|
|
Line 14: |
Line 14: |
| | page count = 12 | | | page count = 12 |
| }} | | }} |
| {{#Wiki_filter:I'- 'UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555April 1, 1993NRC INFORMATION NOTICE 93-25: ELECTRICAL PENETRATION ASSEMBLY DEGRADATION | | {{#Wiki_filter:I'- 'UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | ===OFFICE OF NUCLEAR REACTOR REGULATION=== |
| | WASHINGTON, D.C. 20555 April 1, 1993 NRC INFORMATION |
| | |
| | NOTICE 93-25: ELECTRICAL |
| | |
| | PENETRATION |
| | |
| | ===ASSEMBLY DEGRADATION=== |
|
| |
|
| ==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 problems that could result in degradation ofelectrical penetration assembly seals. This information notice focuses on thecontainment integrity function of these seals. It is expected that recipientswill review 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 problems that could result in degradation |
| | |
| | of electrical |
| | |
| | penetration |
| | |
| | assembly seals. This information |
| | |
| | notice focuses on the containment |
| | |
| | integrity |
| | |
| | function of these seals. It is expected that recipients |
| | |
| | will review the information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, as appropriate, to avoid similar problems. |
| | |
| | ===However, suggestions=== |
| | contained |
| | |
| | in this information |
| | |
| | notice are not NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances |
| | |
| | In July 1987 and in October 1989, the licensee for the Trojan Nuclear Plant, the Portland General Electric Company, reported problems with containment |
| | |
| | air leakage through its Bunker-Ramo |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assembly seals[licensee |
| | |
| | event reports (LERs) 50-344/87-11 and 50-344/89-23]. |
| | |
| | In July and August 1991, the NRC inspected |
| | |
| | the use of containment |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assembly seals at Trojan and concluded |
| | |
| | that the licensee had not established |
| | |
| | an effective |
| | |
| | program for trending and evaluating |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assembly seal leakage (Inspection |
| | |
| | Report 50-344/91-27). |
| | |
| | On October 28, 1991, while the plant was in a refueling |
| | |
| | outage, the licensee reported to the NRC that in the originally |
| | |
| | installed |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assemblies, the seal (polyurethane) |
| | and lubricant (Celvacene |
| | |
| | or Glycerin) |
| | materials |
| | |
| | were inappropriate |
| | |
| | for the application (LER 50-344/91-11-01). |
| | |
| | The licensee concluded |
| | |
| | that these materials |
| | |
| | may cause seal degradation |
| | |
| | and that the seals may become degraded if subjected |
| | |
| | to design basis accident conditions |
| | |
| | for moisture or temperature. |
| | |
| | The licensee replaced the electrical |
| | |
| | penetration |
| | |
| | assembly seal with an environmentally |
| | |
| | qualified |
| | |
| | ethylene propylene |
| | |
| | rubber seal and added a silicone rubber backup O-ring to the outer face of each electrical |
| | |
| | penetration |
| | |
| | assembly module. The licensee subsequently |
| | |
| | replaced all the Bunker-Ramo |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | with Conax assemblies. |
| | |
| | Discussion |
| | |
| | Electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | provide electrical |
| | |
| | continuity |
| | |
| | for field cables penetrating |
| | |
| | the containment |
| | |
| | and maintain containment |
| | |
| | integrity. |
| | |
| | 9303250146 |
| | -PW a: f1) t arC;02S ISoC'aoI I \l |
| | |
| | .a IN 93-25 April 1, 1993 Degraded electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | can adversely |
| | |
| | affect containment |
| | |
| | integrity |
| | |
| | by allowing excessive |
| | |
| | leakage from the containment |
| | |
| | under accident conditions. |
| | |
| | The Bunker-Ramo |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assembly consists of a cylindrical |
| | |
| | structure |
| | |
| | with circular header plates at each end. One header plate is designed to be bolted to a flange on the containment |
| | |
| | liner plate penetration |
| | |
| | nozzle. Containment |
| | |
| | integrity |
| | |
| | is achieved by two C-cup seals between the flanges. In the Bunker-Ramo |
| | |
| | design, a helical spring-loaded |
| | |
| | polyurethane |
| | |
| | seal is mounted at each end of the-electrical |
| | |
| | penetration |
| | |
| | assembly. |
| | |
| | Each electrical |
| | |
| | penetration |
| | |
| | assembly has two seals, an outer one, nominally |
| | |
| | of 8.9 cm [3.5 inch] diameter, and an inner one, of nominally |
| | |
| | 6.4 cm [2.5 inch]diameter. |
| | |
| | The outer seal functions |
| | |
| | as part of the containment |
| | |
| | boundary while the inner seal functions |
| | |
| | as an outer seal test pressure boundary. |
| | |
| | The electrical |
| | |
| | penetration |
| | |
| | assembly header plate is equipped with a connection |
| | |
| | to which a pressure indicating |
| | |
| | gauge can be attached to monitor seal leakage.At the Trojan plant, the qualified |
| | |
| | life of the seal had not been accurately |
| | |
| | established. |
| | |
| | The simultaneous |
| | |
| | effects of corrosion |
| | |
| | and moisture at normal temperature |
| | |
| | had not been taken into account. The established |
| | |
| | longevity |
| | |
| | was not corrected |
| | |
| | after factoring |
| | |
| | in the actual degradation |
| | |
| | observed during periodic surveillance |
| | |
| | of the individual |
| | |
| | seals.' Also, an administrative |
| | |
| | mechanism |
| | |
| | was not in place to replace the seals before their estimated qualified |
| | |
| | life expired. The original seal material in the Bunker-Ramo |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assembly has polyester''urethane |
| | |
| | manufactured |
| | |
| | by Parker Packing Company (Parker) under the trade name of Parkerthane (Parker Compound No. P4611). Parker, which manufactures |
| | |
| | both polyester |
| | |
| | urethane and polyether urethane seals, indicated |
| | |
| | in its catalog that polyester |
| | |
| | urethane maintains critical characteristics |
