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| {{#Wiki_filter:IUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555November 23, 1994NRC INFORMATION NOTICE 94-79:MICROBIOLOGICALLY INFLUENCED CORROSION OFEMERGENCY DIESEL GENERATOR SERVICE WATER PIPING | | {{#Wiki_filter:I UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555 November 23, 1994 NRC INFORMATION |
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| | NOTICE 94-79: MICROBIOLOGICALLY |
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| | INFLUENCED |
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| | CORROSION |
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| | OF EMERGENCY |
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| | DIESEL GENERATOR |
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| | SERVICE WATER PIPING |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors.PurDoseThe U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to degradation resulting from microbiologicallyinfluenced corrosion in carbon steel piping systems that supply service waterto emergency diesel generators. It is expected that recipients will reviewthe information for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specificaction or written response is required. | | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors.PurDose The U.S. Nuclear Regulatory |
| | |
| | Commission (NRC) is issuing this information |
| | |
| | notice to alert addressees |
| | |
| | to degradation |
| | |
| | resulting |
| | |
| | from microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | in carbon steel piping systems that supply service water to emergency |
| | |
| | diesel 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 |
| | |
| | Haddam Neck Plant On February 12, 1994, a through-wall |
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| | leak developed |
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| | in the service water system supply piping to the "A" emergency |
| | |
| | diesel generator. |
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| | The leak occurred in a weld in an area of low flow, where the licensee was doing light surface grinding to prepare for ultrasonic |
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| | test (UT) inspection. |
| | |
| | Previously, in March 1993, the licensee had found a similar leak associated |
| | |
| | with the "B" emergency diesel generator. |
| | |
| | After removing the leaking section and examining |
| | |
| | the pipe, the licensee determined |
| | |
| | that the leak was caused by poor initial weld quality and microbiologically |
| | |
| | influenced |
| | |
| | corrosion. |
| | |
| | Lack of penetration |
| | |
| | of some welds created a crevice condition. |
| | |
| | Radiographic |
| | |
| | tests (RT) of additional |
| | |
| | emergency diesel generator |
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| | service water system piping revealed three additional |
| | |
| | welds that could form similar leaks. It was during preparation |
| | |
| | of one of these welds for UT examination |
| | |
| | that the through-wall |
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| | leak associated |
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| | with the "A" emergency |
| | |
| | diesel generator |
| | |
| | was found.The licensee had previously |
| | |
| | performed |
| | |
| | a structural |
| | |
| | integrity |
| | |
| | determination |
| | |
| | in 1993 by radiography. |
| | |
| | Though based on a uniform wall loss instead of a sharp ,disruption, the licensee had at that time concluded |
| | |
| | that the worst-case |
| | |
| | degraded cross-section |
| | |
| | of the as-found pipe welds, located in the unisolable |
| | |
| | portions of the emergency |
| | |
| | diesel generator |
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| | supply piping, met the Generic Letter 90-05 acceptance |
| | |
| | criteria for structural |
| | |
| | integrity |
| | |
| | and that the degraded piping would have sufficient |
| | |
| | mechanical |
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| | and structural |
| | |
| | integrity |
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| | to remain operable. |
| | |
| | &_ r" .in '^*94170C 9411170039 towzl +2ji)K I TE NO-rice H#-14-u1 T4 lII /- |
| | IN 94-79 November 23, 1994 Beaver Valley Power Station. Unit I On May 6, 1994, the licensee found a through-wall |
| | |
| | leak (an 8 mm [5/16 inch]diameter hole) on the "Al train reactor plant river water system header to the emergency |
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| | diesel generators. |
| | |
| | The leak developed |
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| | on the below-grade |
| | |
| | portion of the 15-cm [6-inch] diameter A106 Grade B carbon steel piping. The licensee excavated |
| | |
| | the "A" and 'B" train headers, ultrasonically |
| | |
| | examined them using the "autoscan" area mapping technique, and found localized |
| | |
| | pitting to less than minimum required wall thickness |
| | |
| | in three additional |
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| | locations |
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| | along the"A" train piping. The pits were not clustered |
| | |
| | or closely spaced, but were located along the pipe length between the five and seven o'clock positions. |
| | |
| | For reference, the nominal pipe wall thickness |
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| | is 6.4 mm [0.25 inch] and minimum code wall thickness |
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| | is 1.5 mm [0.06 inch].The licensee evaluated |
| | |
| | the pitting in accordance |
