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| {{#Wiki_filter:K9J(UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555-0001September 22, 1995NRC INFORMATION NOTICE 95-41: DEGRADATION OF VENTILATION SYSTEM CHARCOALRESULTING FROM CHEMICAL CLEANING OF STEAMGENERATORS | | {{#Wiki_filter:K9J(UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555-0001 September |
| | |
| | 22, 1995 NRC INFORMATION |
| | |
| | NOTICE 95-41: DEGRADATION |
| | |
| | OF VENTILATION |
| | |
| | SYSTEM CHARCOAL RESULTING |
| | |
| | ===FROM CHEMICAL CLEANING OF STEAM GENERATORS=== |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors. | | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors. |
|
| |
|
| ==Purpose== | | ==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. | | The U.S. Nuclear Regulatory |
| | |
| | Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to the potential |
| | |
| | degradation |
| | |
| | of ventilation |
| | |
| | system charcoal as a result of the charcoal's |
| | |
| | exposure to chemicals |
| | |
| | during the chemical cleaning of steam generators. |
| | |
| | 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 |
| | |
| | On June 5, 1994, a chemical cleaning of the secondary |
| | |
| | sides of the steam generators |
| | |
| | at Surry Unit 2 was begun. During this cleaning, containment |
| | |
| | purge was established |
| | |
| | using train A of the auxiliary |
| | |
| | ventilation |
| | |
| | system, which contains a safety-grade |
| | |
| | charcoal adsorber. |
| | |
| | The chemical cleaning process involves the--use of ethylene diamine tetraacetic |
| | |
| | acid (EDTA) as the cleaning agent and of various other chemicals |
| | |
| | such as ethylenediamine (EDA), hydrazine, ammonia, hydrogen peroxide, nitrogen, and CCl-801, a proprietary |
| | |
| | corrosion inhibitor. |
| | |
| | During the chemical cleaning the steam generators |
| | |
| | were isolated from the containment |
| | |
| | atmosphere |
| | |
| | and force-vented |
| | |
| | to the outdoor atmosphere |
| | |
| | through the atmospheric |
| | |
| | steam dump relief valves. The steam generators |
| | |
| | were rinsed to remove residual chemicals. |
| | |
| | ===After the rinse, the steam generators=== |
| | were opened for sludge lancing of the tube sheet region.On June 16, 1994, a strong odor of ammonia was reported in the Unit 2 containment. |
| | |
| | Concentrations |
| | |
| | were measured at 30 ppm (parts per million)ammonia and 6 ppm hydrazine. |
| | |
| | Consequently, personnel |
| | |
| | were evacuated |
| | |
| | from the containment. |
| | |
| | At the time of the evacuation, the chemical cleaning and rinse had been completed |
| | |
| | on steam generators |
| | |
| | A and C and the steam generators |
| | |
| | were vented to the containment. |
| | |
| | Because of the elevated levels of hydrazine |
| | |
| | and ammonia in the containment, train B of the auxiliary |
| | |
| | ventilation |
| | |
| | system was started to assist train A in reducing the airborne concentrations. |
| | |
| | Both trains operated approximately |
| | |
| | 8 hours until chemical concentrations |
| | |
| | in the containment |
| | |
| | were reduced.950918034 t~q~gut II @ |
| | IN 95-41 September |
| | |
| | 22, 1995 -As a result of the exposure of the charcoal to the chemicals, in accordance |
| | |
| | with the technical |
| | |
| | specifications (TS), a sample of train A charcoal was taken and a laboratory |
| | |
| | test of a sample of the sample was performed. |
| | |
| | The results of the laboratory |
| | |
| | test showed a methyl iodide removal efficiency |
| | |
| | of 93.4 percent, which was below the TS limit. The charcoal was replaced. |
| | |
| | A sample from train B was tested and the results of the laboratory |
| | |
| | test of that sample showed a methyl iodide removal efficiency |
| | |
| | of 90.7 percent. This value was also 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 the charcoal was determined |
| | |
| | to have failed, train A had operated for 657 hours, while the train B had operated for 360 hours. In addition, the licensee had held discussions |
| | |
| | with the charcoal supplier during which the supplier had indicated |
| | |
| | that exposure of the charcoal to hydrazine |
| | |
| | and ammonia in the above noted concentrations |
| | |
| | should not have resulted in its degradation. |
| | |
| | As a result of the experience |
| | |
