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| {{#Wiki_filter:'SeUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001April 2, 1996NRC INFORMATION NOTICE 96-19: FAILURE OF TONE ALERT RADIOS TO ACTIVATE WHENRECEIVING A SHORTENED ACTIVATION SIGNAL | | {{#Wiki_filter:'Se UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555-0001 April 2, 1996 NRC INFORMATION |
| | |
| | NOTICE 96-19: FAILURE OF TONE ALERT RADIOS TO ACTIVATE WHEN RECEIVING |
| | |
| | A SHORTENED |
| | |
| | ACTIVATION |
| | |
| | SIGNAL |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors.PurgoseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the possibility that tone alert radios may notreliably activate when receiving a shortened activation signal. It isexpected that recipients will review the information for applicability totheir facilities and consider actions, as appropriate, to avoid similarproblems. However, suggestions contained in this information notice are notNRC requirements; therefore, no specific action or written response isrequired. | | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors.Purgose The U.S. Nuclear Regulatory |
| | |
| | Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to the possibility |
| | |
| | that tone alert radios may not reliably activate when receiving |
| | |
| | a shortened |
| | |
| | activation |
| | |
| | signal. 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 are not NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances |
| | |
| | In a report made pursuant to Section 50.72(b)(1)(v) |
| | of Title 10 of the Code o Federal Regulations |
| | |
| | (10 CFR 50.72(b)(1)(v)), Event Number 29907, dated January 30, 1996, the licensee for the Callaway site reported a problem with tone alert radios. During a test of the Emergency |
| | |
| | Alert System (EAS), a radio station engineer observed that a tone alert radio receiver did not activate.An investigation |
| | |
| | by the licensee found that the length of the broadcast activation |
| | |
| | signal was insufficient |
| | |
| | to reliably activate the tone alert radio receiver model in use at the radio station. The broadcast |
| | |
| | duration of the activation |
| | |
| | signal had been reduced from 20 seconds to 8 seconds as permitted by current Federal Communications |
| | |
| | Commission (FCC) regulations. |
| | |
| | The radio station restored the duration of the activation |
| | |
| | signal broadcast |
| | |
| | to the original 20-second |
| | |
| | length and observed that the tone alert radio receiver activated |
| | |
| | as expected.Discussion |
| | |
| | Section 50.47(b)(5) |
| | of 10 CFR requires emergency |
| | |
| | response plans for nuclear power reactors to include a means of providing |
| | |
| | early notification |
| | |
| | and clear instruction |
| | |
| | to the populace within the plume exposure pathway emergency planning zone (EPZ) in the event of an emergency. |
| | |
| | Many nuclear power reactor sites have integrated |
| | |
| | tone alert radios into alert and notification |
| | |
| | systems used to notify and provide instructions |
| | |
| | to members of the general public near the site during emergency |
| | |
| | situations. |
| | |
| | t$DR~~~~ If aeq 0n 9Goc 9603270127 |
| | 1\ - |
| | % i KY-2 IN 96-19 April 2, 1996 These radios may serve as supplements |
| | |
| | to a siren system by filling in voids in siren coverage, or they can be the principal |
| | |
| | means of notifying |
| | |
| | the EPZ population. |
| | |
| | Tone alert radio receivers |
| | |
| | are used in conjunction |
| | |
| | with the EAS.On December 28, 1994, the FCC issued a Report and Order (59 FR 67090)concerning |
| | |
| | the Emergency |
| | |
| | Broadcast |
| | |
| | System (EBS). This Report and Order replaced the EBS with what is now known as the EAS. This change allowed for the creation of a new generation |
| | |
| | of alerting equipment |
| | |
| | embracing |
| | |
| | digital technology. |
| | |
| | The change also modified some of the old EBS requirements. |
| | |
| | One of the changes permits the use of a shorter duration tone activation |
| | |
| | signal to activate tone alert radio receivers. |
| | |
| | This change may have decreased |
| | |
| | the reliability |
| | |
| | of some tone alert radios currently |
| | |
| | in use to activate when required.Before July 1, 1995, the broadcast |
| | |
| | duration of the signal that activates |
| | |
| | tone alert radios was required to be between 20 and 25 seconds. After July 1, 1995, the broadcast |
| | |