| | |
| | with the American Society of Mechanical |
| | |
| | Engineers (ASME) Code of record. The basis for the localized thinning evaluation |
| | |
| | was conducted |
| | |
| | in accordance |
| | |
| | with industry guidance, EPRI NP-59IISP, "Acceptance |
| | |
| | Criteria for Structural |
| | |
| | Evaluation |
| | |
| | of Erosion-Corrosion |
| | |
| | Thinning in Carbon Steel Piping." This evaluation |
| | |
| | was reviewed by personnel in NRR and deemed as an acceptable |
| | |
| | conservative |
| | |
| | means of demonstrating |
| | |
| | ASME Code conformance. |
| | |
| | The licensee determined |
| | |
| | microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | to be the cause of the pitting and through-wall |
| | |
| | leak. The licensee removed a 0.61 m [24 inch] long section of piping to culture and characterize |
| | |
| | the microbial |
| | |
| | activity and perform additional |
| | |
| | ultrasonic |
| | |
| | testing.The general inside surface of the piping was moderately |
| | |
| | corroded, with localized |
| | |
| | pits and tubercles. |
| | |
| | Cultures from the pits contained |
| | |
| | sulfur-reducing bacteria and the anaerobic |
| | |
| | bacteria Clostridium. |
| | |
| | The tubercle formation |
| | |
| | was the result of the growth of the iron-oxidizing |
| | |
| | bacteria Gallionella. |
| | |
| | Ultrasonic |
| | |
| | examinations |
| | |
| | of a heat-affected |
| | |
| | zone indicated |
| | |
| | that the weld examined was not subject to preferential |
| | |
| | microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | attack.Discussion |
| | |
| | Stagnant or intermittent-flow |
| | |
| | conditions, as in the case of emergency |
| | |
| | diesel service water supply headers, are conducive |
| | |
| | to the growth of microorganisms |
| | |
| | that can accelerate |
| | |
| | corrosion |
| | |
| | rates. Service water supply lines to emergency diesel generators |
| | |
| | are stagnant because motor-operated |
| | |
| | isolation |
| | |
| | valves are normally maintained |
| | |
| | shut (except during monthly surveillance |
| | |
| | testing).Crevices such as those in piping welds that lack penetration |
| | |
| | can enhance microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | attack by giving a place for deposits and, therefore, for the bacteria to collect. Microbial |
| | |
| | films form when aerobic species, such as iron-oxidizing |
| | |
| | bacteria, create anaerobic |
| | |
| | conditions |
| | |
| | underneath |
| | |
| | them for microorganisms, such as sulfate-reducing |
| | |
| | bacteria, to accumulate |
| | |
| | at the metal surface. Sulfate-reducing |
| | |
| | bacteria attack the metal surface, produce corrosive |
| | |
| | chemicals, and cause deep pitting. |
| | |
| | K>J IN 94-79 November 23, 1994 Microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | on carbon steel will increase general corrosion, through-wall |
| | |
| | pitting, and the formation |
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| | of tubercles. |
| | |
| | Tubercles consist of corrosion |
| | |
| | products, microbes, and debris. Tubercle growth could restrict cooling water flow to equipment. |
| | |
| | Stainless |
| | |
| | steel piping is not immune to microbiologically |
| | |
| | influenced |
| | |
| | corrosion because microbes can attack at the weld heat affected zone (HAZ) in stainless steels when this zone becomes sensitized. |
| | |
| | Microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | can also damage metals lined with polymeric |
| | |
| | materials, typically |
| | |
| | at coating imperfections. |
| | |
| | Once microbial |
| | |
| | films are established |
| | |
| | on metal surfaces, they are extremely difficult |
| | |
| | to eliminate |
| | |
| | because of the resiliency |
| | |
| | of the individual |
| | |
| | microorganisms. |
| | |
| | Biocides are applied by some licensees |
| | |
| | in areas where continuous |
| | |
| | flow conditions |
| | |
| | cannot be maintained. |
| | |
| | ===However, biocide treatments=== |
| | are not always effective |
| | |
| | against established |
| | |
| | microorganism |
| | |
| | colonies because the biocide cannot penetrate |
| | |
| | through the tubercles |
| | |
| | or aerobic biofilms.Treatment |
| | |
| | against established |
| | |
| | colonies involves a combination |
| | |
| | of mechanical |
| | |
| | or chemical pipe cleaning, continued |
| | |
| | water treatment |
| | |
| | and regular maintenance. |
| | |
| | Continuous |
| | |
| | flow conditions |
| | |
| | have been found to prevent the attachment |
| | |
| | and growth of microbial |
| | |
| | films.It may be necessary |
| | |
| | to replace materials |
| | |
| | if microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | severely damages them or where mitigation |
| | |
| | measures cannot bring the system condition |
| | |
| | under control. Possible alternatives |
| | |
| | include replacing carbon steel with stainless |
| | |
| | steel or replacing |
| | |
| | stainless |
| | |
| | steel with more resistant |
| | |
| | materials, such as 6-percent |
| | |
| | molybdenum |
| | |
| | stainless |
| | |
| | steels, nickel base alloys, titanium, or nonmetallic |
| | |
| | materials. |
| | |
| | The licensee did not regularly |
| | |
| | treat the Beaver Valley River water supply lines to the diesel with biocide or corrosion |
| | |
| | inhibitors. |
| | |
| | ===The chlorination=== |
| | injection |
| | |
| | point for the main river water headers is downstream |
| | |
| | of the branch lines to the emergency |
| | |
| | diesel generators. |
| | |
| | It also appears that the existing program at Haddam Neck of hypochlorite |
| | |
| | injection |