| | |
| | up to 6 years while polyether |
| | |
| | urethane maintains critical characteristics |
| | |
| | up to 10 years.The polyester |
| | |
| | urethane (the originally |
| | |
| | installed |
| | |
| | seal material) |
| | was determined |
| | |
| | inadequate |
| | |
| | for several reasons: Short expected life (independently |
| | |
| | estimated |
| | |
| | at 2-5 years under some conditions) |
| | Incompatibility |
| | |
| | with water (hydrolysis |
| | |
| | shortens life)Incompatibility |
| | |
| | with high temperature (acceleration |
| | |
| | of hydrolysis) |
| | Susceptibility |
| | |
| | to compression-set (a slowly acquired permanent deformation) |
| | The licensee used different |
| | |
| | lubricants |
| | |
| | over the years. In 1987, the licensee determined |
| | |
| | that three seals had failed because they were erroneously |
| | |
| | lubricated |
| | |
| | with an incompatible (silicone) |
| | grease. After examination |
| | |
| | of seal failures that occurred in 1991, Parker determined |
| | |
| | that the failed seals had castor oil residue on the exterior, indicative |
| | |
| | of the use of Celvacene lubricant', which'includes |
| | |
| | castor oil and cellulose |
| | |
| | acetate butyrate.Celvacene, specified |
| | |
| | for use by the original penetration |
| | |
| | supplier, can cause |
| | |
| | IN 93-25 April 1, 1993 degradation |
| | |
| | of polyurethane |
| | |
| | as follows. The cellulose |
| | |
| | acetate butyrate component |
| | |
| | breaks down in the presence of moisture, producing |
| | |
| | butyric acid, which in turn catalyses |
| | |
| | hydrolysis |
| | |
| | of the seal polymer. The hydrolysis |
| | |
| | slowly degrades the polyurethane |
| | |
| | material. |
| | |
| | Under accident conditions, the seal degradation |
| | |
| | may be accelerated. |
| | |
| | The original penetration |
| | |
| | supplier, Bunker-Ramo, no longer supplies such assemblies. |
| | |
| | Similar electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | have been supplied by Amphenol, but this company also no longer supplies such assemblies. |
| | |
| | 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: |
| | C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment: |
| | List of Receitly Issued NRC Information |
| | |
| | Notices |
| | |
| | 14 Attachment |
| | |
| | IN 93-25 April 1, 1993 Page I of I LIST OF RECENTLY ISSUED KRC INFORMlATION |
| | |
| | NOTICES a 4c 40L '0 I UJ :3 0 A.UflU Inrormation |
| | |
| | Notice No.93-24 93-23 93-22 93-21 93-20 93-19 93-18)93-17 93-16 Subject Distribution |
| | |
| | of Revision 7 of PURE6-1021. |
| | |
| | 0Operator |
| | |
| | Licensing Examiner Standards" Weschler Instruments |
| | |
| | ===Nodel 252 Switchboard=== |
| | Peters Triping of Klockner-Nfoeller Molded-Case |
| | |
| | Circuit Breakers due to Support Level Failure Summary of NRC Staff Observations |
| | |
| | Compiled during Engineering |
| | |
| | Audits or Inspections |
| | |
| | of Licen-see Erosion/Corrosion |
| | |
| | Programs Thermal Fatigue Cracking of Feedwater |
| | |
| | Piping to*Steam Generators |
| | |
| | Slab Hopper Bulging Portable Moisture-Density |
| | |
| | ===Gauge User Responsibilities=== |
| | during Field Operations |
| | |
| | Safety Systems Response to Loss of Coolant and Loss of Offs1te Power Failures of Nut-Locking |
| | |
| | Devices in Check Valves Issuane Issued to 03/31/93 All holders of orater and senior operator eienses at nuclear power reactors.03/31/93 All holders of OLs or CPs for nuclear power reactors.03/26/93 All holders of OLs or CPs for nuclear power reactors.03/25/93 All holders of OLs or CPs for light water nuclear power reactors.I i 03/24/93 All holders of OLs or CPs for PWRs supplied by Westinghouse |
| | |
| | or Combustion |
| | |
| | Engineering. |
| | |
| | 03/17/92 All nuclear fuel cycle licensees. |
| | |
| | 03/10/93 All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees |
| | |
| | that possess moisture-density |
| | |
| | gauges.03/08/93 All holders of OLs or CPs for nuclear power reactors.02/19/93 All holders of OLs or CPs for nuclear power reactors.2 I(00 00 W O 1 c1 n 2 IL I-I U 4): zU Z a FA.~OL -Operating |
| | |
| | License CP -Construction |
| | |
| | Permit |
| | |
| | IN 93-25 April 1, 1993 degradation |
| | |
| | of polyurethane |
| | |
| | as follows. The cellulose |
| | |
| | acetate butyrate component |
| | |
| | breaks down in the presence of moisture, producing |
| | |
| | butyric acid, which in turn catalyses |
| | |
| | hydrolysis |
| | |
| | of the seal polymer. The hydrolysis |
| | |
| | slowly degrades the polyurethane |
| | |
| | material. |
| | |
| | Under accident conditions, the seal degradation |
| | |
| | may be accelerated. |
| | |
| | The original penetration |
| | |
| | supplier, Bunker-Ramo, no longer supplies such assemblies. |
| | |
| | Similar electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | have been supplied by Amphenol, but this company also no longer supplies such assemblies. |
| | |
| | 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.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating |
| | |
| | ===Reactor Support Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices*SEE PRMV a CONCURRENCES |
| | |
| | *C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | GHMarcus TechEd 03/05/93 04/13/92*D/DRIL:NRR |
| | |
| | CERossi 03/03/93*C/RVIB:DRIL:NRR |
| | |
| | LJNorrholm |
| | |
| | 02/27/93*OGCB: DORS:NRR CVHodge 06/03/92*RESINSP/RV |
| | |
| | RBarr 06/03/92*RVIB:DRIL:NRR |
| | |
| | KNaidu 01/11/93*SC/RVIB:DRIL:NRR |
| | |
| | GCwallna 02/27/93 DOCUMENT NAME: 93-25.IN |
| | |
| | IN 93-XX March xx, 1993 castor oil residue on the exterior, indicative |
| | |
| | of the use of Celvacene lubricant, which includes castor oil and cellulose |
| | |
| | acetate butyrate.Celvacene, specified |
| | |
| | for use by the original penetration |
| | |
| | supplier, can cause degradation |
| | |
| | of polyurethane |
| | |
| | as follows. The cellulose |
| | |
| | acetate butyrate component |
| | |
| | breaks down in the presence of moisture, producing |
| | |
| | butyric acid, which in turn catalyses |
| | |
| | hydrolysis |
| | |
| | of the seal polymer. The hydrolysis |
| | |
| | slowly degrades the polyurethane |
| | |
| | material. |
| | |