| | duration of the signal that activates |
| | |
| | tone alert radios was permitted |
| | |
| | to be between 8 and 25 seconds. The FCC encourages |
| | |
| | the use of the longer (up to 25 seconds) tone during emergencies. |
| | |
| | Tone alert radio receivers |
| | |
| | are, and have been, available |
| | |
| | from various manufacturers |
| | |
| | for several years. Depending |
| | |
| | on the specifications |
| | |
| | provided by the purchaser, the threshold |
| | |
| | for activation |
| | |
| | has been built into receivers. |
| | |
| | The signal duration needed for some tone alert radio receiver models may be longer than the currently |
| | |
| | approved 8-second minimum signal duration now allowed by FCC regulations. |
| | |
| | The FCC regulations |
| | |
| | permit individual |
| | |
| | radio stations to select the duration of the activation |
| | |
| | signal they broadcast, provided it is within the limits of 8 to 25 seconds. To reliably activate a tone alert radio receiver the duration of the activation |
| | |
| | signal broadcast |
| | |
| | by the radio station must be long enough to meet the activation |
| | |
| | threshold |
| | |
| | built into tone alert radio receivers |
| | |
| | in service in a particular |
| | |
| | reception |
| | |
| | area. If the duration of the activation |
| | |
| | signal broadcast |
| | |
| | is not compatible |
| | |
| | with the threshold |
| | |
| | set in a receiver, the reliability |
| | |
| | of the receiver response is questionable. |
| | |
| | Either the duration of the activation |
| | |
| | signal broadcast |
| | |
| | or the threshold |
| | |
| | for activation |
| | |
| | built into receivers |
| | |
| | may need to be modified to ensure compatibility. |
| | |
| | i N' '' IN 96-19 April 2, 1996 This Information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Den4 o. Cru e , Director Division of Reactor Project Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl~nrc.gov |
| | |
| | J. L. Birmingham, NRR (301) 415-2829 Internet:lb4@nrc.gov |
| | |
| | Attachment: |
| | List of A b1~f;ilivJ- |
| | Recently Issued NRC Information |
| | |
| | Notices%b eo |
| | |
| | Attachment |
| | |
| | IN 96-19 April 2, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 96-18 95-03 Supp. 1 96-17 96-16 Compliance |
| | |
| | with 10 CFR Part 20 for Airborne Thorium Loss of Reactor Coolant Inventory |
| | |
| | and Potential Loss of Emergency |
| | |
| | Mitiga-tion Functions |
| | |
| | While in a Shutdown Condition Reactor Operation |
| | |
| | Incon-sistent with the Updated Final Safety Analysis Report BWR Operation |
| | |
| | with Indicated |
| | |
| | ===Flow Less Than Natural Circulation=== |
| | Unexpected |
| | |
| | Plant Perform-ance During Performance |
| | |
| | of New Surveillance |
| | |
| | Tests Degradation |
| | |
| | of Radwaste Facility Equipment |
| | |
| | at Millstone |
| | |
| | Nuclear Power Station, Unit 1 Potential |
| | |
| | Containment |
| | |
| | Leak Paths Through Hydrogen Analyzers Control Rod Insertion Problems 03/25/96 03/25/96 03/18/96 03/14/96 03/08/96 03/01/96 02/26/96 02/15/96 All material licensees authorized |
| | |
| | to possess and use thorium in unsealed form All holders of OLs or CPs for PWR power plants All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for boiling-water |
| | |
| | reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors 96-15 96-14 96-13 96-12 OL = Operating |
| | |
| | License CP = Construction |
| | |
| | Permit |
| | |
| | IN 96-xx March xx, 1996 This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Project Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl~nrc.gov |
| | |
| | J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov |
| | |
| | Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices* See previous concurrence |
| | |
| | OFFICE PERB:DRPM:NRR |
| | |
| | SC/PERB:DRPM |
| | |
| | I C/PERB:DRPM:NRR |
| | |
| | NAME DMBarss* THEssig* CLMiller*I DATE 03/18/96 03/18/96 I 03/18/96 OFFICE TECHED:RPB |
| | |
| | PECB:DRPM:NRR |
| | |
| | C/PECT.VPM.?NRR |
| | |
| | D/DRPM:HRR |
| | |
| | NAME BCalure* l JBirmingham* |
| | |
| | ===AEChaffJ DMCrutchfield=== |
| | DATE I03/ /96 03/21/96 03/a2/96 V0! 03/ /96.rrt -t~~s e rserl swur 1.w -ntn^ *a.PlrIULAL WULUiILFI |
| | |
| | wAML: b: JLL1 I\UNLALKI.1N |
| | |
| | IN 96-xx March xx, 1996 This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Project Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl@nrc.gov |
| | |
| | J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov |
| | |
| | Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices 11 5 ?ee-e a 4jo&5 Cti4et- A4J-t.OFFICE PERB:DRPM:NRR |
| | |
| | SC/PERB:DQPM |
| | |
| | C/PERB:DRPNRR |
| | |
| | NAME DMBarss Z&N 6 THEssig 1& J MWller l_ _ _ are __ _= .. .-_I_ .DATE 03/IJ/96 j 03/0TV/96 l 03I%'iI96 J OFFICE TECHED:RPB |
| | |
| | PECB:DRPM:NRR |
| | |
| | C/PECB:DRPM:NRR |
| | |
| | D/DRPM:NRR |
| | |
| | NAME 1 JBirmingham |
| | |
| | -AEChaffee |
| | |
| | ===DLCrutchfield=== |
| | DATE I03/'t /96 1031&'196/4 |
| | 03/ /96 103/ A96 O DUMT N--E: : _ _ -._. ..OFFICIAL DOCUMENT NAME: G:.\MLMUS\1UNLALK1.1N |
| | |
| | OFFICE PERB:DRPM:NRR |
| | |
| | SC/PERB:DRPM |
| | |
| | C/PERB:DRPM:NRR |
|
| |
|
| ==Description of Circumstances==
| | NAME DMBarss THEssig CLMiller.DATE 03/ /96 03//96 03/ /96 OFFICE TECH PECB:DRPM:NRR |
| In a report made pursuant to Section 50.72(b)(1)(v) of Title 10 of the Code oFederal Regulations (10 CFR 50.72(b)(1)(v)), Event Number 29907, datedJanuary 30, 1996, the licensee for the Callaway site reported a problem withtone alert radios. During a test of the Emergency Alert System (EAS), a radiostation engineer observed that a tone alert radio receiver did not activate.An investigation by the licensee found that the length of the broadcastactivation signal was insufficient to reliably activate the tone alert radioreceiver model in use at the radio station. The broadcast duration of theactivation signal had been reduced from 20 seconds to 8 seconds as permittedby current Federal Communications Commission (FCC) regulations. The radiostation restored the duration of the activation signal broadcast to theoriginal 20-second length and observed that the tone alert radio receiveractivated as expected.DiscussionSection 50.47(b)(5) of 10 CFR requires emergency response plans for nuclearpower reactors to include a means of providing early notification and clearinstruction to the populace within the plume exposure pathway emergencyplanning zone (EPZ) in the event of an emergency. Many nuclear power reactorsites have integrated tone alert radios into alert and notification systemsused to notify and provide instructions to members of the general public nearthe site during emergency situations.t$DR~~~~ If aeq 0n 9Goc96032701271\ -
| |
| % iKY-2 IN 96-19April 2, 1996 These radios may serve as supplements to a siren system by filling in voids insiren coverage, or they can be the principal means of notifying the EPZpopulation. Tone alert radio receivers are used in conjunction with the EAS.On December 28, 1994, the FCC issued a Report and Order (59 FR 67090)concerning the Emergency Broadcast System (EBS). This Report and Orderreplaced the EBS with what is now known as the EAS. This change allowed forthe creation of a new generation of alerting equipment embracing digitaltechnology. The change also modified some of the old EBS requirements. Oneof the changes permits the use of a shorter duration tone activation signal toactivate tone alert radio receivers. This change may have decreased thereliability of some tone alert radios currently in use to activate whenrequired.Before July 1, 1995, the broadcast duration of the signal that activates tonealert radios was required to be between 20 and 25 seconds. After July 1,1995, the broadcast duration of the signal that activates tone alert radioswas permitted to be between 8 and 25 seconds. The FCC encourages the use ofthe longer (up to 25 seconds) tone during emergencies.Tone alert radio receivers are, and have been, available from variousmanufacturers for several years. Depending on the specifications provided bythe purchaser, the threshold for activation has been built into receivers.The signal duration needed for some tone alert radio receiver models may belonger than the currently approved 8-second minimum signal duration nowallowed by FCC regulations.The FCC regulations permit individual radio stations to select the duration ofthe activation signal they broadcast, provided it is within the limits of 8 to25 seconds. To reliably activate a tone alert radio receiver the duration ofthe activation signal broadcast by the radio station must be long enough tomeet the activation threshold built into tone alert radio receivers in servicein a particular reception area. If the duration of the activation signalbroadcast is not compatible with the threshold set in a receiver, thereliability of the receiver response is questionable. Either the duration ofthe activation signal broadcast or the threshold for activation built intoreceivers may need to be modified to ensure compatibility.
