Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1ML031060227 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
03/01/1996 |
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From: |
Crutchfield D Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-96-014, NUDOCS 9602260117 |
Download: ML031060227 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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 [[: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 [[: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 March 1, 1996 NRC INFORMATION NOTICE 96-14: DEGRADATION OF RADWASTE FACILITY EQUIPMENT AT
MILLSTONE NUCLEAR POWER STATION, UNIT 1
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 discuss degradation of radwaste facility equipment at Millstone
Nuclear Power Station, Unit 1. 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
During a routine NRC inspection at Millstone, inspectors found that the Unit 1 radwaste facility equipment was significantly degraded, especially vessels and
piping in the facility. In general, a lack of continuing and preventive
maintenance appeared to have allowed several systems and components to
significantly degrade, in some instances creating unnecessary adverse
radiological conditions. Piping located in the mezzanine areas above the "C"
and 'DI floor drain collector tanks were notably rusted, with a dusting of
flaked-off paint and rust deposited across all horizontal surfaces in this
area. Inspectors also noted the degraded condition of several valve bodies
and pipe flanges in the radwaste system. Three areas in this facility (the
filter sludge tank room, the spent resin tank room, and the evaporator
concentrates tank room) were sealed off because of radiological conditions.
In the case of the filter sludge and spent resin tank rooms, these facilities
are still in use and have temporary hoses passing through hand-stacked block
walls to make the connections from these vessels to the waste processing
systems in the Unit 1 waste processing buildings. The concentrates tank room
was no longer in use, the last of the concentrates having been processed and
disposed of in accordance with a licensee commitment to the NRC in 1990. A
video tape taken in November 1994 during the last manned entry into the filter
sludge tank room indicated that a crack in the filter sludge tank led to the
dispersal of highly radioactive spent filter sludge throughout the tank room.
Discussions with licensee staff members indicated that a similar condition
exists in the spent resin tank room, which in this case is caused by the
overfill of the spent resin tank.
BR Ik f E_ posertk- 79-01 Li 963e
9602260117
v-' IN 96-14 March 1, 1996 Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of antiquated processing and system control. The continued use of powdered
filters, in addition to the problem previously identified with regard to the
material condition of the sludge tank, has resulted in poor water quality
throughout this system and the generation of unnecessary wastes.
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee's
program. Subsequently, the NRC Region I Office has requested the licensee
submit a description of its plans to improve the conditions in these radwaste
areas.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
[Original signed by]
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: 96-14.IN
Tech Editor has reviewed and concurred as of 01/29/96
- SEE PREVIOUS CONCURRENCES
Ta receiv, a copy of tfle docurnent. ndicate In the box: 'C' - Copy without enclosures
'E' - Copy with enclosures N - No copy
OFFICE PECB/DRPM PEBDRPM _ C PECB:DRPM D:D
NAME EWang* CMiller* AChaffee* DCrifflh1 eld
DATE 02/23/96 02/23/96 02/23/96 02 W /96 OFFICIAL RECORD COPY
, I..
Attachment
IN 96-14 March 1, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-13 Potential Containment 02/26/96 All holders of OLs or CPs
Leak Paths Through for nuclear power reactors
Hydrogen Analyzers
96-12 Control Rod Insertion 02/15/96 All holders of OLs or CPs
Problems for nuclear power reactors
96-11 Ingress of Demineralizer 02/14/96 All holders of OLs or CPs
Resins Increases Potential for pressurized water
Stress Corrosion Cracking nuclear power reactors
of Control Rod Drive
Mechanism Penetrations
96-10 Potential Blockage by 02/13/96 All holders of OLs or CPs
Debris of Safety System for nuclear power reactors
Piping Which is Not Used
During Normal Operation
or Tested During Surveil- lances
96-09 Damage in Foreign Steam 02/12/96 All holders of OLs or CPs
Generator Internals for pressurized water
reactors
96-08 Thermally Induced Pres- 02/05/96 All holders of OLs or CPs
sure Locking of a High for nuclear power reactors
Pressure Coolant Injec- tion Gate Valve
96-07 Slow Five Percent Scram 01/26/96 All holders of OLs or CPs
Insertion Times Caused for boiling water reactors
By Viton Diaphragms in
Scram Solenoid Pilot
Valves
96-06 Design and Testing 01/25/96 All holders of OLs or CPs
Deficiencies of Tornado for nuclear power reactors
Dampers at Nuclear Power
Plants
OL = Operating License
CP = Construction Permit
IN 96-14 March 1, 1996 Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of antiquated processing and system control. The continued use of powdered
filters, in addition to the problem previously identified with regard to the
material condition of the sludge tank, has resulted in poor water quality
throughout this system and the generation of unnecessary wastes.
