Electrical Penetration Assembly DegradationML031080020 |
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: |
04/01/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-93-025, NUDOCS 9303250146 |
Download: ML031080020 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 a
IN 93-25 4c
April 1, 1993 Page I of I
40L '0
LIST OF RECENTLY ISSUED
INFORMlATION NOTICES
KRC
I UJ :3 UflU U
Inrormation
Notice No. Subject Issuane Issued to
0
Distribution of 03/31/93 All holders of orater and A.
93-24 Revision 7 of PURE6-1021. senior operator eienses at
0Operator Licensing nuclear power reactors.
Examiner Standards"
93-23 Weschler Instruments 03/31/93 All holders of OLs or CPs
Nodel 252 Switchboard for nuclear power reactors.
Peters
93-22 Triping of Klockner- 03/26/93 All holders of OLs or CPs
Nfoeller Molded-Case for nuclear power reactors.
Circuit Breakers due to
Support Level Failure
93-21 Summary of NRC Staff 03/25/93 All holders of OLs or CPs
Observations Compiled for light water nuclear
during Engineering Audits power reactors.
or Inspections of Licen- see Erosion/Corrosion
Programs
I
03/24/93 All holders of OLs or CPs i
93-20 Thermal Fatigue Cracking
of Feedwater Piping to for PWRs supplied by
- Steam Generators Westinghouse or Combustion
Engineering.
93-19 Slab Hopper Bulging 03/17/92 All nuclear fuel cycle
licensees.
93-18 Portable Moisture-Density 03/10/93 All U.S. Nuclear Regulatory 2 Gauge User Responsibilities Commission licensees that
I(00
) during Field Operations possess moisture-density
gauges. 00
93-17 Safety Systems Response 03/08/93 All holders of OLs or CPs W O
to Loss of Coolant and for nuclear power reactors. 1c1 Loss of Offs1te Power
93-16 Failures of Nut-Locking 02/19/93 All holders of OLs or CPs
Devices in Check Valves for nuclear power reactors.
IL I
-IU
4):
zU
OL - Operating License n 2 Z a
FA.~
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
- 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 02/27/93
- OGCB: DORS:NRR *RESINSP/RV *RVIB:DRIL:NRR *SC/RVIB:DRIL:NRR
CVHodge RBarr KNaidu GCwallna
06/03/92 06/03/92 01/11/93 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
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 GwalinamJ~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
D/DORS:NRR C/OGCB:DORS:NRR*RPB:ADM
BKGrimes GHMarcus TechEd
02/ /93 02/ /93 04/13/92
- OGCB:DORS:NRR *RESINSP/RV *RVIB:DRIL:NRR SC/RVIB:DRIL:NRR CYRU:DRIL:NRR
CVHodge RBarr KNaidu GCwalina LJNorrholm
06/03/92 06/03/92 01/11/93 02/ /93 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, 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 C/OGCB:DORS:NRR*RPB:ADM D/DRIL:NRR C--#-
BKGrimes GHMarcus TechEd CERossi
01/ /93 01/ /93 04/13/92
- OGCB: DORS:NRFZ *RESINSP/RV *RVIB:DRIL:NRR IB:DRIL:NRR 01/jg gmlL:NRR
/93 CVHodge RBarr KNaidu Gaina
06/03/92 06/03/92 01/11/93 /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 Support
Office of Nuclear Reactor Regu lation
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
D/DORS:NRR C/OGCB:DORS:NRR*RPB:ADM
BKGrimes GHMarcus TechEd
01/f /93 01/ /93 04/13/92
- OGCB:DORSONRR *RESINSP/RV ! n IB:DRIL:NRR C/RVIB:DRIL:NRR D/DRIL:NRR
CVHodge USA RBarr KNai du LJNorrholm CERossi
06/03/92 0413 06/03/92 01/11/93 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
D/DORS:NRR C/OGCB:DORS:NRR*RPB:ADM D/DRIL:NRR
BKGrimes GHMarcus TechEd CERossi
01/ /93 01/ /93 04/13/92 01/ /93 OGCB:DORS:NRR RESINSP/RV *RVIB:DRIL:NRR SC/RVIB:DRIL:NRR C/RVIB:DRIL:NRR
CVHodge V@ RBarr w KNaidu GCwalina LJNorrholm
06/o3/92 01/11/93 01/ /93 01/ /93
01 /Iq/3
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'
in .ttachmet Cincluded
A im
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.
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 D/DOEA:NRR C/OGCB:DOEA:NRR
CERossi CHBerlinger
04/ /92 04/ /92 OGCB:DOEA:NRR RESINSP/RV ROAB:DSP:NRR RVIB:DRIS:NRR RPB:ADM
CVHodge RBarr SMazumdar KNaidu TechEd J'Ma;, )
04/ /92 04/ /92 04/ /92 04/ /92 04/13 /92
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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)
- 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)
- 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)
- 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)
- 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 |
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