| |
|
| |
|
| i N' '' IN 96-19April 2, 1996 This Information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Den4 o. Cru e , DirectorDivision of Reactor Project ManagementOffice of Nuclear Reactor RegulationTechnical contacts:D. M. Barss, NRR(301) 415-2922Internet:dmbl~nrc.govJ. L. Birmingham, NRR(301) 415-2829Internet:lb4@nrc.govAttachment: List ofA b1~f;ilivJ-Recently Issued NRC Information Notices%b eo
| | C/PECB:DRPM:NRR |
|
| |
|
| AttachmentIN 96-19April 2, 1996 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to96-1895-03Supp. 196-1796-16Compliance with 10 CFRPart 20 for AirborneThoriumLoss of Reactor CoolantInventory and PotentialLoss of Emergency Mitiga-tion Functions While in aShutdown ConditionReactor Operation Incon-sistent with the UpdatedFinal Safety AnalysisReportBWR Operation withIndicated Flow Less ThanNatural CirculationUnexpected Plant Perform-ance During Performanceof New Surveillance TestsDegradation of RadwasteFacility Equipment atMillstone Nuclear PowerStation, Unit 1Potential ContainmentLeak Paths ThroughHydrogen AnalyzersControl Rod InsertionProblems03/25/9603/25/9603/18/9603/14/9603/08/9603/01/9602/26/9602/15/96All material licenseesauthorized to possess anduse thorium in unsealedformAll holders of OLs or CPsfor PWR power plantsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor boiling-water reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactorsAll holders of OLs or CPsfor nuclear power reactors96-1596-1496-1396-12OL = Operating LicenseCP = Construction Permit
| | D/DRPM:NRR |
|
| |
|
| IN 96-xxMarch xx, 1996 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Project ManagementOffice of Nuclear Reactor RegulationTechnical contacts:D. M. Barss, NRR(301) 415-2922Internet:dmbl~nrc.govJ. L. Birmingham, NRR(301) 415-2829Internet:jlb4@nrc.govAttachment:List of Recently Issued NRC Information Notices* See previous concurrenceOFFICE PERB:DRPM:NRR SC/PERB:DRPM I C/PERB:DRPM:NRRNAME DMBarss* THEssig* CLMiller*IDATE03/18/9603/18/96I03/18/96OFFICE TECHED:RPB PECB:DRPM:NRR C/PECT.VPM.?NRR D/DRPM:HRRNAME BCalure* l JBirmingham* AEChaffJ DMCrutchfieldDATE I03/ /96 03/21/96 03/a2/96 V0! 03/ /96.rrt -t~~s e rserl swur 1.w -ntn^ *a.PlrIULAL WULUiILFI wAML: b: JLL1 I\UNLALKI.1N
| | NAME 4 JBirmningham |
|
| |
|
| IN 96-xxMarch xx, 1996 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Project ManagementOffice of Nuclear Reactor RegulationTechnical contacts:D. M. Barss, NRR(301) 415-2922Internet:dmbl@nrc.govJ. L. Birmingham, NRR(301) 415-2829Internet:jlb4@nrc.govAttachment:List of Recently Issued NRC Information Notices11 5 ?ee-e a 4jo&5 Cti4et- A4J-t.OFFICE PERB:DRPM:NRR SC/PERB:DQPM C/PERB:DRPNRRNAME DMBarss Z&N 6 THEssig 1& J MWller l_ _ _ are __ _= .. .-_I_ .DATE 03/IJ/96 j 03/0TV/96 l 03I%'iI96 JOFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRRNAME 1 JBirmingham -AEChaffee DLCrutchfieldDATE I03/'t /96 1031&'196/4 03/ /96 103/ A96O DUMT N--E: : _ _ -._. ..OFFICIAL DOCUMENT NAME:G:.\MLMUS\1UNLALK1.1N
| | AEChaffee |
|
| |
|
| OFFICE PERB:DRPM:NRR SC/PERB:DRPM C/PERB:DRPM:NRRNAME DMBarss THEssig CLMiller.DATE03/ /9603//9603/ /96OFFICE TECH PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRRNAME 4 JBirmningham AEChaffee DLCrutchfieldDATE 03//P96 03/ /96 03/ /96 03/ /96-.r .I .rl., , nu n ... uuS e -t. * .lr 4- AI .t ValUrlWlAL UULUMtNI NAML:b: FILMUZO\ I URALK I. I *
| | ===DLCrutchfield=== |
| }} | | DATE 03//P96 03/ /96 03/ /96 03/ /96-.r .I .rl., , nu n ... uuS e -t. * .lr 4- AI .t Val UrlWlAL UULUMtNI NAML: b: FILMUZO\ I URALK I. I *}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation SignalML031060187 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
04/02/1996 |
---|
From: |
Crutchfield D M Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-96-019, NUDOCS 9603270127 |
Download: ML031060187 (7) |
|
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[: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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
'Se UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 April 2, 1996 NRC INFORMATION
