Preconditioning of Molded-Case Circuit Breakers Before Surveillance TestingML031060110 |
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: |
04/25/1996 |
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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-96-024, NUDOCS 9604220229 |
Download: ML031060110 (14) |
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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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 April 25, 1996 NRC INFORMATION NOTICE 96-24: PRECONDITIONING OF MOLDED-CASE CIRCUIT BREAKERS
BEFORE SURVEILLANCE TESTING
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the detrimental effect that preconditioning of
molded-case circuit breakers could have on the diagnostic validity of
surveillance tests. It is expected that recipients will review this
information for applicability to their facilities and consider actions, as
appropriate, to avoid similar problbms. However, suggestions contained in
this information notice are not NRC requirements; therefore, no specific
action or written response is required.
DescriDtion of Circumstances
During an inspection at the Diablo Canyon Nuclear Power Plant (IR 50-275,
323/94-27 dated December 21, 1994), NRC inspectors noted that the licensee
preconditioned circuit breakers before performing surveillance testing.
Before the overcurrent trip testing, Diablo Canyon staff exercised the circuit
breakers by manually opening and closing them three times. The plant staff
'did not record the as-found condition of the breakers in terms of unexercised
trip currents and times.
During another inspection at the South Texas Project (IR 50-498, 499/94-35 dated January 19, 1995), NRC inspectors noted that the licensee exercised
similar circuit breakers manually at least five times before testing the
overcurrent trip unit.
Discussion
A molded-case circuit breaker is one of the most widely used protective
devices for electrical circuits at nuclear power plants. Its proper operation
is essential for the protection and safe operation of plant electrical
equipment. Many circuit breakers are continuously energized for long periods.
Often they are in service for years and are rarely, if ever, called upon to
perform a protective function. Nevertheless, when needed, they must rapidly
isolate a faulted or overloaded circuit to prevent equipment damage.
Therefore, for the safe operation of the electrical distribution system
equipment of a nuclear power plant, it is important to periodically verify
their continued reliability.
.K
VE uor~cEya-0OZ %6qZ 'I
I
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IN 96-24 April 25, 1996 Periodic inspection and testing of circuit breakers in their as-found
condition is an appropriate way of demonstrating the functional operability of
the breaker and of detecting any degradation. However, the practice of
preconditioning before testing (e.g., lubricating pivot points and manually
cycling the breaker) defeats the purpose of the periodic test. Such
preconditioning does not confirm continued operability between tests nor does
it provide information on the condition of the circuit breaker for trending
purposes. Testing some circuit breakers in the as-found condition can provide
useful data on which to base decisions on surveillance intervals and the
ability of the untested circuit breakers to perform their intended function.
Since only a fraction of the circuit breakers are tested each refueling outage
to justify the operability of the remaining circuit breakers, preconditioning
before testing does not provide the expected assurance of the operability of
remaining breakers which are not tested. By preconditioning circuit breakers, useful information may be lost because the breaker may not have been capable
of performing its intended function without preconditioning.
To correct this situation, Diablo Canyon Power Plant plans to revise the
electrical maintenance procedure before the next surveillance test has to be
performed. The revised procedures will state that electrical testing should
be performed before any intentional manual exercising of the breakers, and to
ensure that electrical testing on breakers with removable trip units is
performed before removing the trip unit.
Some plants have older technical specification bases that cite National
Electrical Manufacturers Association (NEMA) Standard AB 2-1980. This version
of the standard specifies mechanical cycling of circuit breakers prior to
electrical testing. In later versions of this standard, this procedure was
deleted. There appears to be no valid technical need for mechanical cycling
prior to electrical surveillance testing.
The NRC has issued other generic communications on molded-case circuit breaker
applications and testing: NRC Information Notice (IN) 92-51, and its
Supplement 1, "Misapplication and Inadequate Testing of Molded-Case Circuit
Breakers;" IN 93-26, "Grease Solidification Causes Molded Case Circuit Breaker
Failure to Close;" and IN 93-64, "Periodic Testing and Preventive Maintenance
of Molded-Case Circuit Breakers."
