Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam GeneratorsML031060234 |
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: |
09/22/1995 |
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From: |
Crutchfield D M Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-95-041, NUDOCS 9509180341 |
Download: ML031060234 (12) |
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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>. |
K9J( September 22, 1995NRC INFORMATION NOTICE 95-41: DEGRADATION OF VENTILATION SYSTEM CHARCOALRESULTING FROM CHEMICAL CLEANING OF STEAMGENERATORS
Addressees
All holders of operating licenses or construction permits for nuclear powerreactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to the potential degradation of ventilation systemcharcoal as a result of the charcoal's exposure to chemicals during thechemical cleaning of steam generators. It is expected that recipients willreview the information for applicability to their facilities and consideractions, as appropriate, to avoid similar problems. However, suggestionscontained in this information notice are not NRC requirements; therefore, nospecific action or written response is required.
Description of Circumstances
On June 5, 1994, a chemical cleaning of the secondary sides of the steamgenerators at Surry Unit 2 was begun. During this cleaning, containment purgewas established using train A of the auxiliary ventilation system, whichcontains a safety-grade charcoal adsorber. The chemical cleaning processinvolves the--use of ethylene diamine tetraacetic acid (EDTA) as the cleaningagent and of various other chemicals such as ethylenediamine (EDA), hydrazine,ammonia, hydrogen peroxide, nitrogen, and CCl-801, a proprietary corrosioninhibitor. During the chemical cleaning the steam generators were isolatedfrom the containment atmosphere and force-vented to the outdoor atmospherethrough the atmospheric steam dump relief valves. The steam generators wererinsed to remove residual chemicals. After the rinse, the steam generatorswere opened for sludge lancing of the tube sheet region.On June 16, 1994, a strong odor of ammonia was reported in the Unit 2containment. Concentrations were measured at 30 ppm (parts per million)ammonia and 6 ppm hydrazine. Consequently, personnel were evacuated from thecontainment. At the time of the evacuation, the chemical cleaning and rinsehad been completed on steam generators A and C and the steam generators werevented to the containment. Because of the elevated levels of hydrazine andammonia in the containment, train B of the auxiliary ventilation system wasstarted to assist train A in reducing the airborne concentrations. Bothtrains operated approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until chemical concentrations in thecontainment were reduced.950918034t~q~gut II @
IN 95-41September 22, 1995 -As a result of the exposure of the charcoal to the chemicals, in accordancewith the technical specifications (TS), a sample of train A charcoal was takenand a laboratory test of a sample of the sample was performed. The results ofthe laboratory test showed a methyl iodide removal efficiency of 93.4 percent,which was below the TS limit. The charcoal was replaced. A sample fromtrain B was tested and the results of the laboratory test of that sampleshowed a methyl iodide removal efficiency of 90.7 percent. This value wasalso below the TS limit, and the train B charcoal was replaced.The failure of these samples was a surprise to the licensee. At the time thecharcoal was determined to have failed, train A had operated for 657 hours0.0076 days <br />0.183 hours <br />0.00109 weeks <br />2.499885e-4 months <br />,while the train B had operated for 360 hours0.00417 days <br />0.1 hours <br />5.952381e-4 weeks <br />1.3698e-4 months <br />. In addition, the licensee hadheld discussions with the charcoal supplier during which the supplier hadindicated that exposure of the charcoal to hydrazine and ammonia in the abovenoted concentrations should not have resulted in its degradation.As a result of the experience at Unit 2, when the steam generators at Unit 1were chemically cleaned, the licensee arranged for the containment flow to bediverted to a non-safety-grade system containing charcoal. When the licenseecompleted the cleaning operation, laboratory testing of the charcoal in thenon-safety-grade system showed that the adsorber efficiency was 3.3 percentless than its efficiency before the chemical cleaning. On the basis of thesetwo experiences, the licensee concluded that discharging the air involved insteam generator cleaning operations through systems containing charcoal waslikely to degrade the charcoal.The licensee's laboratory tests of the charcoal were performed at 30C [86°F]and a relative humidity of 95 percent with a face velocity of 24.4 meters perminute [80 feet per minute]. The laboratory tests were conducted using the1979 version of American Society for Testing and Materials (ASTM) D3803,Standard Test Method for Nuclear-Grade Activated Carbon.' The licensee didnot attempt to determine the chemical