Potential Blockage of Safety-Related Strainers by Material Brought Inside ContainmentML031060375 |
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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
01/25/1995 |
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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-95-006, NUDOCS 9501190091 |
Download: ML031060375 (9) |
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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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Category:NRC Information Notice
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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 January 25, 1995 NRC INFORMATION NOTICE 95-06: POTENTIAL BLOCKAGE OF SAFETY-RELATED STRAINERS
BY MATERIAL BROUGHT INSIDE CONTAINMENT
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 (IN)to alert addressees to the potential blockage of safety-related
strainers by material brought inside containment. 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
On April 28, 1994, with the reactor in cold shutdown, the licensee for the
Palisades Nuclear Power Station (Palisades) determined that plastic material
used inside containment could block the containment sump screens after a
design basis accident. The licensee declared the high-pressure safety
injection pumps and the containment spray system pumps inoperable and began
thoroughly cleaning the containment to remove unnecessary material that could
contribute to the blockage of containment sump screens.
In April 1994, at the Grand Gulf Nuclear Station (Grand Gulf), engineering
personnel evaluated whether plastic wrap and similar materials used inside
containment could block safety-related strainers. The evaluation specifically
addressed the potential for a thin plastic film used to cover the personnel
shielding platform and the dryer/separator strongback to become dislodged by
containment spray during a loss-of-coolant accident (LOCA) and enter the
suppression pool and eventually block the emergency core cooling suction
strainers. The plastic film had been used to cover the equipment to prevent
the spread of loose surface contamination.
On October 10, 1994, at Browns Ferry Unit 2, divers inspecting the underwater
surfaces of the Unit 2 torus found numerous pieces of cloth-like material on
the bottom of the torus and on the surfaces of the emergency core cooling
strainers. The pieces were typically 25 square centimeters [4 square inches]
in size, but smaller pieces were also found. The divers made a videotape of
the as-found condition of one half of the torus. This included two of the
four emergency core cooling suction strainers inside the torus. The videotape
9501190091 PDR ITE NOfCotQ 95t*°O4 9
'I'
IN 95-06 January 25, 1995 showed that about 15 percent of the surface area of one strainer was covered
and a lesser amount of the second strainer. The material was later found to
be pieces of absorbent paper towels sometimes used inside containment for
maintenance and cleaning purposes.
Discussion
The events described above illustrate that plastic or fibrous material brought
inside containment may become a concern after a design basis accident. In
general, the material met the plant guidelines for material allowed inside
containment and was intentionally brought inside the containment to reduce the
spread of loose contamination, identify plant equipment, or for cleaning
purposes. The materials involved and the actions taken by the licensees are
further described as follows:
Palisades
Palisades employs a pressurized-water reactor with a large dry containment.
The licensee evaluated the use of adhesive labels and double-sided tape to
affix signs to walls and equipment or piping inside containment. The licensee
recognized that the high temperature and humidity that may result from a
design basis accident could loosen or dissolve the adhesive. The licensee
concluded that, in a worst case scenario in which all of the material became
dislodged and entered the containment sumps, the material would cause blockage
of recirculation flow of containment sump water and, thereby, could affect the
functioning of safety systems.
The licensee thoroughly cleaned the containment and removed about 9 square
meters [100 square feet] of unnecessary signs and adhesives including
nonessential vendor labels, duct tape, double-sided tape used to affix signs,
"Dymo-tape" labels, and tape used to identify plant equipment. After the
cleaning, less than .9 square meter [10 square feet] of material remained.
The licensee did an engineering analysis and found that the area of greatest
concern extended radially about 1.5 meters [5 feet] from the containment sump
downcomer for plastic signs and labels and about 3 meters [10 feet] for duct
tape. The licensee plans to develop a checklist for containment cleanliness
that addresses sump blockage from signs, labels, and tags affixed by adhesive
materials. The licensee will also develop a labeling standard that considers
the possibility for sump blockage from materials secured by adhesives.
Grand Gulf
Grand Gulf uses a boiling-water reactor (BWR) with a Mark III containment that
has an open suppression pool separated from the drywell by a weir wall. The
licensee had formed a task force to inspect for materials inside the
containment that could block the emergency core cooling strainers. The task
force was concerned that plastic film covering some of the refueling equipment
could be dislodged and block the strainers. The licensee removed the plastic
film from the dryer/separator strongback and is having a cover fabricated for
the strongback that will withstand LOCA conditions. The licensee determined
that, because of the location, the plastic film covering the personnel
IN 95-06 January 25, 1995 shielding platform could not be washed into the suppression pool; therefore
the plastic film was left in place and securely fastened to the platform. The
licensee had previously painted the transparent plastic film to make the film
easier to locate.
The task force also considered whether step pads used inside containment could
block the strainers. The step pads are used to control contamination at exits
from radiological control areas inside containment and are taped to the floor
with yellow and magenta duct tape. The licensee does not consider it likely
that the step pads would be dislodged during a containment spray actuation;
however, to minimize this possibility, the radiation department removed step
pads not required for continuing work.
