Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam GeneratorsML031060234 |
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: |
09/22/1995 |
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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-95-041, NUDOCS 9509180341 |
Download: ML031060234 (12) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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>. |
K9J(UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 September
22, 1995 NRC INFORMATION
NOTICE 95-41: DEGRADATION
OF VENTILATION
SYSTEM CHARCOAL RESULTING
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 potential
degradation
of ventilation
system charcoal as a result of the charcoal's
exposure to chemicals
during the chemical cleaning of steam generators.
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 June 5, 1994, a chemical cleaning of the secondary
sides of the steam generators
at Surry Unit 2 was begun. During this cleaning, containment
purge was established
using train A of the auxiliary
ventilation
system, which contains a safety-grade
charcoal adsorber.
The chemical cleaning process involves the--use of ethylene diamine tetraacetic
acid (EDTA) as the cleaning agent and of various other chemicals
such as ethylenediamine (EDA), hydrazine, ammonia, hydrogen peroxide, nitrogen, and CCl-801, a proprietary
corrosion inhibitor.
During the chemical cleaning the steam generators
were isolated from the containment
atmosphere
and force-vented
to the outdoor atmosphere
through the atmospheric
steam dump relief valves. The steam generators
were rinsed to remove residual chemicals.
were opened for sludge lancing of the tube sheet region.On June 16, 1994, a strong odor of ammonia was reported in the Unit 2 containment.
Concentrations
were measured at 30 ppm (parts per million)ammonia and 6 ppm hydrazine.
Consequently, personnel
were evacuated
from the containment.
At the time of the evacuation, the chemical cleaning and rinse had been completed
on steam generators
A and C and the steam generators
were vented to the containment.
Because of the elevated levels of hydrazine
and ammonia in the containment, train B of the auxiliary
ventilation
system was started to assist train A in reducing the airborne concentrations.
Both trains operated approximately
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until chemical concentrations
in the containment
were reduced.950918034 t~q~gut II @
IN 95-41 September
22, 1995 -As a result of the exposure of the charcoal to the chemicals, in accordance
with the technical
specifications (TS), a sample of train A charcoal was taken and a laboratory
test of a sample of the sample was performed.
The results of the laboratory
test showed a methyl iodide removal efficiency
of 93.4 percent, which was below the TS limit. The charcoal was replaced.
A sample from train B was tested and the results of the laboratory
test of that sample showed a methyl iodide removal efficiency
of 90.7 percent. This value was also below the TS limit, and the train B charcoal was replaced.The failure of these samples was a surprise to the licensee.
At the time the charcoal was determined
to have failed, train A had operated for 657 hours0.0076 days <br />0.183 hours <br />0.00109 weeks <br />2.499885e-4 months <br />, while the train B had operated for 360 hours0.00417 days <br />0.1 hours <br />5.952381e-4 weeks <br />1.3698e-4 months <br />. In addition, the licensee had held discussions
with the charcoal supplier during which the supplier had indicated
that exposure of the charcoal to hydrazine
and ammonia in the above noted concentrations
should not have resulted in its degradation.
As a result of the experience
at Unit 2, when the steam generators
at Unit 1 were chemically
cleaned, the licensee arranged for the containment
flow to be diverted to a non-safety-grade
system containing
charcoal.
When the licensee completed
the cleaning operation, laboratory
testing of the charcoal in the non-safety-grade
system showed that the adsorber efficiency
was 3.3 percent less than its efficiency
before the chemical cleaning.
On the basis of these two experiences, the licensee concluded
that discharging
the air involved in steam generator
cleaning operations
through systems containing
charcoal was likely to degrade the charcoal.The licensee's
laboratory
tests of the charcoal were performed
at 30C [86°F]and a relative humidity of 95 percent with a face velocity of 24.4 meters per minute [80 feet per minute]. The laboratory
tests were conducted
using the 1979 version of American Society for Testing and Materials (ASTM) D3803, Standard Test Method for Nuclear-Grade
Activated
Carbon.' The licensee did not attempt to determine
the chemical compound responsible
for the degradation
of the charcoal.
However, it and its charcoal supplier believe that the probable culprits were EDA and EDTA.The NRC staff held telephone
conversations
with charcoal suppliers
and testing laboratory
representatives.
Based upon these conversations, the parties concluded
that, although the ammonia did not contribute
to the degradation
of the charcoal, the breakdown
of hydrazine
in the charcoal may have contributed
additional
moisture to the charcoal resulting
in its degradation.
These discussions
also confirmed
that both EDA and EDTA could degrade the charcoal.
