Emergency Response ExercisesML031130496 |
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, 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 |
---|
Issue date: |
10/23/1987 |
---|
From: |
Rossi C Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-87-054, NUDOCS 8710190144 |
Download: ML031130496 (9) |
|
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 |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Contain2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Con2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend and/or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[: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>. |
SSINS No.: 6835 IN 87-54 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 October 23, 1987 NRC INFORMATION NOTICE NO. 87-54: EMERGENCY RESPONSE EXERCISES
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is being provided to remind addressees of flexibility
that exists in certain rewuiremnents contiined in emergency planning rules. It
is expected that recipientsvwill review&the information for applicability to
their program. However, suggestions contained in this information notice do
not constitute NRC requirements'; therefore,'no'specific action or written
response is'required.
Description of Circumstances
To satisfy the current requirements of 10 CFR 50.47 and 10 CFR Part 50, Appen- dix E, each licensee must' annually exercise its emergency plan. In addition, each licensee is required to exercise with offsite authorities such that the
State and local government emergency plans'are exercised biennially. Currently
there are no specific requirements which address whether each exercise scenario
must lead to the declaration of A General Emergency. Mowever, perhaps as a
carryover from the 'previous requirements for annual State and local exercises, almost all exercise scenarios are planned to progress to a General Emergency
condition.
Discussion:
While it may be-appropriate for biennial offsite exercises to proceed to a
General Emergency declaration, exercises other than biennial offsite exercises
(off-year exercises) are not required to proceed to severe core damace. Such
exercises can provide an opportunity forlmore realistic emergency response
trainine and evaluation of licensee staff. For example, before severe core
damage would be expected to occur, the operating staff may be given the oppor- tunity to diagnose and attempt-to correct the problem through an interactive
scenario. In addition, some exercise scenarios. may be. designed with initiating
events at the Alert or Site Area Emergency classification. Since actual events
may go directly to these higher level classifications without sequencing
8710190144
' - is'.
IN 87-54 October 23, 1987 through each emergency classi advance.Opportunity to-activate response facili- ties may not occur. The flexibility within the requirements allows for the
development of other realistic scenarios which, in turn, can improve emergency
response capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f, states that "licensees shall
enable any State or local government located within the plume exposure.pathway
EPZ to participate in annual exercises when requested by such State or local
government." To satisfy this requirement, it may be necessary for licensees to
develop an exercise scenario which provides opportunities to test the appropri- ate aspects of the offsite response plan. Such participation may need to be
negotiated between the.licensee and the offsite.authorities...
Licensees that have conducted realistic and interactive exercises have identi- fied and corrected weaknesses in their ability to respond to such simulated ;
onsite events as fire, loss of electrical power, and equipment failure. The
response of personnel and availability and utilizationof alternate.equipment, to mitigate simulated severe, off-normal plant conditions have been;.challenging
and.have led somellicensees to conduct further training and provide added.
procedures and support equipment. In addition, interactive exercises-can
provide a training opportunity for personnel that Would be called upon to make
strategic decisions in areas that are not addressed by existing procedures.
-Licensees-arni applc-a-its- may-_fShto-cons4de -neorpet-tig--thesetconcep~tsn, planning and conducting off-year emergency response-exercises.-
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in.IE Information Notice 85-55,:
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by.this information!notice.,
If you have any questions about.this matter, please contact.the technical.
contact 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 Contact:
Cheryl A. Sakenas, AEOD .
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
-Attachment.
4 IN-87-54 October 23, 1987
.LIST OF RECENTLY ISSUED i
I
INFORMATION NOTICES 1987 -I
k, I
Information Date of
Notice No. Subject Issuance Issued to
87-53 Auxiliary Feedwater Pump 10/20/87 All holders of OLs
Trips Resulting from Low or CPs for nuclear
Suction Pressure power reactors.
87-52 Insulation Breakdown of 10/16/87 All holders of OLs
Silicone Rubber-Insulated or CPs for nuclear
Single Conductor Cables power reactors.
During High Potential Testing
87-51 Failure of Low Pressure 10/13/87 All nuclear power
Safety Injection Pump Due reactor facilities
to Seal Problems holding an OL or CP.
87-50 Potential LOCA at High- 10/9/87 All nuclear power
and Low-Pressure Tnterfaces reactor facilities
from Fire Damage holding an OL or CP.