Browns Ferry
Browns Ferry uses a BWR with a Mark I Type containment that consists of a
steel drywell and toroidal suppression pool. Divers inspecting inside the
Unit 2 torus found pieces of paper towel and tape in the torus and on the
strainers. The licensee cleaned the torus and strainers of the paper towel
and tape, removing about 1 square meter [11 square feet] of material. The
total surface area of the four strainers is 3.7 square meters [40 square
feet]. If all of the material had become deposited on the strainers it would
have blocked about 25 percent of the strainer surface area. From videotape, about 15 percent of one of the two strainers examined was actually blocked
under normal operating and test conditions. The licensee calculated that the
strainers could be blocked up to 65 percent and still allow adequate core
cooling flow.
The licensee determined that material may enter the torus through any of three
ways: (1) personnel accessways, (2) vacuum breaker vents, or (3) the torus
downcomer vents inside containment. The licensee plans to place covers over
the vacuum breaker vents and the torus downcomer vents during maintenance
activities in those areas. Regarding the personnel accessways, the licensee
reviewed the foreign material control data from the last outage and found
weaknesses in the process. For example, an entry in the material control log
specified that a bag of towels was brought into the torus area but did not
specify the quantity of towels taken in or removed. The licensee issued a
site bulletin to alert plant personnel to the need to carefully implement
material control procedures and is reviewing the foreign material exclusion
procedures for revision.
Related Generic Communications
In NRC Bulletin 93-02 and Supplement 1, "Debris Plugging of Emergency Core
Cooling Suction Strainers," the staff discussed the potential for containment
sump screens and emergency core cooling strainers to become blocked by fibrous
material from piping insulation or air filters. The staff requested licensees
to identify sources of fibrous materials and to take immediate compensatory
actions to ensure the functional capabilities of affected safety systems. In
NRC Information Notice 93-34 and Supplement .1,"Potential for Loss of
Emergency Cooling Function Due to a Combination of Operational and Post-LOCA
Debris in Containment," the NRC staff discussed the problem of emergency core
II 1 .
K>
IN 94-xx
December xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Dave Skeen, NRR
(301) 504-1174 Joseph Birmingham, NRR
(301) 504-2829
- See previous concurrence J,d .i
OFFICE
NAME
DATE
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IN 95-06 January 25, 1995 cooling systems becoming blocked by a combination of operational and
postaccident debris including paint flakes, dirt and corrosion products, and
fibrous material from any source. In NRC Information Notice 94-57, 'Debris in
Containment and the Residual Heat Removal System," the staff discussed
additional examples of debris blockage of emergency core cooling systems.
These communications highlighted the need to consider dirt and debris and
fibrous material as sources of material capable of blocking containment sump
screens or emergency core cooling strainers.
This information notice discusses the potential for materials such as tape, labels, plastic film, and paper or cloth products intentionally brought inside
containment to collect on screens and strainers and block core cooling
systems.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Joseph L. Birmingham, NRR
(301) 504-2829 Richard M. Lobel, NRR
(301) 504-2865 Attachment:
List of Recently Issued NRC Information Notices
AA, XJ# 6
Attachment
IN 95-06 January 25, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-05 Undervoltage Protection 01/20/95 All holders of Construction
Relay Settings Out of Permits for nuclear power
Tolerance Due to Test reactors.
Equipment Harmonics
95-04 Excessive Cooldown and 01/19/95 All holders of OLs or CPs
Depressurization of the for nuclear power reactors.
Reactor Coolant System
Following a Loss of
Offsite Power
95-03 Loss of Reactor Coolant 01/18/95 All holders of Ols or CPs
Inventory and Potential for nuclear power reactors.
Loss of Emergency Mitiga- tion Functions While in
a Shutdown Condition
95-02 Problems with General 01/17/95 All holders of OLs or CPs
Electric CR2940 Contact for nuclear power reactors.
Blocks in Medium-Voltage
Circuit Breakers
95-01 DOT Safety Advisory: 01/04/95 All U.S. Nuclear Regulatory
High Pressure Aluminum Commission licensees.
Seamless and Aluminum
Composite Hoop-Wrapped
Cylinders
94-90 Transient Resulting in a 12/30/94 All holders of OLs or CPs
Reactor Trip and Multiple for nuclear power reactors.
Safety Injection System
Actuations at Salem
94-89 Equipment Failures at 12/28/94 All U.S. Nuclear Regulatory
Irradiator Facilities Commission irradiator
licensees.
94-88 Inservice Inspection 12/23/94 All holders of OLs or CPs
Deficiencies Result in for pressurized water
Severely Degraded Steam reactors.