| | at Unit 2, when the steam generators |
| | |
| | at Unit 1 were chemically |
| | |
| | cleaned, the licensee arranged for the containment |
| | |
| | flow to be diverted to a non-safety-grade |
| | |
| | system containing |
| | |
| | charcoal. |
| | |
| | When the licensee completed |
| | |
| | the cleaning operation, laboratory |
| | |
| | testing of the charcoal in the non-safety-grade |
| | |
| | system showed that the adsorber efficiency |
| | |
| | was 3.3 percent less than its efficiency |
| | |
| | before the chemical cleaning. |
| | |
| | On the basis of these two experiences, the licensee concluded |
| | |
| | that discharging |
| | |
| | the air involved in steam generator |
| | |
| | cleaning operations |
| | |
| | through systems containing |
| | |
| | charcoal was likely 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 per minute [80 feet per minute]. The laboratory |
| | |
| | tests were conducted |
| | |
| | using the 1979 version of American Society for Testing and Materials (ASTM) D3803, Standard Test Method for Nuclear-Grade |
| | |
| | Activated |
| | |
| | Carbon.' The licensee did not attempt to determine |
| | |
| | the chemical compound responsible |
| | |
| | for the degradation |
| | |
| | of the charcoal. |
| | |
| | However, it and its charcoal supplier believe that the probable culprits were EDA and EDTA.The NRC staff held telephone |
| | |
| | conversations |
| | |
| | with charcoal suppliers |
| | |
| | and testing laboratory |
| | |
| | representatives. |
| | |
| | Based upon these conversations, the parties concluded |
| | |
| | that, although the ammonia did not contribute |
| | |
| | to the degradation |
| | |
| | of the charcoal, the breakdown |
| | |
| | of hydrazine |
| | |
| | in the charcoal may have contributed |
| | |
| | additional |
| | |
| | moisture to the charcoal resulting |
| | |
| | in its degradation. |
| | |
| | These discussions |
| | |
| | also confirmed |
| | |
| | that both EDA and EDTA could degrade the charcoal. |
| | |
| | The staff also noted that, had the licensee performed the laboratory |
| | |
| | tests in accordance |
| | |
| | with the guidance in NRC Information |
| | |
| | Notice 87-32, "Deficiencies |
| | |
| | in the Testing of Nuclear-Grade |
| | |
| | Activated |
| | |
| | Charcoal," (Accession |
| | |
| | No. 8707070003) |
| | or in accordance |
| | |
| | with the 1989 version of ASTM D3803, the measured degradation |
| | |
| | of the charcoal would have been greater than that identified |
| | |
| | by the licensee. |
| | |
| | K..- V IN 95-41 September |
| | |
| | 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 perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers |
| | |
| | in their ventilation |
| | |
| | systems during and/or after chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.'nn .1%ic I Division of Reactor Pr ram Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices A4e UQ FJLa |
| | |
| | ~1 <-J Attachment |
| | |
| | 1 IN 95-41 September |
| | |
| | 22, 1995 Referenced |
| | |
| | Codes and Standards American Society for Testing and Materials, ASTM D3803, "Standard |
| | |
| | Test Method for Nuclear-Grade |
| | |
| | Activated |
| | |
| | Carbon,' Philadelphia, Pennsylvania. |
| | |
| | wXvachment |
| | |
| | 2 IN 95-41 September |
| | |
| | 22, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 95-40 95-39 95-38 95-37 Supplemental |
| | |
| | Information |
| | |
| | to Generic Letter 95-03,"Circumferential |
| | |
| | Cracking of Steam Generator |
| | |
| | Tubes" Brachytherapy |
| | |
| | Incidents Involving |
| | |
| | Treatment Planning Errors Degradation |
| | |
| | of Boraflex Neutron Absorber in Spent Fuel Storage Racks Inadequate |
| | |
| | Offsite Power System Voltages during Design-Basis |
| | |
| | Events 09/20/95 09/19/95 09/08/95 09/07/95 All holders of OLs or CPs for nuclear power reactors.All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | Medical Licensees. |
| | |
| | All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.95-36 Potential Post-Fire Lighting Problems with Emergency 08/29/95 All holders of OLs or CPs for nuclear power reactors.95-35 95-34 93-83, Supp. 1 95-33 Degraded Ability of Steam Generators |
| | |
| | to Remove Decay Heat by Natural Circulation |
| | |
| | Air Actuator and Supply Air Regulator |
| | |
| | Problems in Copes-Vulcan |
| | |
| | Pressurizer |
| | |
| | Power-Operated |
| | |
| | Relief Valves Potential |
| | |
| | Loss of Spent Fuel Pool Cooling After a Loss-of-Coolant |