87-49 Deficiencies in Outside 10/9/87 All nuclear power
.! - Containment Flooding - io... .1 '7 , . ,w E .. reactor facilities
Protection holding an OL or CP.
87-48 Information Concerning the 10/9/87 All nuclear power
Use of Anaerobic Adhesive/ reactor facilities
Sealants holding an OL or CP.
87-47 Transportation of Radio- 10/5/87 All NRC licensees
graphy Devices authorized to manu- facture, distribute
and/or operate radio- graphic exposure
devices and/or
source changers.
87-46 Undetected Loss of Reactor 9/30/87 All PWR facilities
Coolant holding on OL or CP.
87-45 Recent Safety-Related 9/25/87 All NRC licensees
Violations of NRC authorized to possess
Requirements by Industrial and use sealed sources
Radiography Licensees for industrial radio- graphy.
OL = Operating License
CP = Construction Permit
IN 87-54 October 23, 1987 through each emergency class, advance opportunity to activate response facili- ties may not occur. The flexibility within the requirements allows for the
development of other realistic scenarios which, in turn, can improve emergency
response capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f, states that "licensees shall
enable any State or local government located within the plume exposure pathway
EPZ to participate in annual exercises when requested by such State or local
government." To satisfy this requirement, it may be necessary for licensees to
develop an exercise scenario which provides opportunities to test the appropri- ate aspects of the offsite response plan. Such participation may need to be
negotiated between the licensee and the offsite authorities.
Licensees that have conducted realistic and interactive exercises have identi- fied and corrected weaknesses in their ability to respond to such simulated
onsite events as fire, loss of electrical power, and equipment failure. The
response of personnel and availability and utilization of alternate equipment
to mitigate simulated severe off-normal plant conditions have been challenging
and have led some licensees to conduct further training and provide added
procedures and support equipment. In addition, interactive exercises can
provide a training opportunity for personnel that would be called upon to make
strategic decisions in areas that are not addressed by existing procedures.
Licensees and applicants may wish to consider incorporating these concepts in
planning and conducting off-year emergency response exercises.
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in TE Information Notice 85-55,
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact 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 Contact:
Cheryl A. Sakenas, AEOD
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES R C/OGCB:DOEA:NRR D/DREP:NRR
CHBerlinger FCongel
87 10/ /87 10/ /87
- PPMB:ARM OGCB:DOEA:NRR IR : OA:A D C/IRB:DOA:AEOD C/PEPB:DREP:NRR
TechEd JERamsey CASakenas KEPerkins DBMatthews
09/29/87 10/ /87 10/ /87 10/ /87 10/ /87
IN 87-XX
October xx, 1987 through each emergency class, advance opportunity to activate response facili- ties may not occur. The flexibility within the requirements allows for the
development of other realistic scenarios which, in turn, can improve emergency
response capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f, states that "licensees shall
enable any State or local government located within the plume exposure pathway
EPZ to participate in annual exercises when requested by such State or local
government." To satisfy this requirement, it may be necessary for licensees to
develop an exercise scenario which provides opportunities to test the appropri- ate aspects of the offsite response plan. Such participation may need to be
negotiated between the licensee and the offsite authorities.
Licensees that have conducted realistic and interactive exercises have identi- fied and corrected weaknesses in their ability to respond to such simulated
onsite events as fire, loss of electrical power, and equipment failure. The
response of personnel and availability and utilization of alternate equipment
to mitigate simulated severe off-normal plant conditions have been challenging
and have led some licensees to conduct further training and provide added
procedures and support equipment. In addition, interactive exercises can
provide a training opportunity for personnel that would be called upon to make
strategic decisions in areas that are not addressed by existing procedures.
Licensees and applicants may wish to consider incorporating these concepts in
planning and conducting off-year emergency response exercises. i-nadd4F4-en,
4c4ersees-may-w4-sh-te-oons rsrlflrPRk r
generi-e---PRA f o in selecting other reallsti exercise osenarf-ix.