| | Under accident conditions, the seal degradation |
| | |
| | may be accelerated. |
| | |
| | The original penetration |
| | |
| | supplier, Bunker-Ramo, no longer supplies such assemblies. |
| | |
| | Si ilar electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | have been supplied by Amphenol6w-butThis |
| | |
| | company also no longer supplies such assemblies. -A 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: |
| | C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices Document Name: PRESBOUN.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | D/DORS:NRR |
| | |
| | BKGrimes 03/ /93U*C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | *D/DRIL:NRR |
| | |
| | C/RVIB:DRIL:NRR |
| | |
| | ===GHMarcus TechEd CERossi LJNorrholm=== |
| | 03/05/93 04/13/92 03/03/93 02/271/93*OGCB:DORS:NRR |
| | |
| | *RESINSP/RV |
| | |
| | *RVIB:DRIL:NRR |
| | |
| | *SC/RVIB:DRIL:NRR |
| | |
| | CVHodge RBarr KNaidu GCwalina 06/03/92 06/03/92 01/11/93 02/27/93 IN 93-XX March xx, 1993 degradation |
| | |
| | of polyurethane |
| | |
| | as follows. Ihe cellulose |
| | |
| | acetate butyrate ccuponent |
| | |
| | breaks dawm in the presence of irsture, producing |
| | |
| | butyric acid, whici in turn catalyses |
| | |
| | hydrolysis |
| | |
| | of the seal polymer. The hydrolysis |
| | |
| | slowly degrades the polyurethane |
| | |
| | material. |
| | |
| | Mier accident cmditins,, the seal degradation |
| | |
| | may be accelerated. |
| | |
| | The original penetration |
| | |
| | supplier, Bunker-Ramo, is no longer in the business.Similar electrical |
| | |
| | penetraticn |
| | |
| | assemblies |
| | |
| | have been splied -by Anphenol, but this ccapany also is no lcnger in the hksiness. |
| | |
| | Ihe licensee at Trojan replaced its Eunker-Ramo |
| | |
| | electrical |
| | |
| | penetration |
| | |
| | assemblies |
| | |
| | with Ckmax electrical |
| | |
| | penetration |
| | |
| | assemblies. |
| | |
| | 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 aPqrcpriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Cperating |
| | |
| | ===Reactor Support Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: |
| | C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naid, NRR (301) 504-2980 Attachment: |
| | List of Recently Issued NR Information |
| | |
| | Notices D x:mnt Name: PRESBCEXI |
| | |
| | IN*SEE PREVIOUS aONCNRRENcS |
| | |
| | D/DORS:NRR |
| | |
| | C/OGCB:DORS:MMR*RPB:ADM |
| | |
| | *D/MlUL:NfR |
| | |
| | BI~rimes Grfrcus64W |
| | |
| | Tech~d CEossi 02/ /93 03/S /93 04/13/92 03/03/93*OGCB:DORS:NRR |
| | |
| | *PMINSP/RV |
| | |
| | *REV :RI:NR:R *SC/RVIB:DR:M;R*C/RIB:WIL:NRR |
| | |
| | CvHodge RBarr .Naidu Gwalina mJ~orrhobii |
| | |
| | 06/03/92 06/03/92 01/11/93 02/27/93 02/27/93 |
| | -IN 93-XX February xx, 1993 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: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices Document Name: PRESBOUN.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | *OGCB:DORS:NRR |
| | |
| | CVHodge 06/03/92 D/DORS:NRR |
| | |
| | BKGrimes 02/ /93*RESINSP/RV |
| | |
| | RBarr 06/03/92 C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | GHMarcus TechEd 02/ /93 04/13/92*RVIB:DRIL:NRR |
| | |
| | SC/RVIB:DRIL:NRR |
| | |
| | KNaidu GCwalina 01/11/93 02/ /93 CYRU:DRIL:NRR |
| | |
| | LJNorrholm |
| | |
| | 02/ /93 IN 93-XX January xx, 1993 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: C. Vernon Hodge, (301) 504-1861 NRR Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices Document Name: PRESBOUN.IN |
| | |
| | *SEE PREVIOUS*OGCB: DORS:NRF CVHodge 06/03/92 CONCURRENCES |
| | |
| | D/DORS:NRR |
| | |
| | BKGrimes 01/ /93 Z *RESINSP/RV |
| | |
| | RBarr 06/03/92 C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | GHMarcus TechEd 01/ /93 04/13/92*RVIB:DRIL:NRR |
| | |
| | IB:DRIL:NRR |
| | |
| | KNaidu Gaina 01/11/93 /93 D/DRIL:NRR |
| | |
| | C--#-CERossi g gmlL:NRR 01/j /93 DD:DRIL:NRR |
| | |
| | RZimmerman |
| | |
| | 01/ /93 IN 93-XX January , 1993 ., under loss of coolant accident (LOCA) conditions. |
| | |
| | Premature |
| | |
| | degradation |
| | |
| | of the insulation |
| | |
| | covering the electrical |
| | |
| | connections |
| | |
| | can expose the connections |
| | |
| | to an adverse environment |
| | |
| | during a LOCA. A brief survey of these LERs is included in Attachment |
| | |
| | 1.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 |
| | |
| | Off ce of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating |
| | |
| | Reactor Office of Nuclear Reactor Regu Support lation Technical |
| | |
| | contacts: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal (301)Naidu, NRR 504-2980 Attachments: |
| | 1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information |
| | |
| | Notices Document Name: PRESBOUN.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | *OGCB:DORSONRR |
| | |
| | *RESINSP/RV |
| | |
| | CVHodge USA RBarr 06/03/92 0413 06/03/92 D/DORS:NRR |
| | |
| | BKGrimes 01/f /93! n IB:DRIL:NRR |
| | |
| | KNai du 01/11/93 C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | GHMarcus TechEd 01/ /93 04/13/92 C/RVIB:DRIL:NRR |
| | |
| | D/DRIL:NRR |
| | |
| | LJNorrholm |
| | |
| | CERossi 01/ /93 01/ /93..I zi' k I '. ,.-: I , : |
| | K>IN 93-XX January xx, 1993 identify excessive |
| | |
| | leakage of EPA seals indicating |
| | |
| | possible degradation |
| | |
| | from moisture intrusion. |
| | |
| | Degraded seals can cause breach of containment |
| | |
| | integrity under loss of coolant accident (LOCA) conditions. |
| | |
| | Premature |
| | |
| | degradation |
| | |
| | of the insulation |
| | |
| | covering the electrical |
| | |
| | connections |
| | |
| | can expose the connections |
| | |
| | to an adverse environment |
| | |
| | during a LOCA. A brief survey of these LERs is included in Attachment |
| | |
| | 1.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: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachments: |
| | 1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information |
| | |
| | Notices Document Name: PRESBOUN.IN |
| | |
| | *SEE PREVIOUS CONCURRENCES |
| | |
| | OGCB:DORS:NRR |
| | |
| | CVHodge V@06/o3/92 01 /Iq/3 D/DORS:NRR |
| | |
| | BKGrimes 01/ /93 RESINSP/RV |
| | |
| | RBarr w C/OGCB:DORS:NRR*RPB:ADM |
| | |
| | GHMarcus TechEd 01/ /93 04/13/92*RVIB:DRIL:NRR |