| | |
| | Accident or a Loss of Offsite Power Switchgear |
| | |
| | Fire and Partial Loss of Offsite Power at Waterford Generating |
| | |
| | Station, Unit 3 08/28/95 08/25/95 08/24/95 08/23/95 All holders of OLs or CPs for pressurized |
| | |
| | water reactors (PWRs).All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.I OL -Operating |
| | |
| | License CP = Construction |
| | |
| | Permit |
| | |
| | K>IN 95-41 September |
| | |
| | 22, 1995 Exposure of charcoal to chemical compounds |
| | |
| | can result in a degradation |
| | |
| | of the charcoal. |
| | |
| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers in their ventilation |
| | |
| | systems during and/or following |
| | |
| | chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by DMCrutchfield |
| | |
| | Dennis M. Crutchfield, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: 95-41.IN*See previous concurrence |
| | |
| | To receive a copy of this document, indicate In the box: C' = Copy without attachment/enclosure |
| | |
| | 'E' = Copy with attachmentlenclosure |
| | |
| | 'N' -No copy OFFICE TERB:DOTS |
| | |
| | IC ADM:PUB IN OECB:DOPS |
| | |
| | I E SC/TERB:DOTS |
| | |
| | E C/TERB:DOTS |
| | |
| | LE NAME JJHayes* Tech Ed/MMejac* |
| | RABenedict* |
| | RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 105/02/ 95 05/02/95.....-.I OFFICE 1SC/OECB:DOPS |
| | |
| | IN IPECB:DRPM |
| | |
| | I E IC/PECB:DRPM |
| | |
| | I NID/DR~1X, I 11 NAME EFGoodwin* |
| | RKiessel* |
| | el DATE 05/15/95 1 3909/14/95 |
| | 09 95 UtiilLIAL |
| | |
| | K-IUKU WURY |
| | |
| | IN 95-xx September |
| | |
| | xx, 1995 Exposure of charcoal to chemical compounds |
| | |
| | can result in a degradation |
| | |
| | of the charcoal. |
| | |
| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers in their ventilation |
| | |
| | systems during and/or following |
| | |
| | chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: S:\DRPM SEC\CHR91438 |
| | *See previous concurrence |
| | |
| | -a_ An Ad_ try -.--- -ta~ rh otonl IF' .Cnnv with atnchmentlenclosure |
| | |
| | *N' -No copy T o 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:DOTSE |
| | |
| | NAME 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~ .nnLA nFFT(F ISC/OECB!DOPS |
| | |
| | IN IPECH: URPM I t IL/ tLt1:UKrM I1 IU UKNrr I -11-- _, ___ .__.__ ..__ _ _ .__NAME EFGoodwin* |
| | I RKiessel* |
| | _AEChaffee* |
| | |
| | ===IDMCrutchfieldqI=== |
| | DATE 05/15/95 109/13/95 |
| | --9/1/95 099 UOFICIIAL |
| | |
| | KLLUKU HUrY |
| | |
| | IN 95-xx September |
| | |
| | xx, 1995 Exposure of charcoal to chemical compounds |
| | |
| | can result in a degradation |
| | |
| | of the charcoal. |
| | |
| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers in their ventilation |
| | |
| | systems during and/or following |
| | |
| | chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | Contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:\IN\CHR91438 |
| | *See previous concurrence |
| | |
| | -- .-rt S. *" 11. b_-f -t -fthrA |
| | |
| | * ttsdtmfilfntjnfLd |
| | |
| | E = COnY with =tachmerd/en |
| | |
| | e^suu. '' a No copy re lculy. |
| | |
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| | |
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| | |
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| | |
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| | |
| | 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 FIC SCIFECR:DOPS |
| | |
| | I N I PECB:DRPM I E I UPLUB; WPM IA/IUUKrfi |
| | |
| | I I I 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 glf OFF lVlAL KcvuKu vuri |
| | |
| | IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds |
| | |
| | can result in a degradation |
| | |
| | of the charcoal. |
| | |
| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers in their ventilation |
| | |
| | systems during and/or following |
| | |
| | chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | Contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:\IN\CHR91438 |
| | *See previous concurrence |
| | |
| | To receive a copy of this document, Indicate In the box: C" = Copy without attachmentlenclosure |
| | |
| | 'E' = Copy with attachment/enclosure |
| | |
| | ON' -No copy OFFICE TERB:DOTS |
| | |
| | C A M:PUB 1 N [OECB:DOPS |
| | |
| | E SC/TERB:DOTS |
| | |
| | lE C/TERB:DOTS |
| | |
| | K E NAME JJHayes* Tech Ed/MMejac* |
| | RABenedict* |
| | RLEmch* ICLMiller* |