If I
IN 96-24 April 25, 1996 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. /a
L.."
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Sikhindra Mitra, NRR
(301) 415-2783 Internet:skml@nrc.gov
Steve Alexander, NRR
(301) 415-2995 Internet:sda@nrc.gov
Christopher Myers, RIV
(817) 860-8144 Internet:cjm@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
-tw@ / "Y
K
Attachment
IN 96-24 April 25, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-23 Fires in Emergency Diesel 04/22/96 All holders of OLs or CPs
Generator Exciters During for nuclear power reactors
Operation Following Unde- tected Fuse Blowing
96-22 Improper Equipment Set- 04/11/96 All holders of OLs or CPs
tings Due to the Use of for nuclear power reactors
Nontemperature-Compensated
Test Equipment
96-21 Safety Concerns Related 04/10/96 All U.S. NRC Medical to the
to the Design of the Door Licensees authorized to use
Interlock Circuit on brachytherapy sources in
Nucletron High-Dose Rate high- and pulsed-dose-rate
and Pulsed Dose Rate remote afterloaders
Remote Afterloading
Brachytherapy Devices
96-20 Demonstration of Associ- 04/04/96 All industrial radiography
ated Equipment Compliance licensees and radiography
with 10 CFR 34.20 equipment manufacturers
96-19 Failure of Tone Alert 04/02/96 All holders of OLs or CPs
Radios to Activate When for nuclear power reactors
Receiving a Shortened
Activation Signal
96-18 Compliance with 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed
form
95-03 Loss of Reactor Coolant 03/25/96 All holders of OLs or CPs
Supp. 1 Inventory and Potential for PWR power plants
Loss of Emergency Mitiga- tion Functions While in a
Shutdown Condition
OL = Operating License
CP - Construction Permit
K2 2 IN 96-24 April 25, 1996 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
original signed by
Brian K. Grimes, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Sikhindra Mitra, NRR
(301) 415-2783 Internet:skml@nrc.gov
Steve Alexander, NRR
(301) 415-2995 Internet:sda@nrc.gov
Christopher Myers, RIV
(817) 860-8144 Internet:cjm@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 96-24.IN Tech Editor reviewed 9/21/95 To receive a copy of this document, Indicate In the box: 'C' - Copy without enclosures 'E" = Copy with sncloRre -l = No copy
OFFICE Contacts C IEELB
NAME CMyers * JCalvo * AChatfee s
SMitra * /
SAlexander* 7 ,
DATE 4/22/96 4/15/96 4/22/96 4/LT/96 OFFICIAL RECORD COPY
IN 96-XX
April XX, 1996 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Sikhindra Mitra, NRR Christopher Myers, RIV
(301) 415-2783 (817) 860-8144 Internet: skmlnrc.gov Internet: cjm@nrc.gov
Steve Alexander, NRR
(301) 415-2995 Internet: sda@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN Tech Editor reviewed 9/21/95 To receive a copy of this document. Indicate In the box: 'C' - Copy without enclosures fEw - Copy with enclosures 'N' - No copy
OFFICE IContacts C/EELB D/DRPI lI
NAME CMyers * JCalvo * AChaffee DCrutchfield
SMitra *
SAlexanderLnfi_
DATE 4 /15/96 7' 4/15/96 4/ /96 4/ /96