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee's
program. Subsequently, the NRC Region I Office has requested the licensee
submit a description of its plans to improve the conditions in these radwaste
areas.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
[Original signed by]
Dennis M. Crutchfield, Director
AI14 X SS J L4 Division of Reactor Program Management
P ffIce of Nuclear Reactor Regulation
Technical contact: Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw~nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: 96-14.IN
Tech Editor has reviewed and concurred as of 01/29/96
- SEE PREVIOUS CONCURRENCES
To receive a copy of ths document, Idicate in the box: c' - Copy without enclosures
E'- Copy with enclosures 'N . No copy
OFFICE PECB/DRPM PERB/DRPC PECB:DRPM D:D
NAME EWang* CMiller* l AChaffee* DCrtfi el dl
DATE 022/602/23/96 l02/23/96 02/ W /96l
OFFICIAL RECORD COPY
-'~ IN 96-xx
February xx, 1996 Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of antiquated processing and system control. The continued use of powdered
filters, in addition to the problem previously identified with regard to the
material condition of the sludge tank, has resulted in poor water quality
throughout this system and the generation of unnecessary wastes.
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee's
program. Subsequently, the NRC Region I Office has requested the licensee
submit a description of its plans to improve the conditions in these radwaste
areas.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact 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 contact: Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw~nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: G:\EYW\96-XX-IN.RAD
To receive a copy of this document Indicate hI the box: 'C - Copy without enclosures
'E- Copy with enclosures 'N - No copy
OFFICE PECB/DRPt I PERB/DRPM C Pi:DRPM D:DRPMI
NAME IEWang AK I 1 AChaffee
Mer DCrAtchfLeld
DATE l02 A 39(tZiJ02,5 /96 02/,23 /96 PS;6 02/ /96
. OFFICIAL RECORD COPY
IN 96-14 March 1, 1996 Subsequent licensee investigation determined that in the evaporator "A" room, a pile (approximately 50 cubic feet) of spent resin was on the floor, as well
as dried evaporator concentrates. Dried evaporator concentrates were also
found in the "A" and "B" concentrated tank room.
Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of processing and system control. The continued use of powdered filters, in
addition to the problem previously identified with regard to the material
condition of the sludge tank, has resulted in the generation of unnecessary
wastes.
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee program.
Subsequently, the NRC Region I Office has requested the licensee submit a
description of its plans to improve the conditions in these radwaste areas.
Additional information is also found in Appendix B to NRC Inspection Report
50-245/95-38; 50-336/95-38; 50-423/95-38.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contacts listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
original signed by
Dennis M. Crutchfield, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Joseph T. Furia, RI
(610)-337-5041 Internet:jtf@nrc.gov
Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: 96-14.IN
Tech Editor has reviewed and concurred as of 01/29/96 To receive a copy of this document, indicate In the box: ACT Copy without enclosures
E' -Copy with enclosures "N" - No copy
OFFICE PECB/DRPM PERB/DRPM C/PECB:DRPM D:DRP~
NAME EWang !(A-A1 CMiller X AChaffee Kruftgftd
DATE 02/ 4/96 02/ /96 02/ /96 001 /96 OFFICIAL RECORD COPY e
5So acXed Con0curredv- Ra X4t111
'
TtLr ic
50C -tartJ-
From: Joseph Furia
To: WND2.WNP4(EYW)
Date: 2/29/96 3:00pm
Subject: IN 96-14, Millstone Radwaste Issue -Reply
The changes look good. Consider this my concurrence.