Generator Tubes
OL - Operating License
CP = Construction Permit
IN 95-06 January 25, 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.
op¶IAn Ad by Bean K.Grimes
rrianr . Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Joseph L. Birmingham, NRR
(301) 504-2829 Richard M. Lobel, NRR
(301) 504-2865 Attachment:
List of Recently Issued NRC Information Notices
OFFICE OECB:DOPS SCSB:DSSA C/SCSB:DSSA D/DSSA:NRR
NAME DSkeen* RLobel* RBarrett* GMHolahan*
DATE 12/05/94 12/13/94 12/13/94 12/22/94 OFFICE ADM:PUB OECB:DOPS SC/OECB:DOPS OECB:DOPS
NAME JMain* JBirmingham* RDennig* RKiessel*
DATE 12/05/94 12/05/94 - /1712/22/94 12/22/94
0
1 OFFICE C/OECB:DOPS D__ l_l
T T-
_
lNAME AChaffee* dEPI
DATE 12/27/94 01//f/95 -
OFFICIAL RECORD COPY
DOCUMENT NAME: S:\95-06.IN
IN 95-06 January 25, 1995 If
This information notice requires no specific action or written response.
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.
nrrtinT1 ,ned byBrlan K.Grimes
Pri an K.'Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
, Technical contacts: Joseph L. Birmingham, NRR
(301) 504-2829 Richard M. Lobel, NRR
i (301) 504-2865 Attachment:
List of Recently Issued NRC Information Notices
pnfl-fivW
-ae jig eUV uu u
OFFICE OECB:DOPS SCSB:DSSA C/SCSB:DSSA D/DSSA:NRR
NAME DSkeen* RLobel* RBarrett* GMHolahan*
DATE 12/05/94 12/13/94 12/13/94 12/22/94 OFFICE ADM:PUB OECB:DOPS SC/OECB:DOPS OECB:DOPS
NAME JMain* JBirmingham* RDennig* RKiessel*
DATE 12/05/94 12/05/94 12/22/94 12/22/94 OFFICE C/OECB:DOPS D/ _
NAME AChaffee* AX^14iS-1"
DATE 122/4 01// r95
=
OFFICIAL RECORD COPY
DOCUMENT NAME: S:\95-06.IN
a
IN 95-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.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Joseph L. Birmingham, NRR
(301) 504-2829 Richard M. Lobel, NRR
(301) 504-2865
OFFICE OECB:DOPS SCSB:DSSA C/SCSB:DSSA D/DSSA:NRR
NAME DSkeen* RLobel* RBarrett* GMHolahan*
DATE 12/05/94 12/13/94 12/13/94 12/22/94 OFFICE ADM:PUB OECB:DOPS SC/OECB:DOPS OECB:DOPS
NAME JMain* JBirmingham* RDennig* WRKessel*
DATE 12/05/94 12/05/94 12/22/94 12/22/94 OFFICE C/OECB:DOPS D/DOPS _
NAME AChaffee* BGrimes
DATE 12/27/94 01/ /95 401 OFFICIAL RECORD COPY
DOCUMENT NAME: G:\DBRISIN.JLB
i
I I -I .
v)
IN 94-xx
December xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
N1~
Technical contacts: Dave 5Aeeri7T4RR
( 4 4-1174 , I
2' Z 4113 Richard-'Lobel, NRR
(301) 504-2865 DOCUMENT NAME: S:\DOPSSEC\DBRISIN.JLB
OFFICE OECB:DOPS SCSB:DSSA C/SCSB:DSSA D/DSSA:NRR
NAME DSkeen* RLobel* RBarrett* GMHolahan*
DATE 12/05/94 1113/94 1 212/13/94 12/22/94 OFFICE ADM:PUB OECB:DOPS SC/OECB:DOPS OECB:DOPS
NAME JMain* JBirmingham* RDennig* RKiessel*
DATE 12/05/94 12/05/94 12/22/94 12/22/94 OFFICE C/OECB:DOPS D/DOPS L_
NAME AChaffee* BGrimes (1k
DATE 12/27/94 12/ /94 OFFICIAL RECORD COPY
j
IN 94-xx
December xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: Dave Skeen, NRR
(301) 504-1174 Richard Lobel, NRR
(301) 504-2865
, d]mae,-
OFFICE SCSB:DSSA C/SCSB:DSSA I D/DSSA:NRR
NAME RLobel* RBarrett* GMHolahan*
DATE 12/13/94 12/13/94 112/22/94 TECH ED OECB:DOPS OLA:DOOEC/,OP /OECB:DOPSl D/DOPS:NRR
JMain* l JBirminghan* l RLDenni' RJ iesse l AEChaffee V l BKGrimes
12/05/94 112/05/94.a e
1 12J2/94 12/494 G:\ . .D.R.SI.._L=
12/17/94 § 12/ /94 Official Do um n Name:
Ofic a Document G:\JLB\DBRISIN.JLB
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list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (18 January 1995, Topic: Packing leak)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Troxler Moisture Density Gauge)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide. (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Brachytherapy)
- Information Notice 1995-40, Supplemental Information to Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes. (20 September 1995, Topic: Hydrostatic, Nondestructive Examination, Brachytherapy)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure. (22 September 1995, Topic: Brachytherapy)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995, Topic: Brachytherapy)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995, Topic: Brachytherapy)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Brachytherapy)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995, Topic: Brachytherapy)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
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