The staff also noted that, had the licensee performed the laboratory
tests in accordance
with the guidance in NRC Information
Notice 87-32, "Deficiencies
in the Testing of Nuclear-Grade
Activated
Charcoal," (Accession
No. 8707070003)
or in accordance
with the 1989 version of ASTM D3803, the measured degradation
of the charcoal would have been greater than that identified
by the licensee.
K..- V IN 95-41 September
22, 1995 Exposure of charcoal to chemical compounds
can result in its degradation.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers
in their ventilation
systems during and/or after chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.'nn .1%ic I Division of Reactor Pr ram Management
Office of Nuclear Reactor Regulation
Technical
contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices A4e UQ FJLa
~1 <-J Attachment
1 IN 95-41 September
22, 1995 Referenced
Codes and Standards American Society for Testing and Materials, ASTM D3803, "Standard
Test Method for Nuclear-Grade
Activated
Carbon,' Philadelphia, Pennsylvania.
wXvachment
2 IN 95-41 September
22, 1995 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 95-40 95-39 95-38 95-37 Supplemental
Information
to Generic Letter 95-03,"Circumferential
Cracking of Steam Generator
Tubes" Brachytherapy
Incidents Involving
Treatment Planning Errors Degradation
of Boraflex Neutron Absorber in Spent Fuel Storage Racks Inadequate
Offsite Power System Voltages during Design-Basis
Events 09/20/95 09/19/95 09/08/95 09/07/95 All holders of OLs or CPs for nuclear power reactors.All U.S. Nuclear Regulatory
Commission
Medical Licensees.
All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.95-36 Potential Post-Fire Lighting Problems with Emergency 08/29/95 All holders of OLs or CPs for nuclear power reactors.95-35 95-34 93-83, Supp. 1 95-33 Degraded Ability of Steam Generators
to Remove Decay Heat by Natural Circulation
Air Actuator and Supply Air Regulator
Problems in Copes-Vulcan
Pressurizer
Power-Operated
Relief Valves Potential
Loss of Spent Fuel Pool Cooling After a Loss-of-Coolant
Accident or a Loss of Offsite Power Switchgear
Fire and Partial Loss of Offsite Power at Waterford Generating
Station, Unit 3 08/28/95 08/25/95 08/24/95 08/23/95 All holders of OLs or CPs for pressurized
water reactors (PWRs).All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.I OL -Operating
License CP = Construction
Permit
K>IN 95-41 September
22, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.orig /s/'d by DMCrutchfield
Dennis M. Crutchfield, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: 95-41.IN*See previous concurrence
To receive a copy of this document, indicate In the box: C' = Copy without attachment/enclosure
'E' = Copy with attachmentlenclosure
'N' -No copy OFFICE TERB:DOTS
IC ADM:PUB IN OECB:DOPS
I E SC/TERB:DOTS
E C/TERB:DOTS
LE NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 105/02/ 95 05/02/95.....-.I OFFICE 1SC/OECB:DOPS
IN IPECB:DRPM
I E IC/PECB:DRPM
I NID/DR~1X, I 11 NAME EFGoodwin*
RKiessel*
el DATE 05/15/95 1 3909/14/95
09 95 UtiilLIAL
K-IUKU WURY
IN 95-xx September
xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: S:\DRPM SEC\CHR91438
-a_ An Ad_ try -.--- -ta~ rh otonl IF' .Cnnv with atnchmentlenclosure
- N' -No copy T o receive a copy 0? this cocunwnt, Indicate mn Xn. o:A; -s°Pqt wnn u--a........
o ---- -. -OFFICE TERB:DOTS
IC ADM:[PUB NOECB:DOPS
I E SC/TERB:DOTSI
E IC/TRB:DOTSE
NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch*DATE 05/02/95 105/10/95
105/02/95
05/02/95_
05/02/9--.---r-I -I .I &Ii M fr~ .nnLA nFFT(F ISC/OECB!DOPS
IN IPECH: URPM I t IL/ tLt1:UKrM I1 IU UKNrr I -11-- _, ___ .__.__ ..__ _ _ .__NAME EFGoodwin*
I RKiessel*
_AEChaffee*
IDMCrutchfieldqI
DATE 05/15/95 109/13/95
--9/1/95 099 UOFICIIAL
KLLUKU HUrY
IN 95-xx September
xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
-- .-rt S. *" 11. b_-f -t -fthrA
E = COnY with =tachmerd/en
e^suu. a No copy re lculy.
