Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20ML031050574 |
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: |
06/12/1997 |
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Revision: |
0 |
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From: |
Slosson M M Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-97-034, NUDOCS 9706090329 |
Download: ML031050574 (11) |
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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
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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>. |
June 12, 1997
NRC INFORMATION NOTICE 97-34: DEFICIENCIES IN LICENSEE SUBMITTALSREGARDING TERMINOLOGY FORRADIOLOGICAL EMERGENCY ACTION LEVELSIN ACCORDANCE WITH THE NEW PART 20
Addressees
All holders of operating licenses or construction permits for test and research reactors.PurooseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to informaddressees of the issuance of a revised Appendix I to NUREG-0849, "Standard Review Planfor the Review and Evaluation of Emergency Plans for Research and Test Reactors." Thisrevised appendix provides guidance on incorporating the new 10 CFR Part 20 regulationsinto the radiological emergency action levels (EALs). It is expected that recipients will reviewthe information for applicability to their facilities and consider actions, as appropriate.However, suggestions contained in this information notice are not NRC requirements;therefore, no specific action or written response is required.
Description of Circumstances
Part 20 was revised and the final rule was published in the Federal Register on May 21,1991 (56 FR 23360), with an original implementation date of January 1, 1993.Subsequently, the implementation date was extended to January 1, 1994 (57 FR 38588). Inresponse to these regulations, many licensees of test and research reactors have submittedto the NRC revised emergency plans that were intended to incorporate or reflect theterminology introduced in the new regulations. Title 10 of the Code of Federal Regulations,Part 20 is referenced in the section of the emergency plan involving radiological EALs.During its review of these submittals, the NRC staff noted that many licensees incorrectlyconverted the wording of the EALs from the old terminology found in NUREG-0849. As anexample, (1) some licensees inappropriately converted "maximum permissibleconcentrations" (MPCs) to "effluent concentrations" (ECs) and (2) some inaccurately used theterm "deep dose equivalent." Several licensees merely substituted the EC term for the MPCterm. Other licensees used various multipliers in an attempt to correct the differencesbetween the two values. Still other licensees replaced the MPC term with "derived airconcentration." These submittals indicate the need for additional guidance that could beused to assist in updating EALs.v52 on ax? ,
IN 97-34June 12, 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions.Guidance in the form of a revision to Appendix I to NUREG-0849 was issued in April 1997.The revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 perpage.)* The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.-The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650), for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen301-415-2923E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information Notices44AaJ p U Attachment 1IN 97-34June 12, 1997 APPENDIX IEMERGENCY CLASSESACTION LEVEL*
PURPOSE
Notification of Unusual Events INOUE)Actual or projected radiological effluentt at the siteboundary which is calculated (or measured) to resultIn either of the following conditions, both of whichare based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less:(1) A deep dose equivalent of 0.15 milliSievert(mSv) 115 mrem)OR(2) A committed effective dose equivalent of 0.15mSv [15 mrem] based on the followingconsiderations:* Ensure that the first step in any response laterfound to be necessary has been carried out.* Bring the operating staff to a state of readiness.* Provide systematic handling of unusual eventsInformation and decisionmaking.* 100 EC x 24 hr* = 2.4 x 103 EC-hr m 0.15mSv (15 mrem) (for radionuclides otherthan noble gases)* 50 EC x 24 hr = 1.2 x 103 EC-hr m 0.15mSv [15 mrem](for noble gases)tReport or observation of a severe naturalphenomenon affecting the reactor siteReceipt of bomb threat affecting the reactor facilityFire within the reactor facility not extinguished within15 minutesAlertActual or projected radiological effluentt at the siteboundary which Is calculated (or measured) to resultin either of the following conditions, both of whichare based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less:(1) A deep dose equivalent of 0.75 mSv [5mrem]OR(2) A committed effective dose equivalent of 0.75mSv 15 mrem) based on the followingconsiderations:* Ensure that emergency personnel are readilyavailable to respond If the situation becomesmore serious or to perform confirmatoryradiation monitoring If required.* Provide current offsite authorities with statusinformation.* 500 EC x 24 hr = 1.2 x 104 EC-hr -0.75mSv [75 mrem] (for radionuclides otherthan noble gases)* 250 EC x 24 hr" = 6 x 13 EC-hr m 0.75mSv (75 mrem] (for noble gases)ttActual or projected radiation levelst at the siteboundary of 0.2 mSv/hr deep dose equivalent [20mremlhr] for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 1.0 mSv 1100 mrem] to thethyroid (committed dose equivalent)