Reference:
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in IE Information Notice 85-55,
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact 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 Contact:
Cheryl A. Sakenas, AEOD
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES D/DOEA:NRR
N105 C/OGCB:DOEA:NRR D/DREP:NRR~4 C
CERossi CHBerlinger FCongel J
10/ /87 10/I /87 10/j5/87 II.l
- PPMB:ARM Of O Ut:NRR IRB:DOA:AEOD C :A C/PEPB:DR flR
TechEd JE~ msey CASakons o l';r LV DBMatthew l
09/29/87 10/13/87 ! /87 _ 10/1 /87 10/15/87
IN 87-XX
October xx, 1987 through each emergency class, advance opportunity to activate response facili- ties may not occur. The flexibility within the requirements allows for the
development of other realistic scenarios which, in turn, can improve emergency
response capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f, states that "licensees shall
enable any State or local government located within the plume exposure pathway
EPZ to participate in annual exercises when requested by such State or local
government." To satisfy this requirement, it may be necessary for licensees to
develop an exercise scenario which provides opportunities to test the appropri- ate aspects of the offsite response plan. Such participation may need to be
negotiated between the licensee and the offsite authorities.
Licensees that have conducted realistic and interactive exercises have identi- fied and corrected weaknesses in their ability to respond to such simulated
onsite events as fire, loss of electrical power, and equipment failure. The
response of personnel and availability and utilization of alternate equipment
to mitigate simulated severe off-normal plant conditions have been challenging
and have led some licensees to conduct further training and provide added
procedures and support equipment. In addition, interactive exercises can
provide a training opportunity for personnel that would be called upon to make
strategic decisions in areas that are not addressed by existing procedures.
Licensees and applicants may wish to consider incorporating these concepts in
planning and conducting off-year emergency r7 sponse exercises. 7n aoldtov&, l'4nfolb
' oIt7Eer trho rtmtt of pdste or Vancieif P.4 Reference: leaAect'm1
4A .Eovr tramitc eewrta 1s1¢nQrO.
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in IE Information Notice 85-55,
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the ftgoena4 JAdm4fistratc w-ef-the-approprH -e5he-t;heona4o*4o t44#-ef+ce% +tchnijcs cow otAjt
1tad blksv or the flQonl Adef4inM.tmtcr dlf en aopprocrte steil *
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Cheryl A. Sakenas, AEOD
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
IN 87-XX
October xx, 1987 through each emergency class, advance opportunity to activate response facili- ties may not occur. The flexibility within the requirements allows for the
development of other realistic scenarios which, in turn, can improve emergency
response capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f, states that "licensees shall
enable any State or local government located within the plume exposure pathway
EPZ to participate in annual exercises when requested by such State or local
government." To satisfy this requirement, it may be necessary for licensees to
develop an exercise scenario which provides opportunities to test the appropri- ate aspects of the offsite response plan. Such participation may need to be
negotiated between the licensee and the offsite authorities.
Licensees that have conducted realistic and interactive exercises have identi- fied and corrected weaknesses in their ability to respond to such simulated
onsite events as fire, loss of electrical power, and equipment failure. The
response of personnel and availability and utilization of alternate equipment
to mitigate simulated severe off-normal plant conditions have been challenging
and have led some licensees to conduct further training and provide added
procedures and support equipment. In addition, interactive exercises can
provide a training opportunity for personnel that would be called upon to make
strategic decisions in areas that are not addressed by existing procedures.
Licensees and applicants may wish to consider incorporating these concepts in
planning and conducti o -year emergency respopse exercises. Irn
h s MAio¢ J
WtA to ther lth rfts wrt <t PX4 or
aoh4tao"#Fsc
Reference: f.^c^u Pnd hkisbk5 In oel4tIVn ceewr nflwi*tlc e~Gfrci6 fermn os.
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in IE Information Notice 85-55,
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Cheryl A. Sakenas, AEOD
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCES D/DOEA:NRR C/OGCB:DOEA:NRR D/DREP:NRR
CERossi CHBerlinger FCongel
10/ /87 10/ /87 10/ /87
- PPMB:ARM OGCB:DOEA:NRR IRB:DOA:AEOD C/IRB:DOA:AEOD C/PEPB:DREP:NRR
TechEd JERamsey CASakenas KEPerkins DBMatthews
09/29/87 10/ /87 10/ /87 10/ /87 10/ /87
- I >
IN 87-XX
September xx, 1987 through each emergency class, advance opportunity to activate response facili- ties, for example, may not occur. This flexibility allows for the development
of more realistic scenarios which, in turn, can improve emergency response
capability.
10 CFR Part 50, Appendix E, Section IV.F.3.f states that "Licensees shall
enable any State or local government located within the plume exposure pathway
EPZ to participate in annual exercises when requested by such State or local
government." In order to satisfy these requirements, it may be necessary for
licensees to develop an exercise scenario which provides opportunities to test
the appropriate aspects of the offsite response plan. The particulars of such
participation may need to be negotiated between the licensee and the offsite
authorities.