| | |
| | was not successful |
| | |
| | in mitigating |
| | |
| | the microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | problems in stagnant dead-end lines at such locations |
| | |
| | as the emergency |
| | |
| | diesel generator |
| | |
| | supply. |
| | |
| | IN 94-79 November 23, 1994 This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Vv BaD D ision f Project Support Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contacts: |
| | Michael Modes, RI James A. Davis, NRR (215) 337-5198 (301) 504-2713 Peter P. Sena, RI Vern Hodge, NRR (412) 643-2000 (301) 504-1861 Attachment: |
| | List of Recently ssued NRC Information |
| | |
| | Notices hi It6 J'4 K>Attachment |
| | |
| | IN 94-79 November 23, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 94-78 94-77 94-76 93-60, Supp. 1 94-75 94-74 94-73 94-72 94-71 Electrical |
| | |
| | Component Failure due to Degrada-tion of Polyvinyl |
| | |
| | ===Chloride Wire Insulation=== |
| | Malfunction |
| | |
| | in Main Gen-erator Voltage Regulator Causing Overvoltage |
| | |
| | at Safety-Related |
| | |
| | Electrical |
| | |
| | Equipment Recent Failures of Charging/Safety Injection |
| | |
| | Pump Shafts Reporting |
| | |
| | Fuel Cycle and Materials |
| | |
| | Events to the NRC Operations |
| | |
| | ===Center Minimum Temperature=== |
| | for Criticality |
| | |
| | ===Facility Management=== |
| | Responsibilities |
| | |
| | for Purchased |
| | |
| | or Contracted |
| | |
| | Services for Radiation Therapy Programs Clarification |
| | |
| | of Critical-ity Reporting |
| | |
| | Criteria Increased |
| | |
| | Control Rod Drop Time from Crud Buildup Degradation |
| | |
| | of Scram Solenoid Pilot Valve Pressure and Exhaust Diaphragms |
| | |
| | 11/21/94 11/17/94 10/26/94 10/20/94 10/14/94 10/13/94 10/12/94 10/05/94 10/04/94 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 pressurized |
| | |
| | water reactors.All 10 CFR Part 70 fuel cycle licensees. |
| | |
| | All holders of OLs or CPs pressurized-water |
| | |
| | reactors (PWRs).All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | Medical Licensees. |
| | |
| | ===All fuel fabrication=== |
| | facilities. |
| | |
| | All holders of OLs or CPs for pressurized |
| | |
| | water reactors.All holders of OLs or CPs for boiling water reactors (BWRs).OL -Operating |
| | |
| | License CP = Construction |
| | |
| | Permit |
| | |
| | -1/4<> A~-' IN 94-79 November 23, 1994 The licensee did not regularly |
| | |
| | treat the Beaver Valley River water supply lines to the diesel with biocide or corrosion |
| | |
| | inhibitors. |
| | |
| | ===The chlorination=== |
| | injection |
| | |
| | point for the main river water headers is downstream |
| | |
| | of the branch lines to the emergency |
| | |
| | diesel generators. |
| | |
| | It also appears that the existing program at Haddam Neck of hypochlorite |
| | |
| | injection |
| | |
| | was not successful |
| | |
| | in mitigating |
| | |
| | the microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | problems in stagnant dead-end lines at such locations |
| | |
| | as the emergency |
| | |
| | diesel generator |
| | |
| | supply.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by B.D. Liaw for Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contacts: Michael Modes, (215) 337-5198 RI James A. Davis, NRR (301) 504-2713 Peter P. Sena, RI (412) 643-2000 Vern Hodge, NRR (301) 504-1861 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices*err DDrFlVT) rnCUriRFNrEN |
| | |
| | OFFICE *OGCB/DORS |
| | |
| | *TECH ED *REGION I *REGION I NAME CVHodge JDMain MCModes PPSena DATE J 09/08/94 09/09/94 09/01/94 10/03/94__ _ _ _ _ _ _ _ _ -EI I __ If_*Ann-nfEDrIOTAN |
| | |
| | T I |
| | |
| | * FMrR/nF*S:EMCB/DE |
| | |
| | *C: EMCB/DE , I vv.1,EI *vI __ , --ARBlough JADavis RAHermann |
| | |
| | ===JRStrosnider=== |
| | 10/03/94 09/20/94 09/20/94-~~~ II f*n. nr*nCrRR /nnP5 I *C AFCBIDOPS I D:DdPWi/Or |
| | |
| | v.LvL _. -BWSheron RLDennig AEChaffee |
| | |
| | G& I _J1 10/06/94 10/20/94 10/25/94 1 1 ff_/_ 4 Lj DOCUMENT NAME: 94-79.IN |
| | |
| | IN 94-XX October xx, 1994 inhibitors. |
| | |
| | The chlorination |
| | |
| | injection |
| | |
| | point for the main river water headers is downstream |
| | |
| | of the branch lines to the emergency diesel generators. |
| | |
| | It also appears that the existing program at Haddam Neck of hypochlorite |
| | |
| | injection |
| | |
| | was not successful |
| | |
| | in mitigating |
| | |
| | the microbiologically |
| | |
| | influenced |
| | |
| | corrosion |
| | |
| | problems in stagnant dead-end lines to such locations |
| | |
| | as the emergency |
| | |
| | diesel generator |
| | |
| | supply.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating |
| | |
| | ===Reactor Support Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: |
| | Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A.Davis, NRR (301) 504-2713 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices*SEE PREVIOUS CONCURRENCE |
| | |
| | OFFICE *OGCB/DORS |
| | |
| | *TECH ED *REGION I *REGION I NAME CVHodge JDMain MCModes PPSena DATE 09/08/94 j09/09/94 |
| | 09/01/94 10/03/94._ -11*Ann:DRA/RFCION |
| | |
| | I I *EMCB/DE I *S:EMCB/DE |
| | |
| | I *C:EMCB/DE |
| | |
| | ARBlough JADavis RAHermann |
| | |
| | ===JRStrosnider=== |
| | 10/03/94 09/20/94 09/20/94 09 94--I -I ~' -7 i*n FOEC 6I1QS I C:994A2'OPS |
| | |
| | I IWS/NRR BWSheron RLW A af e B j jes 10/06/94 10/9 1,/94 10/ /94 _________DOCUMENT NAME: NECK-MIC. |
| | |
| | INY |
| | |
| | -IN 94-XX September |
| | |
| | xx, 1994 stagnant dead-end lines to such locations |
| | |
| | as the emergency |
| | |
| | diesel generator |
| | |
| | supply.This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating |
