Non-Power Reactor Emergency Event Response ML031190745 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:
12/01/1992 From:
Grimes G Office of Nuclear Reactor Regulation To:
References IN-92-079 , NUDOCS 9211240106Download: ML031190745 (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 December 1, 1992 3 Addressees 4 Purpose 5 Description of Circumstances
5.1 The State of Oregon also 5.2 At the facility, the NRC inspectors found that the 5.3 The NRC also found 5.4 American Nuclear 5.5 Improper classification of 5.6 Notification of the NRC Operations Center, or NRC 5.7 Division of Operating Reactor Support 5.8 M. Mendonca, NRR 5.9 List of Recently Issued NRC Information Notices 5.10 December 1, 1992 5.11 LIST OF RECENTLY ISSUED 5.12 All holders of OLs or CPs 5.13 Diesel Engines 5.14 All holders of OLs or CPs 5.15 Electropneumatic Relays 5.16 All holders of OLs or CPs 5.17 Program for Emergency 5.18 All holders of OLs or CPs 5.19 Material by Individuals 5.20 All holders of OLs or CPs 5.21 Power Unit 2 5.22 All holders of OLs or CPs 5.23 All holders of OLs or CPs 5.24 While Critical 5.25 All holders of OLs or CPs 5.26 Origihnal igned by 5.27 Brian K. Grimes, Director 5.28 Office of Nuclear Reactor Regulation 5.29 M. Mendonca, NRR 5.30 List of Recently Issued NRC Information Notices 5.31 LJCunningham 5.32 October xx, 1992 5.33 Brian K. Grimes, Director 5.34 Office of Nuclear Reactor Regulation 5.35 M. Mendonca, NRR 5.36 List of Recently Issued NRC Information Notices 5.37 September xx, 1992 5.38 Charles E. Rossi, Director 5.39 Office of Nuclear Reactor Regulation 5.40 M. Mendonca, NRR 5.41 List of Recently Issued NRC Information Notices 5.42 Gail H. Marcus, Chief 5.43 Division of Operational Events 5.44 Office of Nuclear Reactor Regulation 5.45 Seymour H. Weiss, Director 5.46 Environmental Project Directorate 5.47 Office of Nuclear Reactor Regulation 5.48 CONSIDERATIONS 5.49 The individuals who receive courtesy 5.50 Seymour H. Weiss, Director 5.51 Environmental Project Directorate 5.52 Office of Nuclear Reactor Regulation 5.53 Fouchard, OPA 5.54 L. Cohen, EPB 5.55 P. Qualls, RV 5.56 R. Cooper, RI 5.57 C. Norelius, RIII 5.58 Central Files
NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON , D.C.
20555
December 1, 1992 NRC INFORMATION NOTICE 92-79:
NON-POWER REACTOR EMERGENCY EVENT RESPONSE
Addressees All holders of operating licenses or construction permits for test and
research reactors.
Purpose The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the findings of an NRC review related to
emergency event response at non-power reactors. These findings are on (1)
emergency action levels (EALs ) to determine emergency event classification,
(2) sampling to measure a radioactive release, (3) dose assessment capability
for a radioactive airborne release, and (4) notifications to the NRC.
It is
expected that recipients will review the information for applicability to
their facilities and consider actions, as appropriate, to avoid potential
problems.
However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances In November 1991, a small release of fission products at the Reed College
TRIGA reactor (located in Portland, Oregon ) was sufficient to activate the
alarms of both the continuous air monitor and the gaseous stack monitor. Upon
reviewing the EALs in the emergency plan , the licensee declared a Notification
of Unusual Event and notified the NRC Operations Center and the State. The
NRC responded to the notifications by sending an inspection team to the
college to review the situation. The NRC also sent a Public Affairs Officer
to respond to potential public and media interest.
The State of Oregon also sent a monitoring team.
At the facility, the NRC inspectors found that the licensee had characterized the release as fission products and had
conservatively estimated the amount of radioactivity released.
The NRC
inspectors assisted the licensee in assessing radiological dose consequences.
The local media and public, including the student body, posed extensive
questions on the event and the release. During a press conference, the
licensee and the NRC jointly addressed the health and safety concerns of the
media and public.
92 :1O2
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4edr
IN 92-79 December 1, 1992 The event at Reed College prompted the NRC to review similar non-power reactor
licensees to determine their capabilities to respond in similar circumstances.
The NRC found that, while licensee capabilities varied, some licensees could
not readily locate sampling equipment discussed in emergency plans for
response, had not fully developed procedures for using the sampling equipment, and did not have immediate access to a method of correlating the quantity of
radioactivity released to a dose at the site boundary.
The NRC also found that the EALs and the criteria for notifying the NRC and other offsite
agencies varied greatly between licensees. There were also examples of events
classified as alerts for which emergency plans did not specify notification of
the NRC.
The specific licensees were informed of these findings.
Discussion
Licensee classification of an event under its emergency plan dictates the
manner in which the NRC and other offsite agencies respond.
American Nuclear Society/American National Standards Institute Standard 15.16-1982, "Emergency
Planning for Research Reactors," Regulatory Guide 2.6 , "Emergency Planning for
Research Reactors," 1979, and NUREG-0849 , "Standard Review Plan for the Review
and Evaluation of Emergency Plans for Research and Test Reactors," October
1983 contain information on event classification.
Improper classification of an event may prevent the licensee, the NRC, other agencies, and the public
from responding appropriately to the event.
The-licensee,-theNRQ,-and-the-public-gave-considerable-attention to the
..
unplanned radiological release at Reed College, although the release resulted
in an estimated dose of much less than one millirem at the site boundary.
