservation of Energy Equation 3 January 1992 Information Notice 1992-03, Remote Trip Function Failures in General Electric F-Frame Molded-Case Circuit Breakers 6 January 1992 Topic Overspeed Information Notice 1992-04, Potter and Brumfield Model Mdr Rotary Relay Failures 6 January 1992 Topic Probabilistic Risk Assessment Commercial Grade Overspeed Information Notice 1992-04, Potter and Brumfield Model MDR Rotary Relay Failures 6 January 1992 Topic Probabilistic Risk Assessment Commercial Grade Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs RXMH2 Relays 8 January 1992 Topic Commercial Grade Overspeed Information Notice 1992-05, Potential Coil Insulations Breakdown in Abs Rxmh2 Relays 8 January 1992 Topic Commercial Grade Information Notice 1992-05, Potential Coil Insulations Breakdown in ABS RXMH2 Relays 8 January 1992 Topic Commercial Grade Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment Not Controlled by Plant Technical Specifications 15 January 1992 Information Notice 1992-06, Reliability of ATWS Mitigation System and Other NRC Required Equipment not Controlled by Plant Technical Specifications 15 January 1992 Information Notice 1992-07, Rapid Flow-induced Erosion/Corrosion of Feedwater Piping 9 January 1992 Information Notice 1992-08, Revised Protective Action Guidance for Nuclear Incidents 23 January 1992 Information Notice 1992-09, Overloading and Subsequent Lock Out of Electrical Buses During Accident Conditions 30 January 1992 Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire Used in Endobronchial Treatments 31 January 1992 Topic Brachytherapy Information Notice 1992-10, Brachytherapy Incidents Involving Iridium-192 Wire used in Endobronchial Treatments 31 January 1992 Topic Brachytherapy Information Notice 1992-11, Soil and Water Contamination at Fuel Cycle Facilities 5 February 1992 Information Notice 1992-12, Effects of Cable Leakage Currents on Instrument Settings and Indications 10 February 1992 Topic High Energy Line Break Information Notice 1992-13, Inadequate Control Over Vehicular Traffic at Nuclear Power Plant Sites 18 February 1992 Topic Loss of Offsite Power Information Notice 1992-14, Uranium Oxide Fires at Fuel Cycle Facilities 21 February 1992 Information Notice 1992-15, Failure of Primary Systems Compression Fitting 24 February 1992 Topic Unidentified leakage Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown 25 February 1992 Topic Reactor Vessel Water Level Temporary Modification Information Notice 1992-17, NRC Inspections of Programs Being Developed at Nuclear Power Plants in Response to Generic Letter 89-10 26 February 1992 Topic Stroke time Information Notice 1992-18, Potential for Loss of Remote Shutdown Capability During a Control Room Fire 28 February 1992 Topic Hot Short Safe Shutdown Information Notice 1992-19, Misapplication of Potter and Brumfield Mdr Rotary Relays 2 March 1992 Information Notice 1992-19, Misapplication of Potter and Brumfield MDR Rotary Relays 2 March 1992 Information Notice 1992-20, Inadequate Local Leak Rate Testing 3 March 1992 Topic Local Leak Rate Testing Information Notice 1992-21, Spent Fuel Pool Reactivity Calculations 24 March 1992 Information Notice 1992-23, Results of Validation Testing of Motor-Operated Valve Diagnostic Equipment 27 March 1992 Information Notice 1992-24, Distributor Modification to Certain Commercial-Grade Agastat Electrical Relays 30 March 1992 Information Notice 1992-25, Pressure Locking of Motor-Operated Flexible Wedge Gate Valves 2 April 1992 Topic Stroke time Hydrostatic Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of ITE/Gould A.C. Relays used in Safety-Related Applications 3 April 1992 Topic Commercial Grade Information Notice 1992-27, Thermally Induced Accelerated Aging and Failure of Ite/Gould A.C. Relays Used in Safety-Related Applications 3 April 1992 Topic Commercial Grade Information Notice 1992-28, Inadequate Fire Suppression System Testing 8 April 1992 Topic Safe Shutdown Information Notice 1992-29, Potential Breaker Miscoordination Caused by Instantaneous Trip Circuitry 17 April 1992 Information Notice 1992-30, Falsification of Plant Records 23 April 1992 Information Notice 1992-31, Electrical Connection Problem in Johnson Yokogawa Corporation YS-80 Programmable Indicating Controllers 27 April 1992 Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (Within 10 Miles) Emergency Operations Facilities and Technical Support Centers 29 April 1992 Information Notice 1992-32, Problems Identified with Emergency Ventilation Systems for Near-Site (within 10 Miles) Emergency Operations Facilities and Technical Support Centers 29 April 1992 Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices Are Installed 30 April 1992 Information Notice 1992-33, Increased Instrument Response Time When Pressure Dampening Devices are Installed 30 April 1992 Information Notice 1992-34, New Exposure Limits for Airborne Uranium and Thorium 6 May 1992 Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping Inside Containment at a Boiling Water Reactor 6 May 1992 Information Notice 1992-35, Higher than Predicted Erosion/Corrosion in Unisolable Reactor Coolant Pressure Boundary Piping inside Containment at a Boiling Water Reactor 6 May 1992 Information Notice 1992-36, Intersystem LOCA Outside Containment 7 May 1992 Information Notice 1992-37, Implementation of the Deliberate Misconduct Rule 8 May 1992 Information Notice 1992-38, Implementation Date for the Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 26 May 1992 Information Notice 1992-39, Unplanned Return to Criticality During Reactor Shutdown 13 May 1992 Topic Fuel cladding Information Notice 1992-40, Inadequate Testing of Emergency Bus Undervoltage Logic Circuitry 27 May 1992 Topic Loss of Offsite Power Information Notice 1992-41, Consideration of Stem Rejection Load In Calculation of Required Valve Thrust 29 May 1992 Topic Anchor Darling ... further results