| | |
| | ===Reactor Support Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A. Davis, NRR (301) 504-2713 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices.-- "tf A R'lena-*QVV DPRVUSTnT1 CONCURRENCE |
| | |
| | --.:L: -a V -__s_ ___ -r- -m --OFFICE *OGCB/DORS |
| | |
| | *TECH ED *REGION I REGION I A NAME CVHodge I JDMain MCModes PPSena DATE j09/08/94 |
| | 09/09/94 09/01/94 ff /o3/94_ I ., ._II annlnPq/RFnTON |
| | |
| | T*EMCB/DE*S: EMCB/DE C;EMCB/DE |
| | |
| | fir-_ I___ __a _ v_ --ARBlough JADavis RAHermann |
| | |
| | ===LdRStrosnider=== |
| | -___ /9 09/20/94 09/20/94 09/X6/94 1~.1 Dkbz AC:OGCB/DORS |
| | |
| | D:DORS/NRR |
| | |
| | BW on ELDoolittle |
| | |
| | BKGrimes__/__ /94 09/ /94 09/ /94 DOCUMgNT NAME: NECK-MIC.1fir |
| | |
| | A-- 016 I IN 94-XX September |
| | |
| | xx, 1994 This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating |
| | |
| | ===Reactor Support Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A. Davis, NRR (301) 504-2713 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices*SEE PREVIOUS CONCURRENCE |
| | |
| | --- eIml e .Ac>Iveiw |
|
| |
|
| ==Description of Circumstances==
| | 6 2 OFFICE OGCB/DORS |
| Haddam Neck PlantOn February 12, 1994, a through-wall leak developed in the service watersystem supply piping to the "A" emergency diesel generator. The leak occurredin a weld in an area of low flow, where the licensee was doing light surfacegrinding to prepare for ultrasonic test (UT) inspection. Previously, in March1993, the licensee had found a similar leak associated with the "B" emergencydiesel generator. After removing the leaking section and examining the pipe,the licensee determined that the leak was caused by poor initial weld qualityand microbiologically influenced corrosion. Lack of penetration of some weldscreated a crevice condition. Radiographic tests (RT) of additional emergencydiesel generator service water system piping revealed three additional weldsthat could form similar leaks. It was during preparation of one of thesewelds for UT examination that the through-wall leak associated with the "A"emergency diesel generator was found.The licensee had previously performed a structural integrity determination in1993 by radiography. Though based on a uniform wall loss instead of a sharp,disruption, the licensee had at that time concluded that the worst-casedegraded cross-section of the as-found pipe welds, located in the unisolableportions of the emergency diesel generator supply piping, met the GenericLetter 90-05 acceptance criteria for structural integrity and that thedegraded piping would have sufficient mechanical and structural integrity toremain operable. &_ r" .in '^*94170C9411170039towzl +2ji)K I TE NO-riceH#-14-u1T4 lII /-
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| IN 94-79November 23, 1994 Beaver Valley Power Station. Unit IOn May 6, 1994, the licensee found a through-wall leak (an 8 mm [5/16 inch]diameter hole) on the "Al train reactor plant river water system header to theemergency diesel generators. The leak developed on the below-grade portion ofthe 15-cm [6-inch] diameter A106 Grade B carbon steel piping. The licenseeexcavated the "A" and 'B" train headers, ultrasonically examined them usingthe "autoscan" area mapping technique, and found localized pitting to lessthan minimum required wall thickness in three additional locations along the"A" train piping. The pits were not clustered or closely spaced, but werelocated along the pipe length between the five and seven o'clock positions.For reference, the nominal pipe wall thickness is 6.4 mm [0.25 inch] andminimum code wall thickness is 1.5 mm [0.06 inch].The licensee evaluated the pitting in accordance with the American Society ofMechanical Engineers (ASME) Code of record. The basis for the localizedthinning evaluation was conducted in accordance with industry guidance, EPRINP-59IISP, "Acceptance Criteria for Structural Evaluation of Erosion-CorrosionThinning in Carbon Steel Piping." This evaluation was reviewed by personnelin NRR and deemed as an acceptable conservative means of demonstrating ASMECode conformance. The licensee determined microbiologically influencedcorrosion to be the cause of the pitting and through-wall leak. The licenseeremoved a 0.61 m [24 inch] long section of piping to culture and characterizethe microbial activity and perform additional ultrasonic testing.The general inside surface of the piping was moderately corroded, withlocalized pits and tubercles. Cultures from the pits contained sulfur-reducing bacteria and the anaerobic bacteria Clostridium. The tubercleformation was the result of the growth of the iron-oxidizing bacteriaGallionella. Ultrasonic examinations of a heat-affected zone indicated thatthe weld examined was not subject to preferential microbiologically influencedcorrosion attack.DiscussionStagnant or intermittent-flow conditions, as in the case of emergency dieselservice water supply headers, are conducive to the growth of microorganismsthat can accelerate corrosion rates. Service water supply lines to emergencydiesel generators are stagnant because motor-operated isolation valves arenormally maintained shut (except during monthly surveillance testing).Crevices such as those in piping welds that lack penetration can enhancemicrobiologically influenced corrosion attack by giving a place for depositsand, therefore, for the bacteria to collect. Microbial films form whenaerobic species, such as iron-oxidizing bacteria, create anaerobic conditionsunderneath them for microorganisms, such as sulfate-reducing bacteria, toaccumulate at the metal surface. Sulfate-reducing bacteria attack the metalsurface, produce corrosive chemicals, and cause deep pitting.