NOTICE 96-19: FAILURE OF TONE ALERT RADIOS TO ACTIVATE WHEN RECEIVING
A SHORTENED
ACTIVATION
SIGNAL
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.Purgose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to the possibility
that tone alert radios may not reliably activate when receiving
a shortened
activation
signal. 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 are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
In a report made pursuant to Section 50.72(b)(1)(v)
of Title 10 of the Code o Federal Regulations
(10 CFR 50.72(b)(1)(v)), Event Number 29907, dated January 30, 1996, the licensee for the Callaway site reported a problem with tone alert radios. During a test of the Emergency
Alert System (EAS), a radio station engineer observed that a tone alert radio receiver did not activate.An investigation
by the licensee found that the length of the broadcast activation
signal was insufficient
to reliably activate the tone alert radio receiver model in use at the radio station. The broadcast
duration of the activation
signal had been reduced from 20 seconds to 8 seconds as permitted by current Federal Communications
Commission (FCC) regulations.
The radio station restored the duration of the activation
signal broadcast
to the original 20-second
length and observed that the tone alert radio receiver activated
as expected.Discussion
Section 50.47(b)(5)
of 10 CFR requires emergency
response plans for nuclear power reactors to include a means of providing
early notification
and clear instruction
to the populace within the plume exposure pathway emergency planning zone (EPZ) in the event of an emergency.
Many nuclear power reactor sites have integrated
tone alert radios into alert and notification
systems used to notify and provide instructions
to members of the general public near the site during emergency
situations.
t$DR~~~~ If aeq 0n 9Goc 9603270127
1\ -
% i KY-2 IN 96-19 April 2, 1996 These radios may serve as supplements
to a siren system by filling in voids in siren coverage, or they can be the principal
means of notifying
the EPZ population.
Tone alert radio receivers
are used in conjunction
with the EAS.On December 28, 1994, the FCC issued a Report and Order (59 FR 67090)concerning
the Emergency
Broadcast
System (EBS). This Report and Order replaced the EBS with what is now known as the EAS. This change allowed for the creation of a new generation
of alerting equipment
embracing
digital technology.
The change also modified some of the old EBS requirements.
One of the changes permits the use of a shorter duration tone activation
signal to activate tone alert radio receivers.
This change may have decreased
the reliability
of some tone alert radios currently
in use to activate when required.Before July 1, 1995, the broadcast
duration of the signal that activates
tone alert radios was required to be between 20 and 25 seconds. After July 1, 1995, the broadcast
duration of the signal that activates
tone alert radios was permitted
to be between 8 and 25 seconds. The FCC encourages
the use of the longer (up to 25 seconds) tone during emergencies.
Tone alert radio receivers
are, and have been, available
from various manufacturers
for several years. Depending
on the specifications
provided by the purchaser, the threshold
for activation
has been built into receivers.
The signal duration needed for some tone alert radio receiver models may be longer than the currently
approved 8-second minimum signal duration now allowed by FCC regulations.
The FCC regulations
permit individual
radio stations to select the duration of the activation
signal they broadcast, provided it is within the limits of 8 to 25 seconds. To reliably activate a tone alert radio receiver the duration of the activation
signal broadcast
by the radio station must be long enough to meet the activation
threshold
built into tone alert radio receivers
in service in a particular
reception
area. If the duration of the activation
signal broadcast
is not compatible
with the threshold
set in a receiver, the reliability
of the receiver response is questionable.