| | DATE 05/02/95 05/10/95 105/02/95 |
| | 105/02/95 |
| | 05/02/95 a AI nFrTrr I SC/fECBRiOPS |
| | |
| | I N IOECB:DOPS |
| | |
| | I IM/utCu:VUVp |
| | |
| | I I uIuurP 1 11-_ .--- -. -I- v .A _ .--NAME EFGoodwin* |
| | _ RKiessel IAEChaffee |
| | |
| | SUB BKGrimes DATE 05/15/95 05/ /95 05/ /95 105/ /95 nrchIrTAI |
| | |
| | nrv'nnn fflV 01-1-11,1AL |
| | |
| | KELUKU ,Ur 1 IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds |
| | |
| | can result in a degradation |
| | |
| | of the charcoal. |
| | |
| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
| | |
| | less than that assumed in the staff's safety evaluation. |
| | |
| | Therefore, if licensees |
| | |
| | divert air flow through charcoal adsorbers in their ventilation |
| | |
| | systems during and/or following |
| | |
| | chemical cleaning, they may find it appropriate |
| | |
| | to perform a laboratory |
| | |
| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
| | |
| | requirements |
| | |
| | limit.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact the technical |
| | |
| | contact listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | Contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:\IN\CHR91438 |
| | *See previous concurrence |
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| | To receive a copy of this document, Indicate In the box: ACT -Copy without attachmentlenclosure |
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| | 'E' |
| | * Copy with attachmentlenclosure |
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| | SNH -No copy OFFICE TERB:DOTS |
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| | IC ADM:PUB [ OECB:DOPS |
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| | I E SC/TERB:DOTS |
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| | I E C/TERB:DOTS |
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| | I E NAME JJHayes* Tech Ed/MMejac* |
| | [RABenedict* |
| | IRLEmch* CLMiller*DATE 05/02/95 05/10/95 105/02/95 |
| | 05/02/95 05/02/95 IIOFFICE 1SC/OECB:DOPS |
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| | I I C/OECB:DOPS |
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| | I D/DOPS I 1I NAME EFGoodwin |
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| | X 1AEChaffee |
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| | % 5b I mKGriImes DATE 105/16E/9505/ |
| | /95 05/ /95 OFFICIAL RECORD COPY |
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| | -0 '"?;4 -Exposure of charcoal to chemical compounds |
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| | can result in a degradation |
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| | of the charcoal. |
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| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
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| | less than that assumed in the staff's safety evaluation. |
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| | Therefore, if licensees |
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| | divert air flow through charcoal adsorbers in their ventilation |
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| | systems during and/or following |
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| | chemical cleaning, they may find it appropriate |
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| | to perform a laboratory |
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| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
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| | requirements |
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| | limit.This information |
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| | notice requires no specific action or written response. |
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| | If you have any questions |
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| | about the information |
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| | in this notice, please contact the technical |
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| | contact listed below or the appropriate |
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| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation |
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| | A -...- |
| | Technical |
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| | Contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
| | |