compound responsible for the degradationof the charcoal. However, it and its charcoal supplier believe that theprobable culprits were EDA and EDTA.The NRC staff held telephone conversations with charcoal suppliers andtesting laboratory representatives. Based upon these conversations, theparties concluded that, although the ammonia did not contribute to thedegradation of the charcoal, the breakdown of hydrazine in the charcoal mayhave contributed additional moisture to the charcoal resulting in itsdegradation. These discussions also confirmed that both EDA and EDTA coulddegrade the charcoal. The staff also noted that, had the licensee performedthe laboratory tests in accordance with the guidance in NRC Information Notice87-32, "Deficiencies in the Testing of Nuclear-Grade Activated Charcoal,"(Accession No. 8707070003) or in accordance with the 1989 version of ASTMD3803, the measured degradation of the charcoal would have been greater thanthat identified by the license K..- V IN 95-41September 22, 1995 Exposure of charcoal to chemical compounds can result in its degradation.With such degradation, in the event of an accident, the charcoal may performat an efficiency less than that assumed in the staff's safety evaluation.Therefore, if licensees divert air flow through charcoal adsorbers in theirventilation systems during and/or after chemical cleaning, they may find itappropriate to perform a laboratory test of the charcoal to ensure that thecharcoal has not degraded below its TS surveillance requirements limit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.'nn .1%ic IDivision of Reactor Pr ram ManagementOffice of Nuclear Reactor RegulationTechnical contact: John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesA4e UQ FJLa
~1 <-J Attachment 1IN 95-41September 22, 1995 Referenced Codes and StandardsAmerican Society for Testing and Materials, ASTM D3803, "Standard Test Methodfor Nuclear-Grade Activated Carbon,' Philadelphia, Pennsylvani wXvachment 2IN 95-41September 22, 1995 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to95-4095-3995-3895-37Supplemental Informationto Generic Letter 95-03,"Circumferential Crackingof Steam Generator Tubes"Brachytherapy IncidentsInvolving TreatmentPlanning ErrorsDegradation of BoraflexNeutron Absorber inSpent Fuel Storage RacksInadequate Offsite PowerSystem Voltages duringDesign-Basis Events09/20/9509/19/9509/08/9509/07/95All holders of OLs or CPsfor nuclear power reactors.All U.S. Nuclear RegulatoryCommission MedicalLicensees.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.95-36PotentialPost-FireLightingProblems withEmergency08/29/95All holders of OLs or CPsfor nuclear power reactors.95-3595-3493-83,Supp. 195-33Degraded Ability ofSteam Generators toRemove Decay Heat byNatural CirculationAir Actuator and SupplyAir Regulator Problems inCopes-Vulcan PressurizerPower-Operated Relief ValvesPotential Loss of SpentFuel Pool Cooling After aLoss-of-Coolant Accidentor a Loss of Offsite PowerSwitchgear Fire andPartial Loss of OffsitePower at WaterfordGenerating Station, Unit 308/28/9508/25/9508/24/9508/23/95All holders of OLs or CPsfor pressurized waterreactors (PWRs).All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.IOL -Operating LicenseCP = Construction Permit K>IN 95-41September 22, 995Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.orig /s/'d by DMCrutchfieldDennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME: 95-41.IN*See previous concurrenceTo receive a copy of this document, indicate In the box: C' = Copy without attachment/enclosure 'E' = Copy with attachmentlenclosure 'N' -No copyOFFICE TERB:DOTS IC ADM:PUB IN OECB:DOPS I E SC/TERB:DOTS E C/TERB:DOTS LENAME JJHayes* Tech Ed/MMejac* RABenedict* RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 105/02/ 95 05/02/95.....-.IOFFICE1SC/OECB:DOPSIN IPECB:DRPMI E IC/PECB:DRPMI NID/DR~1X, I11NAME EFGoodwin* RKiessel* elDATE 05/15/95 1 3909/14/95 09 95UtiilLIAL K-IUKU WURY IN 95-xxSeptember xx, 995Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contact: John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME:S:\DRPM SEC\CHR91438*See previous concurrence-a_ An Ad_ try -.--- -ta~ rh otonlIF' .Cnnv with atnchmentlenclosure *N' -No copyTo receive a copy 0? this cocunwnt, Indicate mn Xn. o:A; -s°Pqt wnn u--a........ o ---- -. -OFFICE TERB:DOTS IC ADM:[PUB NOECB:DOPS I E SC/TERB:DOTSI E IC/TRB:DOTSENAME JJHayes* Tech Ed/MMejac* RABenedict* RLEmch*DATE 05/02/95 105/10/95 105/02/95 05/02/95_ 05/02/9--.---r-I -I .I &Ii M fr~ .nnLAnFFT(F ISC/OECB!DOPSIN IPECH: URPMI t IL/ tLt1:UKrMI1 IU UKNrrI -11-- _, ___ .__.__ ..__ _ _ .__NAME EFGoodwin* I RKiessel* _AEChaffee* IDMCrutchfieldqIDATE 05/15/95 109/13/95 --9/1/95 099UOFICIIAL KLLUKU HUrY IN 95-xxSeptember xx, 1995 Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Dennis M. Crutchfield, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor Regulation
Technical Contact:
John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\IN\CHR91438*See previous concurrence-- .-rt S. *" 11. b_-f -t -fthrA
- ttsdtmfilfntjnfLd E = COnY with =tachmerd/en e^suu. a No copyre lculy.