Either the duration of the activation
signal broadcast
or the threshold
for activation
built into receivers
may need to be modified to ensure compatibility.
i N' IN 96-19 April 2, 1996 This Information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Den4 o. Cru e , Director Division of Reactor Project Management
Office of Nuclear Reactor Regulation
Technical
contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl~nrc.gov
J. L. Birmingham, NRR (301) 415-2829 Internet:lb4@nrc.gov
Attachment:
List of A b1~f;ilivJ-
Recently Issued NRC Information
Notices%b eo
Attachment
IN 96-19 April 2, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-18 95-03 Supp. 1 96-17 96-16 Compliance
with 10 CFR Part 20 for Airborne Thorium Loss of Reactor Coolant Inventory
and Potential Loss of Emergency
Mitiga-tion Functions
While in a Shutdown Condition Reactor Operation
Incon-sistent with the Updated Final Safety Analysis Report BWR Operation
with Indicated
Flow Less Than Natural Circulation
Unexpected
Plant Perform-ance During Performance
of New Surveillance
Tests Degradation
of Radwaste Facility Equipment
at Millstone
Nuclear Power Station, Unit 1 Potential
Containment
Leak Paths Through Hydrogen Analyzers Control Rod Insertion Problems 03/25/96 03/25/96 03/18/96 03/14/96 03/08/96 03/01/96 02/26/96 02/15/96 All material licensees authorized
to possess and use thorium in unsealed form All holders of OLs or CPs for PWR power plants All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for boiling-water
reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors 96-15 96-14 96-13 96-12 OL = Operating
License CP = Construction
Permit
IN 96-xx March xx, 1996 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Project Management
Office of Nuclear Reactor Regulation
Technical
contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl~nrc.gov
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices* See previous concurrence
OFFICE PERB:DRPM:NRR
SC/PERB:DRPM
I C/PERB:DRPM:NRR
NAME DMBarss* THEssig* CLMiller*I DATE 03/18/96 03/18/96 I 03/18/96 OFFICE TECHED:RPB
PECB:DRPM:NRR
C/PECT.VPM.?NRR
D/DRPM:HRR
NAME BCalure* l JBirmingham*
AEChaffJ DMCrutchfield
DATE I03/ /96 03/21/96 03/a2/96 V0! 03/ /96.rrt -t~~s e rserl swur 1.w -ntn^ *a.PlrIULAL WULUiILFI
wAML: b: JLL1 I\UNLALKI.1N
IN 96-xx March xx, 1996 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Project Management
Office of Nuclear Reactor Regulation
Technical
contacts: D. M. Barss, NRR (301) 415-2922 Internet:dmbl@nrc.gov
J. L. Birmingham, NRR (301) 415-2829 Internet:jlb4@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices 11 5 ?ee-e a 4jo&5 Cti4et- A4J-t.OFFICE PERB:DRPM:NRR
SC/PERB:DQPM
C/PERB:DRPNRR
NAME DMBarss Z&N 6 THEssig 1& J MWller l_ _ _ are __ _= .. .-_I_ .DATE 03/IJ/96 j 03/0TV/96 l 03I%'iI96 J OFFICE TECHED:RPB
PECB:DRPM:NRR
C/PECB:DRPM:NRR
D/DRPM:NRR
NAME 1 JBirmingham
-AEChaffee
DLCrutchfield
DATE I03/'t /96 1031&'196/4
03/ /96 103/ A96 O DUMT N--E: : _ _ -._. ..OFFICIAL DOCUMENT NAME: G:.\MLMUS\1UNLALK1.1N
OFFICE PERB:DRPM:NRR
SC/PERB:DRPM
C/PERB:DRPM:NRR
NAME DMBarss THEssig CLMiller.DATE 03/ /96 03//96 03/ /96 OFFICE TECH PECB:DRPM:NRR
C/PECB:DRPM:NRR
D/DRPM:NRR
NAME 4 JBirmningham
AEChaffee
DLCrutchfield
DATE 03//P96 03/ /96 03/ /96 03/ /96-.r .I .rl., , nu n ... uuS e -t. * .lr 4- AI .t Val UrlWlAL UULUMtNI NAML: b: FILMUZO\ I URALK I. I *
|
---|
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
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