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| K>J IN 94-79November 23, 1994 Microbiologically influenced corrosion on carbon steel will increase generalcorrosion, through-wall pitting, and the formation of tubercles. Tuberclesconsist of corrosion products, microbes, and debris. Tubercle growth couldrestrict cooling water flow to equipment.Stainless steel piping is not immune to microbiologically influenced corrosionbecause microbes can attack at the weld heat affected zone (HAZ) in stainlesssteels when this zone becomes sensitized. Microbiologically influencedcorrosion can also damage metals lined with polymeric materials, typically atcoating imperfections.Once microbial films are established on metal surfaces, they are extremelydifficult to eliminate because of the resiliency of the individualmicroorganisms. Biocides are applied by some licensees in areas wherecontinuous flow conditions cannot be maintained. However, biocide treatmentsare not always effective against established microorganism colonies becausethe biocide cannot penetrate through the tubercles or aerobic biofilms.Treatment against established colonies involves a combination of mechanical orchemical pipe cleaning, continued water treatment and regular maintenance.Continuous flow conditions have been found to prevent the attachment andgrowth of microbial films.It may be necessary to replace materials if microbiologically influencedcorrosion severely damages them or where mitigation measures cannot bring thesystem condition under control. Possible alternatives include replacingcarbon steel with stainless steel or replacing stainless steel with moreresistant materials, such as 6-percent molybdenum stainless steels, nickelbase alloys, titanium, or nonmetallic materials.The licensee did not regularly treat the Beaver Valley River water supplylines to the diesel with biocide or corrosion inhibitors. The chlorinationinjection point for the main river water headers is downstream of the branchlines to the emergency diesel generators. It also appears that the existingprogram at Haddam Neck of hypochlorite injection was not successful inmitigating the microbiologically influenced corrosion problems in stagnantdead-end lines at such locations as the emergency diesel generator supply.
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| IN 94-79November 23, 1994 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Vv BaDD ision f Project SupportOffice of Nuclear Reactor RegulationTechnical contacts: Michael Modes, RI James A. Davis, NRR(215) 337-5198 (301) 504-2713Peter P. Sena, RI Vern Hodge, NRR(412) 643-2000 (301) 504-1861Attachment:List of Recently ssued NRC Information Noticeshi It6 J'4 K>AttachmentIN 94-79November 23, 1994 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to94-7894-7794-7693-60,Supp. 194-7594-7494-7394-7294-71Electrical ComponentFailure due to Degrada-tion of Polyvinyl ChlorideWire InsulationMalfunction in Main Gen-erator Voltage RegulatorCausing Overvoltage atSafety-Related ElectricalEquipmentRecent Failures of Charging/Safety Injection Pump ShaftsReporting Fuel Cycleand Materials Events tothe NRC Operations CenterMinimum Temperaturefor CriticalityFacility ManagementResponsibilities forPurchased or ContractedServices for RadiationTherapy ProgramsClarification of Critical-ity Reporting CriteriaIncreased Control RodDrop Time from CrudBuildupDegradation of ScramSolenoid Pilot ValvePressure and ExhaustDiaphragms11/21/9411/17/9410/26/9410/20/9410/14/9410/13/9410/12/9410/05/9410/04/94All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor pressurized waterreactors.All 10 CFR Part 70fuel cycle licensees.All holders of OLs or CPspressurized-water reactors(PWRs).All U.S. Nuclear RegulatoryCommission MedicalLicensees.All fuel fabricationfacilities.All holders of OLs or CPsfor pressurized waterreactors.All holders of OLs or CPsfor boiling water reactors(BWRs).OL -Operating LicenseCP = Construction Permit
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| -1/4<> A~-' IN 94-79November 23, 1994 The licensee did not regularly treat the Beaver Valley River water supplylines to the diesel with biocide or corrosion inhibitors. The chlorinationinjection point for the main river water headers is downstream of the branchlines to the emergency diesel generators. It also appears that the existingprogram at Haddam Neck of hypochlorite injection was not successful inmitigating the microbiologically influenced corrosion problems in stagnantdead-end lines at such locations as the emergency diesel generator supply.This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Original signed by B.D. Liaw forBrian K. Grimes, DirectorDivision of Project SupportOffice of Nuclear Reactor RegulationTechnical contacts:Michael Modes,(215) 337-5198RIJames A. Davis, NRR(301) 504-2713Peter P. Sena, RI(412) 643-2000Vern Hodge, NRR(301) 504-1861Attachment:List of Recently Issued NRC Information Notices*err DDrFlVT) rnCUriRFNrENOFFICE *OGCB/DORS *TECH ED *REGION I *REGION INAME CVHodge JDMain MCModes PPSenaDATE J 09/08/94 09/09/94 09/01/94 10/03/94__ _ _ _ _ _ _ _ _ -EI I __ If_*Ann-nfEDrIOTAN TI
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| * FMrR/nF*S:EMCB/DE*C: EMCB/DE, I vv.1,EI *vI __ , --ARBlough JADavis RAHermann JRStrosnider10/03/94 09/20/94 09/20/94-~~~ II f*n. nr*nCrRR /nnP5I *C AFCBIDOPSI D:DdPWi/Orv.LvL _. -BWSheron RLDennig AEChaffee G& I _J110/06/94 10/20/94 10/25/94 1 1 ff_/_ 4 LjDOCUMENT NAME: 94-79.IN