-.w --I I OFFICE TERB:DOTS
lC ADM:PUB IN OECB:DOPS
E E SC/TERB:DOTSI
E C/NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch* CLMiller*DATE 05/02/95 05/10/95 05/02/95 05/02/95 05/02/95.M. a.(FF FIC SCIFECR:DOPS
I N I PECB:DRPM I E I UPLUB; WPM IA/IUUKrfi
I I I I -I .-- .' -- 0 .... .... ... -,,, ...-NAME 1EFGoodwin*
_RKiessel
42 AEChaffee
_ DMCrutchfeld
lDATE 105/15/95
109/J3 /95 1fj1 T 09/.5 /95 09/ /95^rIrY 0 TAiI nrffnn% n glf OFF lVlAL KcvuKu vuri
IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: C" = Copy without attachmentlenclosure
'E' = Copy with attachment/enclosure
ON' -No copy OFFICE TERB:DOTS
C A M:PUB 1 N [OECB:DOPS
E SC/TERB:DOTS
lE C/TERB:DOTS
K E NAME JJHayes* Tech Ed/MMejac*
RABenedict*
RLEmch* ICLMiller*
DATE 05/02/95 05/10/95 105/02/95
105/02/95
05/02/95 a AI nFrTrr I SC/fECBRiOPS
I N IOECB:DOPS
I IM/utCu:VUVp
I I uIuurP 1 11-_ .--- -. -I- v .A _ .--NAME EFGoodwin*
_ RKiessel IAEChaffee
SUB BKGrimes DATE 05/15/95 05/ /95 05/ /95 105/ /95 nrchIrTAI
nrv'nnn fflV 01-1-11,1AL
KELUKU ,Ur 1 IN 95-xx May xx, 1995 Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: ACT -Copy without attachmentlenclosure
'E'
- Copy with attachmentlenclosure
SNH -No copy OFFICE TERB:DOTS
IC ADM:PUB [ OECB:DOPS
I E SC/TERB:DOTS
I E C/TERB:DOTS
I E NAME JJHayes* Tech Ed/MMejac*
[RABenedict*
IRLEmch* CLMiller*DATE 05/02/95 05/10/95 105/02/95
05/02/95 05/02/95 IIOFFICE 1SC/OECB:DOPS
I I C/OECB:DOPS
I D/DOPS I 1I NAME EFGoodwin
X 1AEChaffee
% 5b I mKGriImes DATE 105/16E/9505/
/95 05/ /95 OFFICIAL RECORD COPY
-0 '"?;4 -Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
A -...-
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438
To receive a copy of this document, Indicate In the box: "C' a Copy without attachmentenclosure "F = Copy with attachment/enclosure "N" -No copy-_ _ _ _ -_ .l OFFICE ITERB:DOTS
IC ADM:PUB I OECB:DOPS I E ISC/TERB:DOTS
I E IC/TER.B:DOTS
I E 11 NAME JJHayes* j ITech Ed 1 A!ndJRABenedict*
IRLEmch* --_- CLMiller*DATE 105/02/95
105/1o /95 105/02/95
105/02/95
105/02/95 A- -A _ A __OFFICE ISC/OECB:DOPS
l C/OECB:DOPS
I D/DOPS I l1 NAME EFGoodwin
JAEChaffee
BKGrimes DATE 05/ /95 105/ /95 05/ /95:.UIIILIAL KtLUKU COPY 7,,, A; -..
K>~Exposure of charcoal to chemical compounds
can result in a degradation
of the charcoal.
With such degradation, in the event of an accident, the charcoal may perform at an efficiency
less than that assumed in the staff's safety evaluation.
Therefore, if licensees
divert air flow through charcoal adsorbers in their ventilation
systems during and/or following
chemical cleaning, they may find it appropriate
to perform a laboratory
test of the charcoal to ensure that the charcoal has not degraded below its TS surveillance
requirements
limit.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.Brian K. Grimes, Director Division of Project Support Office of Nuclear Reactor Regulation
Technical
Contact: John J. Hayes, NRR (301) 415-3167 Attachments:
1. Referenced
Codes and Standards 2. List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\IN\CHR91438 To rSceive a copy of this document, Indcate In the box: 'C' Copy without attachmenUt/enclosure
'E' -Copy with attachment/enclosure
'N'
- No conp OFFICE T TECH ED l OECB 14F 1 SC:TERB ,,Jir-C:TERB/DOTS
I Cl NAME ayes RABeneaict,'
RLEmch , CiMiller cog J llDATE OS/ V/95y V 05/ /95 05/oZ /95 05/2.? /95 05/ N-/95 SC:OECB/DOPS
I 1B:OECB/DOPS
I ID:DOPS I 1 EFGoodwin
AEChaffee
BKGrimes 05/ /95 05/ /95 05/ /95 J
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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)
... further results |
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