| | |
| | SC/RVIB:DRIL:NRR |
| | |
| | KNaidu GCwalina 01/11/93 01/ /93 D/DRIL:NRR |
| | |
| | CERossi 01/ /93 C/RVIB:DRIL:NRR |
| | |
| | LJNorrholm |
| | |
| | 01/ /93 of EPA seals represent |
| | |
| | violations |
| | |
| | of Containment |
| | |
| | integrity |
| | |
| | and environmental |
| | |
| | qualification |
| | |
| | deficiencies |
| | |
| | in EPA components |
| | |
| | indicatepe |
| | |
| | s m -/~u4n-deiiP |
| | |
| | coddia")loss~bf(oolant |
| | |
| | accident (LOCA) co'nditions. |
| | |
| | A brief survey of these LERs I4B'Cincluded |
| | |
| | in .ttachmet |
| | |
| | A im This information |
| | |
| | notice requires you have any questions |
| | |
| | about the of the technical |
| | |
| | contacts listed Reactor Regulation (NRR) project no specific action or written response. |
| | |
| | If information |
| | |
| | in this notice, please contact one below or the appropriate |
| | |
| | Office of Nuclear manager.Charles E. Rossi, Director Division of Operational |
| | |
| | ===Events Assessment=== |
| | Office of Nuclear Reactor Regulation |
| | |
| | Technical |
| | |
| | contacts: Vern Hodge, NRR (301) 504-1861 Rob Barr, RV (503) 556-3751 Attachments: |
| | 1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information |
| | |
| | Notices Document Name: BUNK0403 REV 19 OGCB:DOEA:NRR |
| | |
| | CVHodge 04/ /92 RESINSP/RV |
|
| |
|
| ==Description of Circumstances==
| | RBarr 04/ /92 D/DOEA:NRR |
| In July 1987 and in October 1989, the licensee for the Trojan Nuclear Plant,the Portland General Electric Company, reported problems with containment airleakage through its Bunker-Ramo electrical penetration assembly seals[licensee event reports (LERs) 50-344/87-11 and 50-344/89-23]. In July andAugust 1991, the NRC inspected the use of containment electrical penetrationassembly seals at Trojan and concluded that the licensee had not establishedan effective program for trending and evaluating electrical penetrationassembly seal leakage (Inspection Report 50-344/91-27). On October 28, 1991,while the plant was in a refueling outage, the licensee reported to the NRCthat in the originally installed electrical penetration assemblies, the seal(polyurethane) and lubricant (Celvacene or Glycerin) materials wereinappropriate for the application (LER 50-344/91-11-01). The licenseeconcluded that these materials may cause seal degradation and that the sealsmay become degraded if subjected to design basis accident conditions formoisture or temperature. The licensee replaced the electrical penetrationassembly seal with an environmentally qualified ethylene propylene rubber sealand added a silicone rubber backup O-ring to the outer face of each electricalpenetration assembly module. The licensee subsequently replaced all theBunker-Ramo electrical penetration assemblies with Conax assemblies.DiscussionElectrical penetration assemblies provide electrical continuity for fieldcables penetrating the containment and maintain containment integrity.9303250146 -PW a: f1) t arC;02S ISoC'aoII \l
| |
|
| |
|
| .aIN 93-25April 1, 1993 Degraded electrical penetration assemblies can adversely affect containmentintegrity by allowing excessive leakage from the containment under accidentconditions.The Bunker-Ramo electrical penetration assembly consists of a cylindricalstructure with circular header plates at each end. One header plate isdesigned to be bolted to a flange on the containment liner plate penetrationnozzle. Containment integrity is achieved by two C-cup seals between theflanges. In the Bunker-Ramo design, a helical spring-loaded polyurethane sealis mounted at each end of the-electrical penetration assembly. Eachelectrical penetration assembly has two seals, an outer one, nominally of8.9 cm [3.5 inch] diameter, and an inner one, of nominally 6.4 cm [2.5 inch]diameter. The outer seal functions as part of the containment boundary whilethe inner seal functions as an outer seal test pressure boundary. Theelectrical penetration assembly header plate is equipped with a connection towhich a pressure indicating gauge can be attached to monitor seal leakage.At the Trojan plant, the qualified life of the seal had not been accuratelyestablished. The simultaneous effects of corrosion and moisture at normaltemperature had not been taken into account. The established longevity wasnot corrected after factoring in the actual degradation observed duringperiodic surveillance of the individual seals.' Also, an administrativemechanism was not in place to replace the seals before their estimatedqualified life expired. The original seal material in the Bunker-Ramoelectrical penetration assembly has polyester''urethane manufactured by ParkerPacking Company (Parker) under the trade name of Parkerthane (Parker CompoundNo. P4611). Parker, which manufactures both polyester urethane and polyetherurethane seals, indicated in its catalog that polyester urethane maintainscritical characteristics up to 6 years while polyether urethane maintainscritical characteristics up to 10 years.The polyester urethane (the originally installed seal material) was determinedinadequate for several reasons:Short expected life (independently estimated at 2-5 years under someconditions)Incompatibility with water (hydrolysis shortens life)Incompatibility with high temperature (acceleration of hydrolysis)Susceptibility to compression-set (a slowly acquired permanentdeformation)The licensee used different lubricants over the years. In 1987, the licenseedetermined that three seals had failed because they were erroneouslylubricated with an incompatible (silicone) grease. After examination of sealfailures that occurred in 1991, Parker determined that the failed seals hadcastor oil residue on the exterior, indicative of the use of Celvacenelubricant', which'includes castor oil and cellulose acetate butyrate.Celvacene, specified for use by the original penetration supplier, can cause
| | CERossi 04/ /92 RVIB:DRIS:NRR |
|
| |
|
| IN 93-25April 1, 1993 degradation of polyurethane as follows. The cellulose acetate butyratecomponent breaks down in the presence of moisture, producing butyric acid,which in turn catalyses hydrolysis of the seal polymer. The hydrolysis slowlydegrades the polyurethane material. Under accident conditions, the sealdegradation may be accelerated.The original penetration supplier, Bunker-Ramo, no longer supplies suchassemblies. Similar electrical penetration assemblies have been supplied byAmphenol, but this company also no longer supplies such assemblies.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.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachment:List of Receitly Issued NRC Information Notices