. - - - - - - -
UICLIAL KECOKR COPY
,44
I 1 i
<-' IN 96-XX
April XX, 1996 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Sikhindra Mitra, NRR Christopher Myers, RIV
(301) 415-2783 (817) 860-8144 Internet: skmlnrc.gov Internet: cjm~nrc.gov
Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN Tech Editor reviewed 9/21/95 To receive a copy of this document, Indicate In the box: 'C' - Copy without enclosures 'E' - Copy with enclosures 'No = No copy
lOFFICE Contacts I C/EELB l C/PECB I DRPM I
NAME CMyers * JCalvo * AChaffee DCrutchfield
SMitra *
DATE 4 /I5/96 4/11 /96 4/ 4/ /96 OFFICIAL RECORD COPY
IN 96-XX
April XX, 1996 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Christopher Myers, RIV
(817) 860-8144 Sikhindra Mitra, NRR
(301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN Tech Editor reviewed 9/21/95 To receive a copy of this document. Indicate In the box: wCw = Copy without enclosures 'E" - Copy with enclosures 'N'= No copy
OFFICE Contacts C/EELB I
NAME Myers JCalvoJy r AChaffee DCrutchfield
I ~SMi tra_ _ _ _ _ _ _
DATE 4 /16796 4/ I7/96 4/ /96 4/ /96 OFFICIAL RECORD COPY
IN 96-XX
April xx, 1996 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Tom Westerman, RIV Christopher Myers, RIV
(817) 860-8145 (817) 860-8144 Stephen Alexander, NRR Sikhindra Mitra, NRR
(301) 415-2995 (301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * . See previous concurrence
T 5 .LL.1. .I i *k.hn,.. tC =-Cnnu without enclosures,
........................... =E' CoDv with enclosures 'N' = No copy
rcv r^uumn, juciva lwi'Jw. -r,.
OFFICE RIV liE RIV E lRIV l E RIV E PSIB:DISP E
NAME LTWesterman A CMyers k _ TP Gwyn* SAlexander
DATE I1/ g/95 t /,/95 / /95 01/25/95 / /95 OFFICE TECH ED N SC:SIB:DISP l EE:DE E SC:EELB:DE E C:EELB:DEl E
NAME WRSanders SKMitra 't ASGill* JACalvo*
DATE 109/21/95* / /95 41,1/2o%96 I/Y.1 09/21/95 9/27/95 OFFICE IPECB:DRPM PECB:DRPM PECB:DRPM I C:PECB:DRPM l D:DRPM
NAME JTKoshy EFGoodwin* AChaffee DMCrutchfield
DATE IJ/f/96 10/04/95 I /95 /95 /95 OFFICIAL RECORD COPY
IN 96-XX
January xx, 1995 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Tom Westerman, RIV Christopher Myers, RIV
(817) 860-8145 (817) 860-8144 Stephen Alexander, NRR Sikhindra Mitra, NRR
(301) 415-2995 (301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * . See previous concurrence
To receive a copv ol this document. indicate Inthe box: C - Coov without enclosures .
-E' CoDV with enclosures "N" - No coDY
lOFFICE RI Tf RI E I BDS _I
NAME TWesterman CMyers _ _ _ TP Gwyn* SAl exander
DATE / /95 1 I / /9 IL/5 01_/25/95 / /95 OFFICE lTECH ED N SC:SIB:DISP E EELB:DE E SC:EELB:DE I E lC:EELB:DEl E
NAME l RSanders SKMi tra ASGill* JJACalvo*
DATE l09/21/95* / /95 I / 1/96 09/21/95 9/27/95 OFFICE JIPECB:DRPM PECB:DRPM I C:PECB:DRPMl D:DRPM
NAME TKoshy EFGoodwin* AChaffee DMCrutchfi eld
DATE I /oF/9 _ 10/04/95 / /95 / /95 / /95 OFFICIAL RECORD COPY
IK 'I
IN 95-XX
September xx, 1995 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.