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| IN 94-XXOctober xx, 1994 inhibitors. The chlorination injection point for the main riverwater headers is downstream of the branch lines to the emergencydiesel generators. It also appears that the existing program atHaddam Neck of hypochlorite injection was not successful inmitigating the microbiologically influenced corrosion problems instagnant dead-end lines to such locations as the emergency dieselgenerator supply.This information notice requires no specific action or writtenresponse. If you have any questions about the information inthis notice, please contact one of the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation(NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorSupportOffice of Nuclear ReactorRegulationTechnical contacts: Michael Modes, Region I(215) 337-5198Peter P. Sena, Region I(412) 643-2000James A.Davis, NRR(301) 504-2713Attachment: List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB/DORS *TECH ED *REGION I *REGION INAME CVHodge JDMain MCModes PPSenaDATE 09/08/94 j09/09/94 09/01/94 10/03/94._ -11*Ann:DRA/RFCION I I *EMCB/DE I *S:EMCB/DE I *C:EMCB/DEARBlough JADavis RAHermann JRStrosnider10/03/94 09/20/94 09/20/94 09 94--I -I ~' -7 i*n FOEC 6I1QS I C:994A2'OPS I IWS/NRRBWSheron RLW A af e B j jes10/06/94 10/9 1,/94 10/ /94 _________DOCUMENT NAME: NECK-MIC. INY
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| -IN 94-XXSeptember xx, 1994 stagnant dead-end lines to such locations as the emergency dieselgenerator supply.This information notice requires no specific action or writtenresponse. If you have any questions about the information inthis notice, please contact one of the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation(NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorSupportOffice of Nuclear ReactorRegulationTechnical contacts:Michael Modes, Region I(215) 337-5198Peter P. Sena, Region I(412) 643-2000James A. Davis, NRR(301) 504-2713Attachment: List of Recently Issued NRC Information Notices.-- "tf A R'lena-*QVV DPRVUSTnT1 CONCURRENCE--.:L: -a V -__s_ ___ -r- -m --OFFICE *OGCB/DORS *TECH ED *REGION I REGION I ANAME CVHodge I JDMain MCModes PPSenaDATE j09/08/94 09/09/94 09/01/94 ff /o3/94_ I ., ._IIannlnPq/RFnTON T*EMCB/DE*S: EMCB/DEC;EMCB/DE fir-_ I___ __a _ v_ --ARBlough JADavis RAHermann LdRStrosnider-___ /9 09/20/94 09/20/94 09/X6/941~.1DkbzAC:OGCB/DORSD:DORS/NRRBW on ELDoolittle BKGrimes__/__ /94 09/ /94 09/ /94DOCUMgNT NAME: NECK-MIC.1firA-- 016 IIN 94-XXSeptember xx, 1994 This information notice requires no specific action or writtenresponse. If you have any questions about the information inthis notice, please contact one of the technical contacts listedbelow or the appropriate Office of Nuclear Reactor Regulation(NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorSupportOffice of Nuclear ReactorRegulationTechnical contacts:Michael Modes, Region I(215) 337-5198Peter P. Sena, Region I(412) 643-2000James A. Davis, NRR(301) 504-2713Attachment: List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE --- eIml e .Ac>Iveiw 6 2OFFICE OGCB/DORS TECH ED A REGION I REGION INAME CVHodge k ^JDMain MCModes PPSenaDATE 1 O9/08/94 09/09/94 09/01/94 09/ /94ADD:DRS/REGION IEMCB/DES:EMCB/DFC:EMCB/DEARBlough JADa RAHermann JRStrosnider09/ /94 09/0O/94 09/7v/94 09/ /94D: DEAC:OGCB/DORSD:DORS/NRRBWSheron ELDoolittle BKGrimes09/ /94 09/ /94 09/ /94DOCU;MENT NAME: NECK-MIC.INF
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Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water PipingML031060426 |
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: |
11/23/1994 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-94-079, NUDOCS 9411170039 |
Download: ML031060426 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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). 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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>. |
I UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 November 23, 1994 NRC INFORMATION
NOTICE 94-79: MICROBIOLOGICALLY
INFLUENCED
CORROSION
OF EMERGENCY
DIESEL GENERATOR
SERVICE WATER PIPING
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.PurDose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to degradation
resulting
from microbiologically
influenced
corrosion
in carbon steel piping systems that supply service water to emergency
diesel 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
Haddam Neck Plant On February 12, 1994, a through-wall
leak developed
in the service water system supply piping to the "A" emergency
diesel generator.
The leak occurred in a weld in an area of low flow, where the licensee was doing light surface grinding to prepare for ultrasonic
test (UT) inspection.
Previously, in March 1993, the licensee had found a similar leak associated
with the "B" emergency diesel generator.
After removing the leaking section and examining
the pipe, the licensee determined
that the leak was caused by poor initial weld quality and microbiologically
influenced
corrosion.
Lack of penetration
of some welds created a crevice condition.
Radiographic
tests (RT) of additional
emergency diesel generator
service water system piping revealed three additional
welds that could form similar leaks. It was during preparation
of one of these welds for UT examination
that the through-wall
leak associated
with the "A" emergency
diesel generator
was found.The licensee had previously
performed
a structural
integrity
determination
in 1993 by radiography.
Though based on a uniform wall loss instead of a sharp ,disruption, the licensee had at that time concluded
that the worst-case
degraded cross-section
of the as-found pipe welds, located in the unisolable
portions of the emergency
diesel generator
supply piping, met the Generic Letter 90-05 acceptance
criteria for structural
integrity
and that the degraded piping would have sufficient
mechanical
and structural
integrity
to remain operable.
&_ r" .in '^*94170C 9411170039 towzl +2ji)K I TE NO-rice H#-14-u1 T4 lII /-
IN 94-79 November 23, 1994 Beaver Valley Power Station. Unit I On May 6, 1994, the licensee found a through-wall
leak (an 8 mm [5/16 inch]diameter hole) on the "Al train reactor plant river water system header to the emergency
diesel generators.