| | KNaidu 04/ /92 C/OGCB:DOEA:NRR |
|
| |
|
| 14AttachmentIN 93-25April 1, 1993Page I of ILIST OF RECENTLY ISSUEDKRC INFORMlATION NOTICESa4c40L '0I UJ :30A.UflU InrormationNotice No.93-2493-2393-2293-2193-2093-1993-18)93-1793-16SubjectDistribution ofRevision 7 of PURE6-1021.0Operator LicensingExaminer Standards"Weschler InstrumentsNodel 252 SwitchboardPetersTriping of Klockner-Nfoeller Molded-CaseCircuit Breakers due toSupport Level FailureSummary of NRC StaffObservations Compiledduring Engineering Auditsor Inspections of Licen-see Erosion/CorrosionProgramsThermal Fatigue Crackingof Feedwater Piping to*Steam GeneratorsSlab Hopper BulgingPortable Moisture-DensityGauge User Responsibilitiesduring Field OperationsSafety Systems Responseto Loss of Coolant andLoss of Offs1te PowerFailures of Nut-LockingDevices in Check ValvesIssuane Issued to03/31/93 All holders of orater andsenior operator eienses atnuclear power reactors.03/31/93 All holders of OLs or CPsfor nuclear power reactors.03/26/93 All holders of OLs or CPsfor nuclear power reactors.03/25/93 All holders of OLs or CPsfor light water nuclearpower reactors.Ii03/24/93 All holders of OLs or CPsfor PWRs supplied byWestinghouse or CombustionEngineering.03/17/92 All nuclear fuel cyclelicensees.03/10/93 All U.S. Nuclear RegulatoryCommission licensees thatpossess moisture-densitygauges.03/08/93 All holders of OLs or CPsfor nuclear power reactors.02/19/93 All holders of OLs or CPsfor nuclear power reactors.2I(0000W O1 c1n 2IL I-I U4):zUZ aFA.~OL -Operating LicenseCP -Construction Permit
| | CHBerlinger |
|
| |
|
| IN 93-25April 1, 1993 degradation of polyurethane as follows. The cellulose acetate butyratecomponent breaks down in the presence of moisture, producing butyric acid,which in turn catalyses hydrolysis of the seal polymer. The hydrolysis slowlydegrades the polyurethane material. Under accident conditions, the sealdegradation may be accelerated.The original penetration supplier, Bunker-Ramo, no longer supplies suchassemblies. Similar electrical penetration assemblies have been supplied byAmphenol, but this company also no longer supplies such assemblies.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.orig /s/'d by BKGrimesBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachment:List of Recently Issued NRC Information Notices*SEE PRMV a CONCURRENCES*C/OGCB:DORS:NRR*RPB:ADMGHMarcus TechEd03/05/93 04/13/92*D/DRIL:NRRCERossi03/03/93*C/RVIB:DRIL:NRRLJNorrholm02/27/93*OGCB: DORS:NRRCVHodge06/03/92*RESINSP/RVRBarr06/03/92*RVIB:DRIL:NRRKNaidu01/11/93*SC/RVIB:DRIL:NRRGCwallna02/27/93DOCUMENT NAME: 93-25.IN
| | 04/ /92 RPB:ADM TechEd J'Ma;, )04/13 /92 ROAB:DSP:NRR |
|
| |
|
| IN 93-XXMarch xx, 1993 castor oil residue on the exterior, indicative of the use of Celvacenelubricant, which includes castor oil and cellulose acetate butyrate.Celvacene, specified for use by the original penetration supplier, can causedegradation of polyurethane as follows. The cellulose acetate butyratecomponent breaks down in the presence of moisture, producing butyric acid,which in turn catalyses hydrolysis of the seal polymer. The hydrolysis slowlydegrades the polyurethane material. Under accident conditions, the sealdegradation may be accelerated.The original penetration supplier, Bunker-Ramo, no longer supplies suchassemblies. Si ilar electrical penetration assemblies have been supplied byAmphenol6w-butThis company also no longer supplies such assemblies. -AThis 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.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachment:List of Recently Issued NRC Information NoticesDocument Name: PRESBOUN.IN*SEE PREVIOUS CONCURRENCESD/DORS:NRRBKGrimes03/ /93U*C/OGCB:DORS:NRR*RPB:ADM *D/DRIL:NRR C/RVIB:DRIL:NRRGHMarcus TechEd CERossi LJNorrholm03/05/93 04/13/92 03/03/93 02/271/93*OGCB:DORS:NRR *RESINSP/RV *RVIB:DRIL:NRR *SC/RVIB:DRIL:NRRCVHodge RBarr KNaidu GCwalina06/03/92 06/03/92 01/11/93 02/27/93 IN 93-XXMarch xx, 1993 degradation of polyurethane as follows. Ihe cellulose acetate butyrateccuponent breaks dawm in the presence of irsture, producing butyric acid,whici in turn catalyses hydrolysis of the seal polymer. The hydrolysis slowlydegrades the polyurethane material. Mier accident cmditins,, the sealdegradation may be accelerated.The original penetration supplier, Bunker-Ramo, is no longer in the business.Similar electrical penetraticn assemblies have been splied -by Anphenol, butthis ccapany also is no lcnger in the hksiness. Ihe licensee at Trojanreplaced its Eunker-Ramo electrical penetration assemblies with Ckmaxelectrical penetration assemblies.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 aPqrcpriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Cperating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naid, NRR(301) 504-2980Attachment:List of Recently Issued NR Information NoticesD x:mnt Name: PRESBCEXI IN*SEE PREVIOUS aONCNRRENcSD/DORS:NRR C/OGCB:DORS:MMR*RPB:ADM *D/MlUL:NfRBI~rimes Grfrcus64W Tech~d CEossi02/ /93 03/S /93 04/13/92 03/03/93*OGCB:DORS:NRR *PMINSP/RV *REV :RI:NR:R *SC/RVIB:DR:M;R*C/RIB:WIL:NRRCvHodge RBarr .Naidu Gwalina mJ~orrhobii06/03/92 06/03/92 01/11/93 02/27/93 02/27/93
| | SMazumdar 04/ /92}} |