Attachment IIN 97-34June 12. 1997 APPENDIX I (cont'd)-. -W%1At;I 1IUN LtVtL-IrumrvoSite Area EmernencvActual or projected radiological effluentt at the siteboundary which is calculated (or measured) to resultin either of the following conditions both of whichare based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less:(1) A deep dose equivalent of 3.75 mSv [375mrem]OR(2) A committed effective dose equivalent of 3.75mSv [375 mrem] based on the followingconsiderations:* Ensure that response centers are manned.* Ensure that monitoring teams are dispatched.* Ensure that personnel required for evacuation ofonsite areas are at duty stations.* Provide consultation with offsite authorities.* Provide Information for the public through offskeauthorities.* 2500 EC x 24 hr = 6 x IV0 EC-hr m 3.75mSv 1375 mrem] (for radionuclides otherthan noble gases)* 1250 EC x 24 hr* = 3 x I10 EC-hr m 3.75mSv 1375 mrem](for noble gases)"Actual or projected radiation levelst at the siteboundary of 1.0 mSv/hr [100 mremlhr] deep doseequivalent for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 5.0 mSv [500 mrem] to thethyroid (committed dose equivalent)General EmergencySustained actual or projected radiation levelst at thesite boundary of 5.0 mSv/hr [500 mremlhr] deepdose equivalentActual or projected doset at the site boundary in theplume exposure pathway of 10 mSv 11 rem] (totaleffective dose equivalent) or 50 mSv 15 rem] to thethyroid (committed dose equivalent)* Initiate predetermined protective actions for thepublic.* Provide continuous assessment of Informationfrom licensee and offsite organizationmeasurements.* Initiate additional measures as Indicated byactual or potential releases.* Provide consultation with offsite authorities.* Provide updates for the public through offsiteauthorities.* The situation that may lead to an emergency class described in the subsections of Section 4.0 may bereferenced as emergency action levels appropriate to the emergency class.t It is expected that licensees will determine the relationship of the EAL dose levels at the site boundary toinstrumentation readings andlor safety analyses accident conditions for their specific facilitie Attachment IIN 97-34June 12, 1997 Effluent concentration (EC) as fisted In Title 10 of the Code of Federal Regulations, Part 20 (10 CFR Part 20),Standards for the Protection Against Radiation,* Appendix B. Table 2. If the exposure time Is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,the EC multiplier can be increased proportionately, provided that the values of 2.4 x 103 and 1.2 x 103 EC-hr areused to declare a NOUE; the proportional Increase for an alert is 5 and for a site area emergency it Is 25." Table 2 of Appendix B to 10 CFR Part 20 lists the concentration values that are equivalent to the radionuclideconcentrations which, if Inhaled or Ingested continuously over the course of a year, would produce a total effectivedose equivalent of 0.5 mSv [50 mrem]. However, for noble gases where the submersion (external dose) Islimiting, the concentration values would produce a total effective dose equivalent of I mSv [100 mrem Ki1_Attachment 2IN 97-34June 12, 1997 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to97-3395-36,Supp. 197-3297-3197-3097-29Unanticipated Effectof Ventilation Systemon Tank Level Indica-tions and EngineeringSafety Features Actua-tion System SetpointPotential Problemswith Post-Fire Emer-gency LightingDefective Worm ShaftClutch Gears inLimitorque Motor-Operated ValveActuators'Failures of ReactorCoolant Pump ThermalBarriers and CheckValves in ForeignPlantsControl of LicensedMaterial During Reorgan-izations, Employee-Management Disagreements,and Financial CrisesContainment InspectionRule06/11/9706/10/9706/10/9706/03/9706/03/9705/30/97All 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 pressurized-waterreactor plantsAll material and fuelcycle licenseesAll holders of OLs or CPsfor nuclear power reactorsOL = Operating LicenseCP = Construction Permit IN 97-34' June 12, 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions.Guidance in the form of a revision to Appendix I to NUREG-0849 was Issued in April 1997.The revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)* The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.