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
K>I 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 96-22 96-21 96-20 Fires in Emergency
Diesel Generator
Exciters During Operation
Following
Unde-tected Fuse Blowing Improper Equipment
Set-tings Due to the Use of Nontemperature-Compensated
Test Equipment Safety Concerns Related to the Design of the Door Interlock
Circuit on Nucletron
High-Dose
Rate and Pulsed Dose Rate Remote Afterloading
Brachytherapy
Devices Demonstration
of Associ-ated Equipment
Compliance
with 10 CFR 34.20 Failure of Tone Alert Radios to Activate When Receiving
a Shortened Activation
Signal Compliance
with 10 CFR Part 20 for Airborne Thorium Loss of Reactor Coolant Inventory
and Potential Loss of Emergency
Mitiga-tion Functions
While in a Shutdown Condition 04/22/96 04/11/96 04/10/96 04/04/96 04/02/96 03/25/96 03/25/96 All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All U.S. NRC Medical to the Licensees
authorized
to use brachytherapy
sources in high- and pulsed-dose-rate
remote afterloaders
All industrial
radiography
licensees
and radiography
equipment
manufacturers
All holders of OLs or CPs for nuclear power reactors All material licensees authorized
to possess and use thorium in unsealed form All holders of OLs or CPs for PWR power plants 96-19 96-18 95-03 Supp. 1 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
- 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 (301) 415-2783 Internet:
skmlnrc.gov
Christopher
Myers, RIV (817) 860-8144 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 To receive a copy of this document.
Indicate In the box: Tech Editor reviewed 9/21/95'C' -Copy without enclosures
fEw -Copy wi th enclosures
'N' -No copy OFFICE IContacts
C/EELB I D/DRPI l NAME CMyers
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 (301) 415-2783 Internet:
skmlnrc.gov
Christopher
Myers, RIV (817) 860-8144 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 copylOFFICE Contacts I C/EELB l C/PECB I DRPM I NAME CMyers
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 (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 T - 5 .LL.1. .I *k. i hn,.. tC = -Cnnu without enclosures
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- wprs r^uumn, juciva lwi'Jw. --r,. ...........................
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=E' CoDv with enclosures
'N' = No copy 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 (817) 860-8145 Christopher
Myers, RIV (817) 860-8144 Stephen Alexander, NRR (301) 415-2995 Sikhindra
Mitra, (301) 415-2783 NRR Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: 95-XX.IN To receive a copv ol this document.
indicate In the box: C -Coov without enclosures
- .See previous concurrence-E' .CoDV with enclosures "N" -No coDYlOFFICE RI Tf RI E _I I BDS 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 (817) 860-8145 Christopher
Myers, (817) 860-8144 RIV 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 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_ _ _w n SAlexander
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
IZ C: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 RIYE RIV 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//95 OFFICIAL RECORD COPY
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 a nv Cf thids donument.
indicate In the box:* .See previous concurrence
'C' -Coov without enclosures
'E' -Copy with enclosures
'N' .No copy To rAceivA OFFICE RIV l1 El t E RE R E RIV I E lPSIB:DISP
I E NAME TWesterman
CMyers ISAlexander
DATE / /95 I /95 / /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 Nuclear Reactor Regulation (NRR) project manager.appropriate
Office of 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 To receive a copy of this document.
Indicate In the box:* = See previous concurrence
wEd -Copy with oncosurss
rW -No copy NCR -Copy without endosurms 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(g fIq / /95 / /95 /95 / /95 OFFICE PECB:DRPM
C:PECB:DRPM
DD:DRPM NAME 1AChaffee
BKGrimes _ lDATE/ /95 1 / /95 / /95 II 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: Eddy Current Testing, 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, Topic: Stress corrosion cracking)
- 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, Topic: Stress corrosion cracking)
- 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, Overspeed)
- 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)
- 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)
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