| -IN 93-XXFebruary xx, 1993 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.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachment:List of Recently Issued NRC Information NoticesDocument Name:PRESBOUN.IN*SEE PREVIOUS CONCURRENCES*OGCB:DORS:NRRCVHodge06/03/92D/DORS:NRRBKGrimes02/ /93*RESINSP/RVRBarr06/03/92C/OGCB:DORS:NRR*RPB:ADMGHMarcus TechEd02/ /93 04/13/92*RVIB:DRIL:NRR SC/RVIB:DRIL:NRRKNaidu GCwalina01/11/93 02/ /93CYRU:DRIL:NRRLJNorrholm02/ /93 IN 93-XXJanuary xx, 1993 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.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:C. Vernon Hodge,(301) 504-1861NRRRobert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachment:List of Recently Issued NRC Information NoticesDocument Name:PRESBOUN.IN*SEE PREVIOUS*OGCB: DORS:NRFCVHodge06/03/92CONCURRENCESD/DORS:NRRBKGrimes01/ /93Z *RESINSP/RVRBarr06/03/92C/OGCB:DORS:NRR*RPB:ADMGHMarcus TechEd01/ /93 04/13/92*RVIB:DRIL:NRR IB:DRIL:NRRKNaidu Gaina01/11/93 /93D/DRIL:NRR C--#-CERossig gmlL:NRR01/j /93DD:DRIL:NRRRZimmerman01/ /93 IN 93-XXJanuary , 1993 .,under loss of coolant accident (LOCA) conditions. Premature degradation ofthe insulation covering the electrical connections can expose the connectionsto an adverse environment during a LOCA. A brief survey of these LERs isincluded in Attachment 1.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 Off ce ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorOffice of Nuclear Reactor ReguSupportlationTechnical contacts:C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal(301)Naidu, NRR504-2980Attachments:1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information NoticesDocument Name: PRESBOUN.IN*SEE PREVIOUS CONCURRENCES*OGCB:DORSONRR *RESINSP/RVCVHodge USA RBarr06/03/92 0413 06/03/92D/DORS:NRRBKGrimes01/f /93! n IB:DRIL:NRRKNai du01/11/93C/OGCB:DORS:NRR*RPB:ADMGHMarcus TechEd01/ /93 04/13/92C/RVIB:DRIL:NRR D/DRIL:NRRLJNorrholm CERossi01/ /93 01/ /93..I zi' k I '. ,.-: I , :
| |
| K>IN 93-XXJanuary xx, 993identify excessive leakage of EPA seals indicating possible degradation frommoisture intrusion. Degraded seals can cause breach of containment integrityunder loss of coolant accident (LOCA) conditions. Premature degradation ofthe insulation covering the electrical connections can expose the connectionsto an adverse environment during a LOCA. A brief survey of these LERs isincluded in Attachment 1.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.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:C. Vernon Hodge, NRR(301) 504-1861Robert C. Barr, Region V(509) 377-2627Kamal Naidu, NRR(301) 504-2980Attachments:1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information NoticesDocument Name:PRESBOUN.IN*SEE PREVIOUS CONCURRENCESOGCB:DORS:NRRCVHodge V@06/o3/9201 /Iq/3D/DORS:NRRBKGrimes01/ /93RESINSP/RVRBarr wC/OGCB:DORS:NRR*RPB:ADMGHMarcus TechEd01/ /93 04/13/92*RVIB:DRIL:NRR SC/RVIB:DRIL:NRRKNaidu GCwalina01/11/93 01/ /93D/DRIL:NRRCERossi01/ /93C/RVIB:DRIL:NRRLJNorrholm01/ /93 of EPA seals represent violations of Containment integrity and environmentalqualification deficiencies in EPA components indicatepe s m -/~u4n-deiiP coddia")loss~bf(oolant accident (LOCA) co'nditions. A brief survey of these LERs I4B'Cincluded in .ttachmet A imThis information notice requiresyou have any questions about theof the technical contacts listedReactor Regulation (NRR) projectno specific action or written response. Ifinformation in this notice, please contact onebelow or the appropriate Office of Nuclearmanager.Charles E. Rossi, DirectorDivision of Operational Events AssessmentOffice of Nuclear Reactor RegulationTechnical contacts:Vern Hodge, NRR(301) 504-1861Rob Barr, RV(503) 556-3751Attachments:1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information NoticesDocument Name: BUNK0403 REV 19OGCB:DOEA:NRRCVHodge04/ /92RESINSP/RVRBarr04/ /92D/DOEA:NRRCERossi04/ /92RVIB:DRIS:NRRKNaidu04/ /92C/OGCB:DOEA:NRRCHBerlinger04/ /92RPB:ADMTechEd J'Ma;, )04/13 /92ROAB:DSP:NRRSMazumdar04/ /92
| |
| }} | |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Electrical Penetration Assembly DegradationML031080020 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
04/01/1993 |
---|
From: |
Grimes B K Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-93-025, NUDOCS 9303250146 |
Download: ML031080020 (12) |
|
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 |
---|
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>. |
I'- 'UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 April 1, 1993 NRC INFORMATION
NOTICE 93-25: ELECTRICAL
PENETRATION
ASSEMBLY DEGRADATION
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 problems that could result in degradation
of electrical
penetration
assembly seals. This information
notice focuses on the containment
integrity
function of these seals. It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
In July 1987 and in October 1989, the licensee for the Trojan Nuclear Plant, the Portland General Electric Company, reported problems with containment
air leakage through its Bunker-Ramo
electrical
penetration
assembly seals[licensee
event reports (LERs) 50-344/87-11 and 50-344/89-23].
In July and August 1991, the NRC inspected
the use of containment
electrical
penetration
assembly seals at Trojan and concluded
that the licensee had not established
an effective
program for trending and evaluating
electrical
penetration
assembly seal leakage (Inspection
Report 50-344/91-27).
On October 28, 1991, while the plant was in a refueling
outage, the licensee reported to the NRC that in the originally
installed
electrical
penetration
assemblies, the seal (polyurethane)
and lubricant (Celvacene
or Glycerin)
materials
were inappropriate
for the application (LER 50-344/91-11-01).
The licensee concluded
that these materials
may cause seal degradation
and that the seals may become degraded if subjected
to design basis accident conditions
for moisture or temperature.
The licensee replaced the electrical
penetration
assembly seal with an environmentally
qualified
ethylene propylene
rubber seal and added a silicone rubber backup O-ring to the outer face of each electrical
penetration
assembly module. The licensee subsequently
replaced all the Bunker-Ramo
electrical
penetration
assemblies
with Conax assemblies.
Discussion
Electrical
penetration
assemblies
provide electrical
continuity
for field cables penetrating
the containment
and maintain containment
integrity.
9303250146
-PW a: f1) t arC;02S ISoC'aoI I \l
.a IN 93-25 April 1, 1993 Degraded electrical
penetration
assemblies
can adversely
affect containment
integrity
by allowing excessive
leakage from the containment
under accident conditions.
The Bunker-Ramo
electrical
penetration
assembly consists of a cylindrical
structure
with circular header plates at each end. One header plate is designed to be bolted to a flange on the containment
liner plate penetration
nozzle. Containment
integrity
is achieved by two C-cup seals between the flanges. In the Bunker-Ramo
design, a helical spring-loaded
polyurethane
seal is mounted at each end of the-electrical
penetration
assembly.