Licensees that have conducted more realistic and interactive exercises have
identified and corrected weaknesses in their ability to respond to such simu- lated onsite events as fire, loss of electrical power, and equipment failure.
The response of personnel and availability and utilization of alternate equip- ment to mitigate simulated severe off-normal plant conditions have been chal- lenging and have led some licensees to conduct further training and provide
added procedures and support equipment.
Interactive exercises can provide a training opportunity for personnel that
would be called upon to make strategic decisions should an actual event pro- gress beyond existing procedures. Licensees and applicants may wish to con- sider incorporating these concepts in planning and conducting off-year emer- gency response exercises.
Reference:
The revision to the exercise frequency requirements of 10 CFR Part 50,
Appendix E has been previously discussed in IE Information Notice 85-55,
"Revised Emergency Exercise Frequency Rule."
No specific action or written response is required by this information
notice. If you have any questions about this matter, please contact the
Regional Administrator of the appropriate regional office or this office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contact:
Cheryl A. Sakenas, AEOD
(301) 492-9004 Attachment: List of Recently Issued NRC Information Notices
D/DOEA:NRR C/OGCB:DOEA:NRR D/DREP:NRR
J EIpssi CHBerlinger FCongel
(0 /87 ep/ /87 &/ /87 PPMB:AR24 OGCB:DOEA:NRR IRB:DOA:AEOD C/IRB:DOA:AEOD C/PEPB:DREP:NRR
TechEM J!Ramsey tJtakenas WSPerkins atthews
09/f27/87 ANY /87 t/87 A/ /87 I/ /87 lo
|
---|
|
list | - Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis (13 January 1987, Topic: Boric Acid)
- Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes (15 January 1987, Topic: Boric Acid)
- Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel (16 January 1987, Topic: Boric Acid, Coatings)
- Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System (2 February 1987, Topic: Unanalyzed Condition, Boric Acid)
- Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon (30 January 1987, Topic: Boric Acid)
- Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors (3 February 1987, Topic: Boric Acid, Process Control Program)
- Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators (4 February 1987, Topic: Boric Acid, Anchor Darling)
- Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency (5 February 1987, Topic: Probabilistic Risk Assessment)
- Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps (11 February 1987)
- Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas (13 February 1987, Topic: Contraband)
- Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 (13 February 1987)
- Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool (24 February 1987)
- Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment (23 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended (25 March 1987)
- Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended (25 March 1987)
- Information Notice 1987-16, Degradation of Static O Ring Pressure Switches (2 April 1987)
- Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors (7 April 1987, Topic: Scram Discharge Volume)
- Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel (8 April 1987)
- Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies (9 April 1987)
- Information Notice 1987-20, Hydrogen Leak in Auxiliary Building (20 April 1987)
- Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty (11 May 1987)
- Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors (22 May 1987)
- Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation (27 May 1987, Topic: Boric Acid)
- Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters (4 June 1987)
- Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch)
- Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events (11 June 1987, Topic: Boric Acid, Fire Watch)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders (11 June 1987, Topic: Boric Acid)
- Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders (11 June 1987)
- Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources (10 June 1987, Topic: Boric Acid)
- Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors (28 December 1987, Topic: Boric Acid)
- Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators (26 June 1987, Topic: Coatings, Temporary Modification, Biofouling)
- Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors (2 July 1987)
- Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation (10 July 1987, Topic: Uranium Hexafluoride)
- Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal (10 July 1987)
- Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees (24 July 1987)
- Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems (24 July 1987)
- Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room (30 July 1987)
- Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines (4 August 1987)
- Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 (10 August 1987)
- Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants (21 August 1987, Topic: Fuel cladding)
- Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage (31 August 1987, Topic: Packing leak)
- Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers (31 August 1987)
- Information Notice 1987-42, Diesel Generator Fuse Contacts (4 September 1987)
- Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks (8 September 1987)
- Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors (16 September 1987)
- Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees (25 September 1987, Topic: High Radiation Area)
- Information Notice 1987-46, Undetected Loss of Reactor Coolant (30 September 1987)
- Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants (9 October 1987, Topic: Loctite)
- Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection (9 October 1987, Topic: Safe Shutdown)
... further results |
---|