The leak developed
on the below-grade
portion of the 15-cm [6-inch] diameter A106 Grade B carbon steel piping. The licensee excavated
the "A" and 'B" train headers, ultrasonically
examined them using the "autoscan" area mapping technique, and found localized
pitting to less than minimum required wall thickness
in three additional
locations
along the"A" train piping. The pits were not clustered
or closely spaced, but were located along the pipe length between the five and seven o'clock positions.
For reference, the nominal pipe wall thickness
is 6.4 mm [0.25 inch] and minimum code wall thickness
is 1.5 mm [0.06 inch].The licensee evaluated
the pitting in accordance
with the American Society of Mechanical
Engineers (ASME) Code of record. The basis for the localized thinning evaluation
was conducted
in accordance
with industry guidance, EPRI NP-59IISP, "Acceptance
Criteria for Structural
Evaluation
of Erosion-Corrosion
Thinning in Carbon Steel Piping." This evaluation
was reviewed by personnel in NRR and deemed as an acceptable
conservative
means of demonstrating
ASME Code conformance.
The licensee determined
microbiologically
influenced
corrosion
to be the cause of the pitting and through-wall
leak. The licensee removed a 0.61 m [24 inch] long section of piping to culture and characterize
the microbial
activity and perform additional
ultrasonic
testing.The general inside surface of the piping was moderately
corroded, with localized
pits and tubercles.
Cultures from the pits contained
sulfur-reducing bacteria and the anaerobic
bacteria Clostridium.
The tubercle formation
was the result of the growth of the iron-oxidizing
bacteria Gallionella.
Ultrasonic
examinations
of a heat-affected
zone indicated
that the weld examined was not subject to preferential
microbiologically
influenced
corrosion
attack.Discussion
Stagnant or intermittent-flow
conditions, as in the case of emergency
diesel service water supply headers, are conducive
to the growth of microorganisms
that can accelerate
corrosion
rates. Service water supply lines to emergency diesel generators
are stagnant because motor-operated
isolation
valves are normally maintained
shut (except during monthly surveillance
testing).Crevices such as those in piping welds that lack penetration
can enhance microbiologically
influenced
corrosion
attack by giving a place for deposits and, therefore, for the bacteria to collect. Microbial
films form when aerobic species, such as iron-oxidizing
bacteria, create anaerobic
conditions
underneath
them for microorganisms, such as sulfate-reducing
bacteria, to accumulate
at the metal surface. Sulfate-reducing
bacteria attack the metal surface, produce corrosive
chemicals, and cause deep pitting.
K>J IN 94-79 November 23, 1994 Microbiologically
influenced
corrosion
on carbon steel will increase general corrosion, through-wall
pitting, and the formation
of tubercles.
Tubercles consist of corrosion
products, microbes, and debris. Tubercle growth could restrict cooling water flow to equipment.
Stainless
steel piping is not immune to microbiologically
influenced
corrosion because microbes can attack at the weld heat affected zone (HAZ) in stainless steels when this zone becomes sensitized.
Microbiologically
influenced
corrosion
can also damage metals lined with polymeric
materials, typically
at coating imperfections.
Once microbial
films are established
on metal surfaces, they are extremely difficult
to eliminate
because of the resiliency
of the individual
microorganisms.
Biocides are applied by some licensees
in areas where continuous
flow conditions
cannot be maintained.
However, biocide treatments
are not always effective
against established
microorganism
colonies because the biocide cannot penetrate
through the tubercles
or aerobic biofilms.Treatment
against established
colonies involves a combination
of mechanical
or chemical pipe cleaning, continued
water treatment
and regular maintenance.
Continuous
flow conditions
have been found to prevent the attachment
and growth of microbial
films.It may be necessary
to replace materials
if microbiologically
influenced
corrosion
severely damages them or where mitigation
measures cannot bring the system condition
under control. Possible alternatives
include replacing carbon steel with stainless
steel or replacing
stainless
steel with more resistant
materials, such as 6-percent
molybdenum
stainless
steels, nickel base alloys, titanium, or nonmetallic
materials.
The licensee did not regularly
treat the Beaver Valley River water supply lines to the diesel with biocide or corrosion
inhibitors.
The chlorination
injection
point for the main river water headers is downstream
of the branch lines to the emergency
diesel generators.
It also appears that the existing program at Haddam Neck of hypochlorite
injection
was not successful
in mitigating
the microbiologically
influenced
corrosion
problems in stagnant dead-end lines at such locations
as the emergency
diesel generator
supply.
IN 94-79 November 23, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Vv BaD D ision f Project Support Office of Nuclear Reactor Regulation
Technical
contacts:
Michael Modes, RI James A. Davis, NRR (215) 337-5198 (301) 504-2713 Peter P. Sena, RI Vern Hodge, NRR (412) 643-2000 (301) 504-1861 Attachment:
List of Recently ssued NRC Information
Notices hi It6 J'4 K>Attachment
IN 94-79 November 23, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 94-78 94-77 94-76 93-60, Supp. 1 94-75 94-74 94-73 94-72 94-71 Electrical
Component Failure due to Degrada-tion of Polyvinyl
Chloride Wire Insulation
Malfunction
in Main Gen-erator Voltage Regulator Causing Overvoltage
at Safety-Related
Electrical
Equipment Recent Failures of Charging/Safety Injection
Pump Shafts Reporting
Fuel Cycle and Materials
Events to the NRC Operations
Center Minimum Temperature
for Criticality
Facility Management
Responsibilities
for Purchased
or Contracted
Services for Radiation Therapy Programs Clarification
of Critical-ity Reporting
Criteria Increased
Control Rod Drop Time from Crud Buildup Degradation
of Scram Solenoid Pilot Valve Pressure and Exhaust Diaphragms
11/21/94 11/17/94 10/26/94 10/20/94 10/14/94 10/13/94 10/12/94 10/05/94 10/04/94 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 pressurized
water reactors.All 10 CFR Part 70 fuel cycle licensees.