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Tom Westerman, RIV Christopher Myers, RIV
(817) 860-8145 (817) 860-8144 Stephen Alexander, NRR Sikhindra Mitra, NRR
(301) 415-2995 (301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * * See previous concurrence
Te raclva a etonw of thb document Indicate hI Om box: 'C' - Copv without enclosures 'E - Copy with enclosures 'N- - No copy
OFFICE R E RIV E R RIV E PSIB:DISP E
NAME TWesterman c CMyers / T/5 6_ n SAlexander
_ _w
DATE I /Teean/95 jC/1y/95 / /95 _ T/ZS/95 I /95 OFFICE TECH ED N SC:SIB:DISP l DEE E SC:EELB:DE E C:EELB:DE E
NAME RSanders SKMitra* ASGill* JACalvo*
DATE 09/21/95* / /95 09/20/95 09/21/95 / /95 OFFICE PECB:DRPM I E PECB:DRPM / l-JLIPEIBhRPM IZC:PECB:DRPM ID:DRPM
NAME TKoshy EFGoodwin RJK AChaffee DMCrutchfield
DATE 9/26/95 y 95 V // /95 / /95 OFFICIAL RECORD COPY
IN 95-XX
September xx, 1995 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, Deputy Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Tom Westerman, RIV
(817) 860-8145 Christopher Myers, RIV
(817) 860-8144 Stephen Alexander, NRR
(301) 415-2995 Sikhindra Mitra, NRR
(301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * , See previous concurrence
To receive a copy of this document. Indicate In the box: 'C' Copy without enclosures E' - Copy with enclosures N - No copy
OFFICE RIY I E RIY E RIV
RIYE E PSIB:DISP E
NAME TWesterman CMyers ____ _ SAlexander
DATE / /LE95 / /95 I /95 /95 / /95 OFFICE TECH ED I N SC:SIB:DISP E EELB:DE I E SC:EELB:DEl E C:EELB:DEI E
NAME RSanders SKMitra* ASGill* JACalvo I/ACj
DATE 09/21/95* / /95 09/20/95 09/21/95 f /17/95 qI~d'3 OFFICE PECB:DRPM l C:PECB:DRPM l DD:DRPM
NAME AChaffee BKGrimes
DATE I /95 / /95 l//
OFFICIAL RECORD COPY
i
IN 95-XX
August XX, 1995 one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Deputy Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Tom Westerman, RIV
(817) 860-8145 Christopher Myers, RIV
(817) 860-8144 Stephen Alexander, NRR
(301) 415-2995 Sikhindra Mitra, NRR
(301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * . See previous concurrence
To rAceivA a Cf nv donument. indicate Inthe box: 'C'
thids - Coov without enclosures 'E' - Copy with enclosures 'N' . No copy
l1El R EE RIV
RE I E lPSIB:DISP I E
OFFICE
NAME
DATE
RIV
TWesterman
/ /95 t
CMyers
I /95 ISAlexander
/ /95 /95 /95 OFFICE TECH ED N SC:SIB:DISP I E EELB:DE E SC:EELB-DE E C:EELB:DEl E
NAME BCalure SKMitra YOM& ASGill t JACalvo
DATE 08/03/95* j-/ /95 / O/95 /04/95 / /95 OFFICE PECB:DRPM l C:PECB:DRPMT DD:DRPM
NAME AChaffee BKGrimes
DATE I /95 / /95 / /95 OFFICIAL RECORD COPY
K-/
IN 95-XX
August XX, 1995 one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Deputy Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Tom Westerman, RIV
(817) 860-8145 Christopher Myers, RIV
(817) 860-8144 Stephen Alexander, NRR
(301). 415-2995 Sikhindra Mitra, NRR
(301) 415-2783 Attachment: List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-XX.IN * = See previous concurrence
To receive a copy of this document. Indicate In the box: NCR - Copy without endosurms wEd - Copy with oncosurss rW- No copy
OFFICE RIV I E RIY E RIV E RIV I E PSIB:DISP I E
NAME TWesterman CMyers I jSAlexander
DATE / /95 / /95 1/. /95 /95 / /95 OFFICE TECH ED N SC:SIB:DISP I E EELB:DE E SC:EELB:DE E C:EELB:DEI E
NAME BCalure K54a" 1SKMitra ASGill JACalvo I
DATE 08/03/95* gf(gfIq / /95 / /95 /95 / /95 OFFICE PECB:DRPM C:PECB:DRPM DD:DRPM
NAME
DATE/ /95 1
1AChaffee
/ /95 BKGrimes
/ /95 II
_ l
OFFICIAL RECORD COPY
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Commercial Grade, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996, Topic: Hardened grease)
... further results |
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