| | Codes and Standards 2. List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:\IN\CHR91438 |
| | *See previous concurrence |
| | |
| | To receive a copy of this document, Indicate In the box: "C' a Copy without attachmentenclosure "F = Copy with attachment/enclosure "N" -No copy-_ _ _ _ -_ .l OFFICE ITERB:DOTS |
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| | IC ADM:PUB I OECB:DOPS I E ISC/TERB:DOTS |
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| | I E IC/TER.B:DOTS |
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| | I E 11 NAME JJHayes* j ITech Ed 1 A!ndJRABenedict* |
| | IRLEmch* --_- CLMiller*DATE 105/02/95 |
| | 105/1o /95 105/02/95 |
| | 105/02/95 |
| | 105/02/95 A- -A _ A __OFFICE ISC/OECB:DOPS |
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| | l C/OECB:DOPS |
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| | I D/DOPS I l1 NAME EFGoodwin |
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| | JAEChaffee |
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| | BKGrimes DATE 05/ /95 105/ /95 05/ /95:.UIIILIAL KtLUKU COPY 7,,, A; -.. |
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| | K>~Exposure of charcoal to chemical compounds |
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| | can result in a degradation |
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| | of the charcoal. |
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| | With such degradation, in the event of an accident, the charcoal may perform at an efficiency |
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| | less than that assumed in the staff's safety evaluation. |
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| | Therefore, if licensees |
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| | divert air flow through charcoal adsorbers in their ventilation |
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| | systems during and/or following |
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| | chemical cleaning, they may find it appropriate |
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| | to perform a laboratory |
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| | test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance |
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| | requirements |
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| | limit.This information |
| | |
| | notice requires no specific action or written response. |
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| ==Description of Circumstances==
| | If you have any questions |
| 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 hours until chemical concentrations in thecontainment were reduced.950918034t~q~gut II @
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| 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 hours,while the train B had operated for 360 hours. 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 licensee.
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| 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) 415-3167Attachments:1. Referenced Codes and Standards2. List of Recently Issued NRC Information NoticesA4e UQ FJLa
| | about the information |
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| ~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, Pennsylvania.
| | in this notice, please contact the technical |
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| 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
| | contact listed below or the appropriate |
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| 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) 415-3167Attachments: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
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation |
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| 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) 415-3167Attachments: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
| | Technical |
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| 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
| | Contact: John J. Hayes, NRR (301) 415-3167 Attachments: |
| | 1. Referenced |
|
| |
|
| ===Technical Contact:===
| | Codes and Standards 2. List of Recently Issued NRC Information |
| John J. Hayes, NRR(301) 415-3167Attachments: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
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| * ttsdtmfilfntjnfLd E = COnY with =tachmerd/en e^suu. '' a No copyre lculy.