* The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.original signed by S.H. Weiss forMarylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen(301) 415-2923E-mail: Ikcenrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information NoticesDOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCETo receive a copy of ths document, hIdicate hI the box: C' -Copy wloattachmenVenclosure E -Copy w/attachment/enclosure AN- -No copyOFFICE TECH CONI C:PERB:DRPM C:PECB:DRPM D: DRPM 6WNAME LKCohen* CLMiller* AEChaffee* MMSlosscn IDATE 05/20/97 05/22/97 05/30/97 0 //O/97OFFICIAL R ECORD COP I,IN 97-May , 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions..Guidance in the form of a revision to Appendix I to NUREG-0849 was issued in April 1997.The revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)* The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.* The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen(301) 415-2923E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information NoticesDOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCETo receive a copy of this document. indcite in the box: 'C- -Copy w/oattachmentlenclosure E' -Copy w/attachmentlenclosure 'N' -No copyOFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM DNAME LKCohen* CLMiller* AEChaffee blo, MDATE 05/20/97 05/22/97 05/so/97 0!:DRPM IlMS'lossonl)5/ /97OFFICIAL RECORD COPY ,41brJ i41M I IN 97-May , 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions.Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.This revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment I to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)* The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.* The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen(301) 415-2923E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information NoticesDOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCETo receive a copy of this document. kidicate in the box: * -Copy w/oattachment/enclosure 'E' -Copy wlattachment/enclosure *N0 -No copyOFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPM HNAMELKC ohen* I CLMiller* AEChaffee MMSossonDATE /20/97 05/22/97 05/ /97 05/ /97.FFICAL REOR COYe IN 97-May, 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions.Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.This revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)* The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.* The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.Marylee M. Slosson, Acting DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen(301) 415-2923E-mail: lkcenrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information NoticesDOCUMENT NAME: S:\DRPM SEC\RAD51 INTo receive
- copy Of this document. hndIcite In the box: C*' -Copy w/oattachment/enclosure 'E' -Copy wlattachmentlenclosure 'N' -No copyOFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPMINAME LKCohens..t CLMiller (Lb, 1AEChaffee I MMS1osson I IDATE 0/24/97 9&zV97 /97 97OFFICIAL RECORD COPY S. -, A
' ' FIN 97-May , 1997 DiscussionIf the errors in the revised EAL schemes are left uncorrected, they could potentially result in alicensee taking some conservative actions that are unwarranted or in the licensee delayingappropriate actions.Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.This revised appendix provides guidance on incorporating the current 10 CFR Part 20regulations into the radiological EALs and, at the same time, corrects some omissionsin prior guidance and clarifies some other EALs for the implementation of the newPart 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.NUREG-0849, which was published in 1983, is available from the following sources:* The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)* The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082,Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.* The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact the technical contact listedbelow or the appropriate regional office.Marylee M. Slosson, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: Lawrence K. Cohen(301) 415-2923E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-08492. List of Recently Issued NRC information NoticesDOCUMENT NAME: S:\DRPM SEC\RAD51 INTo receive a copy of this document. hIdfice hI the box: ACT -Copy w/oattachmentlenclosure 'E' -Copy w/attachmentlenclosure 'N -No copyOFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPMNAME LKCohen %4V CLMiller AEChaffee MMSlossonDATE 06711/97 04/ /97 04/ /97 04/ /97OFFICIAL RECORD COPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
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