Each electrical
penetration
assembly has two seals, an outer one, nominally
of 8.9 cm [3.5 inch] diameter, and an inner one, of nominally
6.4 cm [2.5 inch]diameter.
The outer seal functions
as part of the containment
boundary while the inner seal functions
as an outer seal test pressure boundary.
The electrical
penetration
assembly header plate is equipped with a connection
to which a pressure indicating
gauge can be attached to monitor seal leakage.At the Trojan plant, the qualified
life of the seal had not been accurately
established.
The simultaneous
effects of corrosion
and moisture at normal temperature
had not been taken into account. The established
longevity
was not corrected
after factoring
in the actual degradation
observed during periodic surveillance
of the individual
seals.' Also, an administrative
mechanism
was not in place to replace the seals before their estimated qualified
life expired. The original seal material in the Bunker-Ramo
electrical
penetration
assembly has polyesterurethane
manufactured
by Parker Packing Company (Parker) under the trade name of Parkerthane (Parker Compound No. P4611). Parker, which manufactures
both polyester
urethane and polyether urethane seals, indicated
in its catalog that polyester
urethane maintains critical characteristics
up to 6 years while polyether
urethane maintains critical characteristics
up to 10 years.The polyester
urethane (the originally
installed
seal material)
was determined
inadequate
for several reasons: Short expected life (independently
estimated
at 2-5 years under some conditions)
Incompatibility
with water (hydrolysis
shortens life)Incompatibility
with high temperature (acceleration
of hydrolysis)
Susceptibility
to compression-set (a slowly acquired permanent deformation)
The licensee used different
lubricants
over the years. In 1987, the licensee determined
that three seals had failed because they were erroneously
lubricated
with an incompatible (silicone)
grease. After examination
of seal failures that occurred in 1991, Parker determined
that the failed seals had castor oil residue on the exterior, indicative
of the use of Celvacene lubricant', which'includes
castor oil and cellulose
acetate butyrate.Celvacene, specified
for use by the original penetration
supplier, can cause
IN 93-25 April 1, 1993 degradation
of polyurethane
as follows. The cellulose
acetate butyrate component
breaks down in the presence of moisture, producing
butyric acid, which in turn catalyses
hydrolysis
of the seal polymer. The hydrolysis
slowly degrades the polyurethane
material.
Under accident conditions, the seal degradation
may be accelerated.
The original penetration
supplier, Bunker-Ramo, no longer supplies such assemblies.
Similar electrical
penetration
assemblies
have been supplied by Amphenol, but this company also no longer supplies such assemblies.
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:
C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment:
List of Receitly Issued NRC Information
Notices
14 Attachment
IN 93-25 April 1, 1993 Page I of I LIST OF RECENTLY ISSUED KRC INFORMlATION
NOTICES a 4c 40L '0 I UJ :3 0 A.UflU Inrormation
Notice No.93-24 93-23 93-22 93-21 93-20 93-19 93-18)93-17 93-16 Subject Distribution
of Revision 7 of PURE6-1021.
0Operator
Licensing Examiner Standards" Weschler Instruments
Nodel 252 Switchboard
Peters Triping of Klockner-Nfoeller Molded-Case
Circuit Breakers due to Support Level Failure Summary of NRC Staff Observations
Compiled during Engineering
Audits or Inspections
of Licen-see Erosion/Corrosion
Programs Thermal Fatigue Cracking of Feedwater
Piping to*Steam Generators
Slab Hopper Bulging Portable Moisture-Density
Gauge User Responsibilities
during Field Operations
Safety Systems Response to Loss of Coolant and Loss of Offs1te Power Failures of Nut-Locking
Devices in Check Valves Issuane Issued to 03/31/93 All holders of orater and senior operator eienses at nuclear power reactors.03/31/93 All holders of OLs or CPs for nuclear power reactors.03/26/93 All holders of OLs or CPs for nuclear power reactors.03/25/93 All holders of OLs or CPs for light water nuclear power reactors.I i 03/24/93 All holders of OLs or CPs for PWRs supplied by Westinghouse
or Combustion
Engineering.
03/17/92 All nuclear fuel cycle licensees.
03/10/93 All U.S. Nuclear Regulatory
Commission
licensees
that possess moisture-density
gauges.03/08/93 All holders of OLs or CPs for nuclear power reactors.02/19/93 All holders of OLs or CPs for nuclear power reactors.2 I(00 00 W O 1 c1 n 2 IL I-I U 4): zU Z a FA.~OL -Operating
License CP -Construction
Permit
IN 93-25 April 1, 1993 degradation
of polyurethane
as follows. The cellulose
acetate butyrate component
breaks down in the presence of moisture, producing
butyric acid, which in turn catalyses
hydrolysis
of the seal polymer. The hydrolysis
slowly degrades the polyurethane
material.
Under accident conditions, the seal degradation
may be accelerated.
The original penetration
supplier, Bunker-Ramo, no longer supplies such assemblies.
Similar electrical
penetration
assemblies
have been supplied by Amphenol, but this company also no longer supplies such assemblies.
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.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment:
List of Recently Issued NRC Information
Notices*SEE PRMV a CONCURRENCES
GHMarcus TechEd 03/05/93 04/13/92*D/DRIL:NRR
CERossi 03/03/93*C/RVIB:DRIL:NRR
LJNorrholm
02/27/93*OGCB: DORS:NRR CVHodge 06/03/92*RESINSP/RV
RBarr 06/03/92*RVIB:DRIL:NRR
KNaidu 01/11/93*SC/RVIB:DRIL:NRR
GCwallna 02/27/93 DOCUMENT NAME: 93-25.IN
IN 93-XX March xx, 1993 castor oil residue on the exterior, indicative
of the use of Celvacene lubricant, which includes castor oil and cellulose
acetate butyrate.Celvacene, specified
for use by the original penetration
supplier, can cause degradation
of polyurethane
as follows. The cellulose
acetate butyrate component
breaks down in the presence of moisture, producing
butyric acid, which in turn catalyses
hydrolysis
of the seal polymer. The hydrolysis
slowly degrades the polyurethane
material.
Under accident conditions, the seal degradation
may be accelerated.
The original penetration
supplier, Bunker-Ramo, no longer supplies such assemblies.