| | Notices DOCUMENT NAME: G:\IN\CHR91438 To rSceive a copy of this document, Indcate In the box: 'C' Copy without attachmenUt/enclosure |
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| * 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
| | 'E' -Copy with attachment/enclosure |
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| 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
| | 'N' |
| | * No conp OFFICE T TECH ED l OECB 14F 1 SC:TERB ,,Jir-C:TERB/DOTS |
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| ===Technical Contact:===
| | I Cl NAME ayes RABeneaict,' |
| John J. Hayes, NRR(301) 415-3167Attachments: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
| | RLEmch , CiMiller cog J llDATE OS/ V/95y V 05/ /95 05/oZ /95 05/2.? /95 05/ N-/95 SC:OECB/DOPS |
| -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 -...-
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| ===Technical Contact:===
| | I 1B:OECB/DOPS |
| John J. Hayes, NRR(301) 415-3167Attachments: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; -..
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| 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
| | I ID:DOPS I 1 EFGoodwin |
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| ===Technical Contact:===
| | AEChaffee |
| John J. Hayes, NRR(301) 415-3167Attachments: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'
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| * 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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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
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 |
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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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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>. |
K9J(UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 September
22, 1995 NRC INFORMATION
NOTICE 95-41: DEGRADATION
OF VENTILATION
SYSTEM CHARCOAL RESULTING
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to the potential
degradation
of ventilation
system charcoal as a result of the charcoal's
exposure to chemicals
during the chemical cleaning of steam generators.
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
On June 5, 1994, a chemical cleaning of the secondary
sides of the steam generators
at Surry Unit 2 was begun. During this cleaning, containment
purge was established
using train A of the auxiliary
ventilation
system, which contains a safety-grade
charcoal adsorber.
The chemical cleaning process involves the--use of ethylene diamine tetraacetic
acid (EDTA) as the cleaning agent and of various other chemicals
such as ethylenediamine (EDA), hydrazine, ammonia, hydrogen peroxide, nitrogen, and CCl-801, a proprietary
corrosion inhibitor.
During the chemical cleaning the steam generators
were isolated from the containment
atmosphere
and force-vented
to the outdoor atmosphere
through the atmospheric
steam dump relief valves. The steam generators
were rinsed to remove residual chemicals.
were opened for sludge lancing of the tube sheet region.On June 16, 1994, a strong odor of ammonia was reported in the Unit 2 containment.
Concentrations
were measured at 30 ppm (parts per million)ammonia and 6 ppm hydrazine.
Consequently, personnel
were evacuated
from the containment.
At the time of the evacuation, the chemical cleaning and rinse had been completed
on steam generators
A and C and the steam generators
were vented to the containment.
Because of the elevated levels of hydrazine
and ammonia in the containment, train B of the auxiliary
ventilation
system was started to assist train A in reducing the airborne concentrations.
Both trains 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 the containment
were reduced.950918034 t~q~gut II @
IN 95-41 September
22, 1995 -As a result of the exposure of the charcoal to the chemicals, in accordance
with the technical
specifications (TS), a sample of train A charcoal was taken and a laboratory
test of a sample of the sample was performed.
The results of the laboratory
test showed a methyl iodide removal efficiency
of 93.4 percent, which was below the TS limit. The charcoal was replaced.
A sample from train B was tested and the results of the laboratory
test of that sample showed a methyl iodide removal efficiency
of 90.7 percent. This value was also 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 the charcoal 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 had held discussions
with the charcoal supplier during which the supplier had indicated
that exposure of the charcoal to hydrazine
and ammonia in the above noted concentrations
should not have resulted in its degradation.
As a result of the experience
at Unit 2, when the steam generators
at Unit 1 were chemically
cleaned, the licensee arranged for the containment
flow to be diverted to a non-safety-grade
system containing
charcoal.
When the licensee completed
the cleaning operation, laboratory
testing of the charcoal in the non-safety-grade
system showed that the adsorber efficiency
was 3.3 percent less than its efficiency
before the chemical cleaning.
On the basis of these two experiences, the licensee concluded
that discharging
the air involved in steam generator
cleaning operations
through systems containing
charcoal was likely 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 per minute [80 feet per minute]. The laboratory
tests were conducted
using the 1979 version of American Society for Testing and Materials (ASTM) D3803, Standard Test Method for Nuclear-Grade
Activated
Carbon.' The licensee did not attempt to determine
the chemical compound responsible
for the degradation
of the charcoal.