All holders of OLs or CPs pressurized-water
reactors (PWRs).All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All fuel fabrication
facilities.
All holders of OLs or CPs for pressurized
water reactors.All holders of OLs or CPs for boiling water reactors (BWRs).OL -Operating
License CP = Construction
Permit
-1/4<> A~-' IN 94-79 November 23, 1994 The licensee did not regularly
treat the Beaver Valley River water supply lines to the diesel with biocide or corrosion
inhibitors.
The chlorination
injection
point for the main river water headers is downstream
of the branch lines to the emergency
diesel generators.
It also appears that the existing program at Haddam Neck of hypochlorite
injection
was not successful
in mitigating
the microbiologically
influenced
corrosion
problems in stagnant dead-end lines at such locations
as the emergency
diesel generator
supply.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by B.D. Liaw for Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
contacts: Michael Modes, (215) 337-5198 RI James A. Davis, NRR (301) 504-2713 Peter P. Sena, RI (412) 643-2000 Vern Hodge, NRR (301) 504-1861 Attachment:
List of Recently Issued NRC Information
Notices*err DDrFlVT) rnCUriRFNrEN
OFFICE *OGCB/DORS
- TECH ED *REGION I *REGION I NAME CVHodge JDMain MCModes PPSena DATE J 09/08/94 09/09/94 09/01/94 10/03/94__ _ _ _ _ _ _ _ _ -EI I __ If_*Ann-nfEDrIOTAN
T I
- C: EMCB/DE , I vv.1,EI *vI __ , --ARBlough JADavis RAHermann
JRStrosnider
10/03/94 09/20/94 09/20/94-~~~ II f*n. nr*nCrRR /nnP5 I *C AFCBIDOPS I D:DdPWi/Or
v.LvL _. -BWSheron RLDennig AEChaffee
G& I _J1 10/06/94 10/20/94 10/25/94 1 1 ff_/_ 4 Lj DOCUMENT NAME: 94-79.IN
IN 94-XX October xx, 1994 inhibitors.
The chlorination
injection
point for the main river water headers is downstream
of the branch lines to the emergency diesel generators.
It also appears that the existing program at Haddam Neck of hypochlorite
injection
was not successful
in mitigating
the microbiologically
influenced
corrosion
problems in stagnant dead-end lines to such locations
as the emergency
diesel generator
supply.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A.Davis, NRR (301) 504-2713 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
OFFICE *OGCB/DORS
- TECH ED *REGION I *REGION I NAME CVHodge JDMain MCModes PPSena DATE 09/08/94 j09/09/94
09/01/94 10/03/94._ -11*Ann:DRA/RFCION
I I *EMCB/DE I *S:EMCB/DE
I *C:EMCB/DE
ARBlough JADavis RAHermann
JRStrosnider
10/03/94 09/20/94 09/20/94 09 94--I -I ~' -7 i*n FOEC 6I1QS I C:994A2'OPS
I IWS/NRR BWSheron RLW A af e B j jes 10/06/94 10/9 1,/94 10/ /94 _________DOCUMENT NAME: NECK-MIC.
INY
-IN 94-XX September
xx, 1994 stagnant dead-end lines to such locations
as the emergency
diesel generator
supply.This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A. Davis, NRR (301) 504-2713 Attachment:
List of Recently Issued NRC Information
Notices.-- "tf A R'lena-*QVV DPRVUSTnT1 CONCURRENCE
--.:L: -a V -__s_ ___ -r- -m --OFFICE *OGCB/DORS
- TECH ED *REGION I REGION I A NAME CVHodge I JDMain MCModes PPSena DATE j09/08/94
09/09/94 09/01/94 ff /o3/94_ I ., ._II annlnPq/RFnTON
T*EMCB/DE*S: EMCB/DE C;EMCB/DE
fir-_ I___ __a _ v_ --ARBlough JADavis RAHermann
LdRStrosnider
-___ /9 09/20/94 09/20/94 09/X6/94 1~.1 Dkbz AC:OGCB/DORS
D:DORS/NRR
BW on ELDoolittle
BKGrimes__/__ /94 09/ /94 09/ /94 DOCUMgNT NAME: NECK-MIC.1fir
A-- 016 I IN 94-XX September
xx, 1994 This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Michael Modes, Region I (215) 337-5198 Peter P. Sena, Region I (412) 643-2000 James A. Davis, NRR (301) 504-2713 Attachment:
List of Recently Issued NRC Information
Notices*SEE PREVIOUS CONCURRENCE
--- eIml e .Ac>Iveiw
6 2 OFFICE OGCB/DORS
TECH ED A REGION I REGION I NAME CVHodge k ^JDMain MCModes PPSena DATE 1 O9/08/94 09/09/94 09/01/94 09/ /94 ADD:DRS/REGION
I EMCB/DE S:EMCB/DF C:EMCB/DE ARBlough JADa RAHermann
JRStrosnider
09/ /94 09/0O/94 09/7v/94 09/ /94 D: DE AC:OGCB/DORS
D:DORS/NRR
BWSheron ELDoolittle
BKGrimes 09/ /94 09/ /94 09/ /94 DOCU;MENT
NAME: NECK-MIC.INF
|
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|
list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed trip)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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