The
ability to quantify the magnitude and effects of a release and to establish
the safety significance of the release proved extremely important in the Reed
College event.
Some abnormal events will generate substantial public interest regardless of
the actual safety significance of the event. A small unplanned radiological
release is such an event.
Notification of the NRC Operations Center, or NRC headquarters or regional contacts for events that could result in high public
interest, can enable the NRC to respond, in coordination with the licensee, to
issues raised by the media or the public about the event.
IN 92-79 December 1, 1992 This information notice requires no specific action or written response. II
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR ) project manager.
F
rian K. Grimes, Director
Division of Operating Reactor Support Office of Nuclear Reactor Regulation
Technical contact:
M. Mendonca, NRR (301) 504-1128 Attachment:
List of Recently Issued NRC Information Notices Attachment
IN 92-79
December 1, 1992 Page I of i
LIST OF RECENTLY ISSUED NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
92-78 Piston to Cylinder
11/30/92
All holders of OLs or CPs Liner Tin Smearing on
for nuclear power reactors.
Cooper-Bessemer KSV
Diesel Engines 92-77 Questionable Selection
11/17/92
All holders of OLs or CPs and Review to Deter- for nuclear power reactors.
mine Suitability of
Electropneumatic Relays for Certain Applications
92-76 Issuance of Supple-
11/13/92
All holders of OLs or CPs ment I to NUREG-1358 , for nuclear power reactors.
'Lessons Learned from
the Special Inspection
Program for Emergency Operating Procedures
(Conducted October 1988 -
September 1991)"
92-75 Unplanned Intakes of
11/12/92
All holders of OLs or CPs Airborne Radioactive
for nuclear power reactors.
Material by Individuals at Nuclear Power Plants
92-74 Power Oscillations at
11/10/92
All holders of OLs or CPs Washington Nuclear
for nuclear power reactors.
Power Unit 2 92-61, Loss of High Head
11/06/92
All holders of OLs or CPs Supp. 1 Safety Injection
for nuclear power reactors.
92-73 Removal of A Fuel
11-04/92
All holders of OLs or CPs Element from A Re- for nuclear power reactors.
search Reactor Core
While Critical 92-59, Horizontally-Installed
11/04/92
All holders of OLs or CPs Rev. 1 Motor-Operated Gate
for nuclear power reactors
Valves
OL - Operating License
CP - Construction Permit
IN 92-79 December 1, 1992 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR ) project manager.
Origihnal igned by Brian 1K.
Grimc7s
Brian K. Grimes, Director Division of Operating Reactor Support
Office of Nuclear Reactor Regulation Technical contact:
M. Mendonca, NRR (301) 504-1128 Attachment:
List of Recently Issued NRC Information Notices DOCUMENT NAME: 92-79.IN
SEE PREVIOUS CONCURRENCES +SEE MEMO FROM S. H. W
S
G. H. MARCUS 09/11/92
GHMarcus
10/02/92
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LJCunningham 09/18/92
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09/30/92
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09/10/92
09/10/92
09/11/92
09/11/92
IN 92-XX
October xx, 1992 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR ) project manager.
Brian K. Grimes, Director Division of Operating Reactor Support
Office of Nuclear Reactor Regulation Technical contact:
M. Mendonca, NRR (301) 504-1128 Attachment:
List of Recently Issued NRC Information Notices Document Name:
NPREMEV.IN
SEE PREVIOUS CONCURRENCES +SEE MEMO FROM S. H. WEISS TO G. H. MARCUS 09/11/92
C/OGCB:DORS:NRR D/DORS:NRR GHMarcus
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09/18/92
09/30/92
10/01/92
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09/16/92
09/10/92
09/10/92
09/11/92
09/11/92
IN 92-XX
September xx, 1992 This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR ) project manager.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical contact:
M. Mendonca, NRR (301) 504-1128 Attachment:
List of Recently Issued NRC Information Notices Document Name: NPREMEV.IN
+SEE MEMO FROM S. H. WEISS TO G. H. MARCUS 09/11/92 C/OGCB:DOEA:NRR D/DOEA:NRR
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09/11/92
I .
f, MEMORANDUM FOR:
September 11, 19J)
Gail H. Marcus, Chief Generic Communications Branch
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation FROM:
Seymour H. Weiss, Director Non-Power Reactors, Decommissioning and
Environmental Project Directorate Division of Reactor Projects - III/IV/V
Office of Nuclear Reactor Regulation SUBJECT:
PROPOSED DRAFT INFORMATION NOTICE ON NON-POWER REACTOR EVENT
CONSIDERATIONS In accordance with NRC Inspection Manual Chapter 0720 , 1 have enclosed, the subject draft information notice.
The individuals who receive courtesy copies of this memorandum should also be considered by the Generic
Communications Branch to be included for concurrence on this information
notice.
/S/
Seymour H. Weiss, Director Non-Power Reactors, Decommissioning and
Environmental Project Directorate Division of Reactor Projects - III/IV/V
Office of Nuclear Reactor Regulation cc
R.
L.
F.
R.
w/enclosure:
Erickson, NRR/PEPB
Cunningham, NRR/PRPB
Fouchard, OPA Scarano, RV/DRSS
bcc:
A. Adams
T. Michaels
M. Mendonca
L. Cohen, EPB F. Kantor, EPB
P. Qualls, RV J. Reese, RV
R. Pate, RV
R. Cooper, RI J.P. Stohr, RII
C. Norelius, RIII L. Callan, RIV
DISTRIBUTION:
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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