However, it and its charcoal supplier believe that the probable culprits were EDA and EDTA.The NRC staff held telephone
conversations
with charcoal suppliers
and testing laboratory
representatives.
Based upon these conversations, the parties concluded
that, although the ammonia did not contribute
to the degradation
of the charcoal, the breakdown
of hydrazine
in the charcoal may have contributed
additional
moisture to the charcoal resulting
in its degradation.
These discussions
also confirmed
that both EDA and EDTA could degrade the charcoal.
The staff also noted that, had the licensee performed the laboratory
tests in accordance
with the guidance in NRC Information
Notice 87-32, "Deficiencies
in the Testing of Nuclear-Grade
Activated
Charcoal," (Accession
No. 8707070003)
or in accordance
with the 1989 version of ASTM D3803, the measured degradation
of the charcoal would have been greater than that identified
by the licensee.
K..- V IN 95-41 September
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 perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers
in their ventilation
systems during and/or after chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.'nn .1%ic I Division of Reactor Pr ram Management
Office of Nuclear Reactor Regulation
Technical
contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices A4e UQ FJLa
~1 <-J Attachment
1 IN 95-41 September
22, 1995 Referenced
Codes and Standards American Society for Testing and Materials, ASTM D3803, "Standard
Test Method for Nuclear-Grade
Activated
Carbon,' Philadelphia, Pennsylvania.
wXvachment
2 IN 95-41 September
22, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-40 95-39 95-38 95-37 Supplemental
Information
to Generic Letter 95-03,"Circumferential
Cracking of Steam Generator
Tubes" Brachytherapy
Incidents Involving
Treatment Planning Errors Degradation
of Boraflex Neutron Absorber in Spent Fuel Storage Racks Inadequate
Offsite Power System Voltages during Design-Basis
Events 09/20/95 09/19/95 09/08/95 09/07/95 All holders of OLs or CPs for nuclear power reactors.All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.95-36 Potential Post-Fire Lighting Problems with Emergency 08/29/95 All holders of OLs or CPs for nuclear power reactors.95-35 95-34 93-83, Supp. 1 95-33 Degraded Ability of Steam Generators
to Remove Decay Heat by Natural Circulation
Air Actuator and Supply Air Regulator
Problems in Copes-Vulcan
Pressurizer
Power-Operated
Relief Valves Potential
Loss of Spent Fuel Pool Cooling After a Loss-of-Coolant
Accident or a Loss of Offsite Power Switchgear
Fire and Partial Loss of Offsite Power at Waterford Generating
Station, Unit 3 08/28/95 08/25/95 08/24/95 08/23/95 All holders of OLs or CPs for pressurized
water reactors (PWRs).All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.I OL -Operating
License CP = Construction
Permit
K>IN 95-41 September
22, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by DMCrutchfield
Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: 95-41.IN*See previous concurrence
To receive a copy of this document, indicate In the box: C' = Copy without attachment/enclosure
'E' = Copy with attachmentlenclosure
'N' -No copy OFFICE TERB:DOTS
IC ADM:PUB IN OECB:DOPS
I E SC/TERB:DOTS
E C/TERB:DOTS
LE NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 105/02/ 95 05/02/95.....-.I OFFICE 1SC/OECB:DOPS
IN IPECB:DRPM
I E IC/PECB:DRPM
I NID/DR~1X, I 11 NAME EFGoodwin*
RKiessel*
el DATE 05/15/95 1 3909/14/95
09 95 UtiilLIAL
K-IUKU WURY
IN 95-xx September
xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: S:\DRPM SEC\CHR91438
-a_ An Ad_ try -.--- -ta~ rh otonl IF' .Cnnv with atnchmentlenclosure
- N' -No copy T o 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:DOTSE
NAME 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~ .nnLA nFFT(F ISC/OECB!DOPS
IN IPECH: URPM I t IL/ tLt1:UKrM I1 IU UKNrr I -11-- _, ___ .__.__ ..__ _ _ .__NAME EFGoodwin*
I RKiessel*
_AEChaffee*
IDMCrutchfieldqI
DATE 05/15/95 109/13/95
--9/1/95 099 UOFICIIAL
KLLUKU HUrY
IN 95-xx September
xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
-- .-rt S. *" 11. b_-f -t -fthrA
E = COnY with =tachmerd/en
e^suu. a No copy re lculy.