Joe
IN 96-14 March 1, 1996 Subsequent licensee investigation determined that in the evaporator "A" room, a pile (approximately 50 cubic feet) of spent resin was on the floor, as well
as dried evaporator concentrates. Dried evaporator concentrates were also
found in the 'A' and "B" concentrated tank room.
Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of processing and system control. The continued use of powdered filters, in
addition to the problem previously identified with regard to the material
condition of the sludge tank, has resulted in the generation of unnecessary
wastes.
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste-systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee program.
Subsequently, the NRC Region I Office has requested the licensee submit a
description of its plans to improve the conditions in these radwaste areas.
Additional information is also found in Appendix B to NRC Inspection Report
50-245/95-38; 50-336/95-38; 50-423/95-38.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
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: Joseph T. Furia, RI
(610)-337-5041 Internet:jtf@nrc.gov
Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: 96-14.IN
Tech Editor has reviewed and concurred as of 01/29/96 To receive a copy of this document. Indicate In the box: 'C' Copy without enclosures
'E', Copy with enclosures 'N' - No copy
OFFICE PECB/DRPM PERB/DRPM l C/PECB:DRPM D:DRPM
lNAME EWang L4A-' CMiller <etrhAChaffee DCrutchfield
IDATE 102/196 _/L /96 02/ /96 02/ /96 I OFFICIAL RECORD COPY
IN 96-14 March 1, 1996 Subsequent licensee investigation determined that in the evaporator "A" room, a pile (approximately 50 cubic feet) of spent resin was on the floor, as well
as dried evaporator concentrates. Dried evaporator concentrates were also
found in the "A" and "B" concentrated tank room.
Discussion
Although the licensee was recently able to significantly reduce the amount of
spent resins and other media generated as a result of the replacement of the
main condenser, large volumes of other resins continue to be generated because
of processing and system control. The continued use of powdered filters, in
addition to the problem previously identified with regard to the material
condition of the sludge tank, has resulted in the generation of unnecessary
wastes. I
In NRC Inspection Report, 50-245/95-35; 50-336/95-35; 50-423/95-35, dated
September 11, 1995, NRC Accession Number 9509180222, the degraded condition of
the radwaste systems, resulting from a general lack of appropriate
maintenance, was identified as a significant weakness in the licensee program.
Subsequently, the NRC Region I Office has requested the licensee submit a
description of its plans to improve the conditions in these radwaste areas.
Additional information is also found in Appendix B to NRC Inspection Report
50-245/95-38; 50-336/95-38; 50-423/95-38.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
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: Joseph T. Furia, RI
(610)-337-5041 Internet:jtf@nrc.gov
Egan Y. Wang, NRR
(301) 415-1076 Internet:eyw~nrc.gov
Attachment: List of Recently Issued NRC Information Notices
File name: 96-14.IN
Tech Editor has reviewed and concurred as of 01/29/96 To receive a copy of this document, Indicate in the box: ACE " Copy without enclosures
'E' - Copy with enclosures 'N' - No copy
OFFICE PECB/DRPM \ PERB/DRPM C/PECB:DR@A D:DRPM
INAME EWang i.( L'y CMiller = AChaffeeT IDCrutchfield
DATE 02a/96 02/ /96 02/ /96 02/ /96 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)
- 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)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- 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)
- 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)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- 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: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- 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)
- 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: Nondestructive 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)
- 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, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- 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)
... further results |
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