- wpy. u.l ocuun.... -.w --IIOFFICE TERB:DOTS lC ADM:PUB IN OECB:DOPS E E SC/TERB:DOTSI E C/NAME JJHayes* Tech Ed/MMejac* RABenedict* RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 05/02/95 05/02/95.M. a.(FF FICSCIFECR:DOPSI N I PECB:DRPMI E I UPLUB; WPMIA/IUUKrfiI II I -I .-- .' -- 0 .... .... ... -,,, ...-NAME 1EFGoodwin* _RKiessel 42 AEChaffee _ DMCrutchfeld lDATE 105/15/95 109/J3 /95 1fj1 T 09/.5 /95 09/ /95^rIrY 0 TAiI nrffnn% n glfOFF lVlAL KcvuKu vuri IN 95-xxMay xx, 1995 Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor Regulation
Technical Contact:
John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\IN\CHR91438*See previous concurrenceTo receive a copy of this document, Indicate In the box: C" = Copy without attachmentlenclosure 'E' = Copy with attachment/enclosure ON' -No copyOFFICE TERB:DOTS C A M:PUB 1 N [OECB:DOPS E SC/TERB:DOTS lE C/TERB:DOTS K ENAME JJHayes* Tech Ed/MMejac* RABenedict* RLEmch* ICLMiller*DATE 05/02/95 05/10/95 105/02/95 105/02/95 05/02/95a AInFrTrr I SC/fECBRiOPSI N IOECB:DOPSI IM/utCu:VUVpI I uIuurP1 11-_ .--- -. -I- v .A _ .--NAME EFGoodwin* _ RKiessel IAEChaffee SUB BKGrimesDATE 05/15/95 05/ /95 05/ /95 105/ /95nrchIrTAI nrv'nnn fflV01-1-11,1AL KELUKU ,Ur 1 IN 95-xxMay xx, 1995 Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor Regulation
Technical Contact:
John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\IN\CHR91438*See previous concurrenceTo receive a copy of this document, Indicate In the box: ACT -Copy without attachmentlenclosure 'E'
- Copy with attachmentlenclosure SNH -No copyOFFICE TERB:DOTS IC ADM:PUB [ OECB:DOPS I E SC/TERB:DOTS I E C/TERB:DOTS I ENAME JJHayes* Tech Ed/MMejac* [RABenedict* IRLEmch* CLMiller*DATE 05/02/95 05/10/95 105/02/95 05/02/95 05/02/95IIOFFICE1SC/OECB:DOPSII C/OECB:DOPSID/DOPSI 1INAME EFGoodwin X 1AEChaffee % 5b I mKGriImesDATE 105/16E/9505/ /95 05/ /95OFFICIAL RECORD COPY
-0 '"?;4 -Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor RegulationA -...-
Technical Contact:
John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME:G:\IN\CHR91438*See previous concurrenceTo receive a copy of this document, Indicate In the box: "C' a Copy without attachmentenclosure "F = Copy with attachment/enclosure "N" -No copy-_ _ _ _ -_ .lOFFICE ITERB:DOTSICADM:PUBIOECB:DOPSI E ISC/TERB:DOTS I E IC/TER.B:DOTS I E 11NAME JJHayes* j ITech Ed 1 A!ndJRABenedict* IRLEmch* --_- CLMiller*DATE 105/02/95 105/1o /95 105/02/95 105/02/95 105/02/95A- -A _ A __OFFICE ISC/OECB:DOPSlC/OECB:DOPSID/DOPSI l1NAME EFGoodwin JAEChaffee BKGrimesDATE 05/ /95 105/ /95 05/ /95:.UIIILIAL KtLUKU COPY7,,, A; -..
K>~Exposure of charcoal to chemical compounds can result in a degradation of thecharcoal. With such degradation, in the event of an accident, the charcoalmay perform at an efficiency less than that assumed in the staff's safetyevaluation. Therefore, if licensees divert air flow through charcoal adsorbersin their ventilation systems during and/or following chemical cleaning, theymay find it appropriate to perform a laboratory test of the charcoal to ensurethat the charcoal has not degraded below its TS surveillance requirementslimit.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor Regulation
Technical Contact:
John J. Hayes, NRR(301) 415-3167
Attachments:
1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\IN\CHR91438To rSceive a copy of this document, Indcate In the box: 'C' Copy without attachmenUt/enclosure 'E' -Copy with attachment/enclosure 'N'
- No conpOFFICE T TECH ED l OECB 14F 1 SC:TERB ,,Jir-C:TERB/DOTS I ClNAME ayes RABeneaict,' RLEmch , CiMiller cog J llDATE OS/ V/95y V 05/ /95 05/oZ /95 05/2.? /95 05/ N-/95SC:OECB/DOPSI 1B:OECB/DOPSI ID:DOPSI 1EFGoodwin AEChaffee BKGrimes05/ /95 05/ /95 05/ /95J
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
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