-.w --I I OFFICE 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 FIC SCIFECR:DOPS
I N I PECB:DRPM I E I UPLUB; WPM IA/IUUKrfi
I I I 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 glf OFF lVlAL KcvuKu vuri
IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: C" = Copy without attachmentlenclosure
'E' = Copy with attachment/enclosure
ON' -No copy OFFICE TERB:DOTS
C A M:PUB 1 N [OECB:DOPS
E SC/TERB:DOTS
lE C/TERB:DOTS
K E NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch* ICLMiller*
DATE 05/02/95 05/10/95 105/02/95
105/02/95
05/02/95 a AI nFrTrr I SC/fECBRiOPS
I N IOECB:DOPS
I IM/utCu:VUVp
I I uIuurP 1 11-_ .--- -. -I- v .A _ .--NAME EFGoodwin*
_ RKiessel IAEChaffee
SUB BKGrimes DATE 05/15/95 05/ /95 05/ /95 105/ /95 nrchIrTAI
nrv'nnn fflV 01-1-11,1AL
KELUKU ,Ur 1 IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: ACT -Copy without attachmentlenclosure
'E'
- Copy with attachmentlenclosure
SNH -No copy OFFICE TERB:DOTS
IC ADM:PUB [ OECB:DOPS
I E SC/TERB:DOTS
I E C/TERB:DOTS
I E NAME JJHayes* Tech Ed/MMejac*
[RABenedict*
IRLEmch* CLMiller*DATE 05/02/95 05/10/95 105/02/95
05/02/95 05/02/95 IIOFFICE 1SC/OECB:DOPS
I I C/OECB:DOPS
I D/DOPS I 1I NAME EFGoodwin
X 1AEChaffee
% 5b I mKGriImes DATE 105/16E/9505/
/95 05/ /95 OFFICIAL RECORD COPY
-0 '"?;4 -Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
A -...-
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: "C' a Copy without attachmentenclosure "F = Copy with attachment/enclosure "N" -No copy-_ _ _ _ -_ .l OFFICE ITERB:DOTS
IC ADM:PUB I OECB:DOPS I E ISC/TERB:DOTS
I E IC/TER.B:DOTS
I E 11 NAME JJHayes* j ITech Ed 1 A!ndJRABenedict*
IRLEmch* --_- CLMiller*DATE 105/02/95
105/1o /95 105/02/95
105/02/95
105/02/95 A- -A _ A __OFFICE ISC/OECB:DOPS
l C/OECB:DOPS
I D/DOPS I l1 NAME EFGoodwin
JAEChaffee
BKGrimes DATE 05/ /95 105/ /95 05/ /95:.UIIILIAL KtLUKU COPY 7,,, A; -..
K>~Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact the technical
contact listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438 To rSceive a copy of this document, Indcate In the box: 'C' Copy without attachmenUt/enclosure
'E' -Copy with attachment/enclosure
'N'
- No conp OFFICE T TECH ED l OECB 14F 1 SC:TERB ,,Jir-C:TERB/DOTS
I Cl NAME ayes RABeneaict,'
RLEmch , CiMiller cog J llDATE OS/ V/95y V 05/ /95 05/oZ /95 05/2.? /95 05/ N-/95 SC:OECB/DOPS
I 1B:OECB/DOPS
I ID:DOPS I 1 EFGoodwin
AEChaffee
BKGrimes 05/ /95 05/ /95 05/ /95 J
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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)
... further results |
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