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| | issue date = 04/02/1996 | | | issue date = 04/02/1996 |
| | title = Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal | | | title = Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal |
| | author name = Crutchfield D M | | | author name = Crutchfield D |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| {{#Wiki_filter:'Se April 2, 1996NRC INFORMATION NOTICE 96-19: FAILURE OF TONE ALERT RADIOS TO ACTIVATE WHENRECEIVING A SHORTENED ACTIVATION SIGNAL | | {{#Wiki_filter:'Se |
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| | 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 |
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| |
|
| ==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== | | ==Description of Circumstances== |
| 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\ - | | In a report made pursuant to Section 50.72(b)(1)(v) of Title 10 of the Code o |
| % 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 compatibilit 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.gov | | |
| | 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 Cru e , Director |
| | |
| | o. |
| | |
| | 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 Recently Issued NRC Information Notices |
| | |
| | A b1~f;ilivJ- eo |
| | |
| | %b |
| | |
| | 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 Compliance with 10 CFR 03/25/96 All material licensees |
| | |
| | Part 20 for Airborne authorized to possess and |
| | |
| | Thorium use thorium in unsealed |
| | |
| | form |
| | |
| | 95-03 Loss of Reactor Coolant 03/25/96 All holders of OLs or CPs |
| | |
| | Supp. 1 Inventory and Potential for PWR power plants |
| | |
| | Loss of Emergency Mitiga- tion Functions While in a |
| | |
| | Shutdown Condition |
| | |
| | 96-17 Reactor Operation Incon- 03/18/96 All holders of OLs or CPs |
| | |
| | sistent with the Updated for nuclear power reactors |
| | |
| | Final Safety Analysis |
| | |
| | Report |
| | |
| | 96-16 BWR Operation with 03/14/96 All holders of OLs or CPs |
| | |
| | Indicated Flow Less Than for boiling-water reactors |
| | |
| | Natural Circulation |
| | |
| | 96-15 Unexpected Plant Perform- 03/08/96 All holders of OLs or CPs |
| | |
| | ance During Performance for nuclear power reactors |
| | |
| | of New Surveillance Tests |
| | |
| | 96-14 Degradation of Radwaste 03/01/96 All holders of OLs or CPs |
| | |
| | Facility Equipment at for nuclear power reactors |
| | |
| | Millstone Nuclear Power |
| | |
| | Station, Unit 1 |
| | 96-13 Potential Containment 02/26/96 All holders of OLs or CPs |
| | |
| | Leak Paths Through for nuclear power reactors |
| | |
| | Hydrogen Analyzers |
| | |
| | 96-12 Control Rod Insertion 02/15/96 All holders of OLs or CPs |
| | |
| | Problems for nuclear power reactors |
| | |
| | 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 |
| | |
| | NAME |
| | |
| | DATE |
| | |
| | OFFICE |
| | |
| | NAME |
| | |
| | PERB:DRPM:NRR |
| | |
| | DMBarss* |
| | 03/18/96 TECHED:RPB |
| | |
| | BCalure* |
| | SC/PERB:DRPM |
| | |
| | THEssig* |
| | 03/18/96 PECB:DRPM:NRR |
| | |
| | lJBirmingham* |
| | IC/PERB:DRPM:NRR |
| | |
| | CLMiller* |
| | I 03/18/96 C/PECT.VPM.?NRR |
| | |
| | AEChaffJ |
| | |
| | ID/DRPM:HRR |
| | |
| | DMCrutchfield |
| | |
| | DATE I03/ |
| | - t~~s |
| | |
| | .rrterserl |
| | |
| | /96 swur |
| | |
| | 03/21/96 |
| | 1.wntn^ |
| | - |
| | 03/a2/96 |
| | *a. |
| | |
| | V0! 03/ /96 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 |
| | |
| | 115 ?ee- e a Cti4et- A4J-t. |
| | |
| | 4jo&5 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 j03/0TV/96 l 03I%'iI96 J |
| | |
| | OFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRR |
| | |
| | NAME 1 JBirmingham - AEChaffee |
| | |
| | 03/ /96 DLCrutchfield |
| | |
| | 103/ A96 DATE I03/'t /96 1031&'196/4 _. .. |
| | |
| | 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., , nun . .. |
| | |
| | * t. |
|
| |
|
| ===Attachment:===
| | - uuS e .lr AI |
| List ofA b1~f;ilivJ-Recently Issued NRC Information Notices%b eo 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 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.gov
| |
|
| |
|
| ===Attachment:===
| | 4- .t Val |
| 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 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.gov
| |
|
| |
|
| ===Attachment:===
| | UrlWlAL UULUMtNI NAML: b: FILMUZO\ I URALK I.* I}} |
| 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 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 *}}
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| {{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 |
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Issue date: |
04/02/1996 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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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~~~~
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9603270127
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-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 Cru e , Director
o.
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 Recently Issued NRC Information Notices
A b1~f;ilivJ- eo
%b
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 Compliance with 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed
form
95-03 Loss of Reactor Coolant 03/25/96 All holders of OLs or CPs
Supp. 1 Inventory and Potential for PWR power plants
Loss of Emergency Mitiga- tion Functions While in a
Shutdown Condition
96-17 Reactor Operation Incon- 03/18/96 All holders of OLs or CPs
sistent with the Updated for nuclear power reactors
Final Safety Analysis
Report
96-16 BWR Operation with 03/14/96 All holders of OLs or CPs
Indicated Flow Less Than for boiling-water reactors
Natural Circulation
96-15 Unexpected Plant Perform- 03/08/96 All holders of OLs or CPs
ance During Performance for nuclear power reactors
of New Surveillance Tests
96-14 Degradation of Radwaste 03/01/96 All holders of OLs or CPs
Facility Equipment at for nuclear power reactors
Millstone Nuclear Power
Station, Unit 1
96-13 Potential Containment 02/26/96 All holders of OLs or CPs
Leak Paths Through for nuclear power reactors
Hydrogen Analyzers
96-12 Control Rod Insertion 02/15/96 All holders of OLs or CPs
Problems for nuclear power reactors
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
OFFICE
NAME
DATE
OFFICE
NAME
PERB:DRPM:NRR
DMBarss*
03/18/96 TECHED:RPB
BCalure*
SC/PERB:DRPM
THEssig*
03/18/96 PECB:DRPM:NRR
lJBirmingham*
IC/PERB:DRPM:NRR
CLMiller*
I 03/18/96 C/PECT.VPM.?NRR
AEChaffJ
ID/DRPM:HRR
DMCrutchfield
DATE I03/
- t~~s
.rrterserl
/96 swur
03/21/96
1.wntn^
-
03/a2/96
V0! 03/ /96 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
115 ?ee- e a Cti4et- A4J-t.
4jo&5 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 j03/0TV/96 l 03I%'iI96 J
OFFICE TECHED:RPB PECB:DRPM:NRR C/PECB:DRPM:NRR D/DRPM:NRR
NAME 1 JBirmingham - AEChaffee
03/ /96 DLCrutchfield
103/ A96 DATE I03/'t /96 1031&'196/4 _. ..
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., , nun . ..
- uuS e .lr AI
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|
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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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