Si ilar electrical
penetration
assemblies
have been supplied by Amphenol6w-butThis
company also no longer supplies such assemblies. -A 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:
C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment:
List of Recently Issued NRC Information
Notices Document Name: PRESBOUN.IN
- SEE PREVIOUS CONCURRENCES
D/DORS:NRR
BKGrimes 03/ /93U*C/OGCB:DORS:NRR*RPB:ADM
C/RVIB:DRIL:NRR
GHMarcus TechEd CERossi LJNorrholm
03/05/93 04/13/92 03/03/93 02/271/93*OGCB:DORS:NRR
CVHodge RBarr KNaidu GCwalina 06/03/92 06/03/92 01/11/93 02/27/93 IN 93-XX March xx, 1993 degradation
of polyurethane
as follows. Ihe cellulose
acetate butyrate ccuponent
breaks dawm in the presence of irsture, producing
butyric acid, whici in turn catalyses
hydrolysis
of the seal polymer. The hydrolysis
slowly degrades the polyurethane
material.
Mier accident cmditins,, the seal degradation
may be accelerated.
The original penetration
supplier, Bunker-Ramo, is no longer in the business.Similar electrical
penetraticn
assemblies
have been splied -by Anphenol, but this ccapany also is no lcnger in the hksiness.
Ihe licensee at Trojan replaced its Eunker-Ramo
electrical
penetration
assemblies
with Ckmax electrical
penetration
assemblies.
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 aPqrcpriate
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Cperating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naid, NRR (301) 504-2980 Attachment:
List of Recently Issued NR Information
Notices D x:mnt Name: PRESBCEXI
IN*SEE PREVIOUS aONCNRRENcS
D/DORS:NRR
C/OGCB:DORS:MMR*RPB:ADM
BI~rimes Grfrcus64W
Tech~d CEossi 02/ /93 03/S /93 04/13/92 03/03/93*OGCB:DORS:NRR
- REV :RI:NR:R *SC/RVIB:DR:M;R*C/RIB:WIL:NRR
CvHodge RBarr .Naidu Gwalina mJ~orrhobii
06/03/92 06/03/92 01/11/93 02/27/93 02/27/93
-IN 93-XX February xx, 1993 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: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment:
List of Recently Issued NRC Information
Notices Document Name: PRESBOUN.IN
- SEE PREVIOUS CONCURRENCES
CVHodge 06/03/92 D/DORS:NRR
BKGrimes 02/ /93*RESINSP/RV
RBarr 06/03/92 C/OGCB:DORS:NRR*RPB:ADM
GHMarcus TechEd 02/ /93 04/13/92*RVIB:DRIL:NRR
SC/RVIB:DRIL:NRR
KNaidu GCwalina 01/11/93 02/ /93 CYRU:DRIL:NRR
LJNorrholm
02/ /93 IN 93-XX January xx, 1993 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: C. Vernon Hodge, (301) 504-1861 NRR Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachment:
List of Recently Issued NRC Information
Notices Document Name: PRESBOUN.IN
- SEE PREVIOUS*OGCB: DORS:NRF CVHodge 06/03/92 CONCURRENCES
D/DORS:NRR
BKGrimes 01/ /93 Z *RESINSP/RV
RBarr 06/03/92 C/OGCB:DORS:NRR*RPB:ADM
GHMarcus TechEd 01/ /93 04/13/92*RVIB:DRIL:NRR
IB:DRIL:NRR
KNaidu Gaina 01/11/93 /93 D/DRIL:NRR
C--#-CERossi g gmlL:NRR 01/j /93 DD:DRIL:NRR
RZimmerman
01/ /93 IN 93-XX January , 1993 ., under loss of coolant accident (LOCA) conditions.
Premature
degradation
of the insulation
covering the electrical
connections
can expose the connections
to an adverse environment
during a LOCA. A brief survey of these LERs is included in Attachment
1.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
Off ce of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Office of Nuclear Reactor Regu Support lation Technical
contacts: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal (301)Naidu, NRR 504-2980 Attachments:
1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information
Notices Document Name: PRESBOUN.IN
- SEE PREVIOUS CONCURRENCES
CVHodge USA RBarr 06/03/92 0413 06/03/92 D/DORS:NRR
BKGrimes 01/f /93! n IB:DRIL:NRR
KNai du 01/11/93 C/OGCB:DORS:NRR*RPB:ADM
GHMarcus TechEd 01/ /93 04/13/92 C/RVIB:DRIL:NRR
D/DRIL:NRR
LJNorrholm
CERossi 01/ /93 01/ /93..I zi' k I '. ,.-: I , :
K>IN 93-XX January xx, 1993 identify excessive
leakage of EPA seals indicating
possible degradation
from moisture intrusion.
Degraded seals can cause breach of containment
integrity under loss of coolant accident (LOCA) conditions.
Premature
degradation
of the insulation
covering the electrical
connections
can expose the connections
to an adverse environment
during a LOCA. A brief survey of these LERs is included in Attachment
1.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: C. Vernon Hodge, NRR (301) 504-1861 Robert C. Barr, Region V (509) 377-2627 Kamal Naidu, NRR (301) 504-2980 Attachments:
1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information
Notices Document Name: PRESBOUN.IN
- SEE PREVIOUS CONCURRENCES
OGCB:DORS:NRR
CVHodge V@06/o3/92 01 /Iq/3 D/DORS:NRR
BKGrimes 01/ /93 RESINSP/RV
RBarr w C/OGCB:DORS:NRR*RPB:ADM
GHMarcus TechEd 01/ /93 04/13/92*RVIB:DRIL:NRR
SC/RVIB:DRIL:NRR
KNaidu GCwalina 01/11/93 01/ /93 D/DRIL:NRR
CERossi 01/ /93 C/RVIB:DRIL:NRR
LJNorrholm
01/ /93 of EPA seals represent
violations
of Containment
integrity
and environmental
qualification
deficiencies
in EPA components
indicatepe
s m -/~u4n-deiiP
coddia")loss~bf(oolant
accident (LOCA) co'nditions.
A brief survey of these LERs I4B'Cincluded
in .ttachmet
A im This information
notice requires you have any questions
about the of the technical
contacts listed Reactor Regulation (NRR) project no specific action or written response.
If information
in this notice, please contact one below or the appropriate
Office of Nuclear manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
contacts: Vern Hodge, NRR (301) 504-1861 Rob Barr, RV (503) 556-3751 Attachments:
1. Survey of Licensee Event Reports (LERs)2. List of Recently Issued NRC Information
Notices Document Name: BUNK0403 REV 19 OGCB:DOEA:NRR
CVHodge 04/ /92 RESINSP/RV
RBarr 04/ /92 D/DOEA:NRR
CERossi 04/ /92 RVIB:DRIS:NRR
KNaidu 04/ /92 C/OGCB:DOEA:NRR
CHBerlinger
04/ /92 RPB:ADM TechEd J'Ma;, )04/13 /92 ROAB:DSP:NRR
SMazumdar 04/ /92
|
---|
|
list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay, Thermal fatigue)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
---|