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 FROM CHEMICAL CLEANING OF STEAM
GENERATORS
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. After the rinse, the steam generators
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 hours 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 its degradation.
Exposure of charcoal to chemical compounds can result incharcoal may perform
With such degradation, in the event of an accident, the
evaluation.
at an efficiency less than that assumed in the staff's safety
adsorbers in their
Therefore, if licensees divert air flow through charcoal
cleaning, they may find it
ventilation systems during and/or after chemical ensure that the
to
appropriate to perform a laboratory test of the charcoal limit.
charcoal has not degraded below its TS surveillance requirements
response. If
This information notice requires no specific action or writtenplease contact
you have any questions about the information in this notice, of Nuclear
the technical contact listed below or the appropriate Office
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
"Standard Test Method
American Society for Testing and Materials, ASTM D3803, Pennsylvania.
for Nuclear-Grade Activated Carbon,' Philadelphia,
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 Supplemental Information 09/20/95 All holders of OLs or CPs
to Generic Letter 95-03, for nuclear power reactors.
"Circumferential Cracking
of Steam Generator Tubes"
95-39 Brachytherapy Incidents 09/19/95 All U.S. Nuclear Regulatory
Involving Treatment Commission Medical
Planning Errors Licensees.
95-38 Degradation of Boraflex 09/08/95 All holders of OLs or CPs
Neutron Absorber in for nuclear power reactors.
Spent Fuel Storage Racks
95-37 Inadequate Offsite Power 09/07/95 All holders of OLs or CPs
System Voltages during for nuclear power reactors.
Design-Basis Events
95-36 Potential Problems with 08/29/95 All holders of OLs or CPs
Post-Fire Emergency for nuclear power reactors.
Lighting
95-35 Degraded Ability of 08/28/95 All holders of OLs or CPs
Steam Generators to for pressurized water
Remove Decay Heat by reactors (PWRs).
Natural Circulation
95-34 Air Actuator and Supply 08/25/95 All holders of OLs or CPs
Air Regulator Problems in for nuclear power reactors.
Copes-Vulcan Pressurizer
Power-Operated Relief Valves
93-83, Potential Loss of Spent 08/24/95 All holders of OLs or CPs
Supp. 1 Fuel Pool Cooling After a for nuclear power reactors.
Loss-of-Coolant Accident
or a Loss of Offsite Power
95-33 Switchgear Fire and 08/23/95 All holders of OLs or CPs
Partial Loss of Offsite for nuclear power reactors.
Power at Waterford
Generating Station, Unit 3 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
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 INID/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 copy Ad_ try
a_An- .--- -ta~ rh otonl IF' . Cnnv with atnchmentlenclosure *N' - No copy
T o receive 0? this cocunwnt, Indicate mnXn. o:A; - s°Pqt
wnn u--a........ o ---- -
OFFICE TERB:DOTS IC ADM:[PUB NOECB:DOPS IE 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
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.___ _ I t IL/ tLt1:UKrM I -11 NAME EFGoodwin* IRKiessel* _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
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OFFICE TERB:DOTS lC ADM:PUB IN OECB:DOPS EE SC/TERB:DOTSI E C/
Tech Ed/MMejac* RABenedict* RLEmch* CLMiller*
I
NAME JJHayes*
DATE 05/02/95 05/10/95 05/02/95 05/02/95 05/02/95
. M. a.
(FF FIC SCIFECR:DOPS I N IPECB:DRPM I EI UPLUB; WPM IA/IUUKrfi I I
I .-- .- I . . ' --
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NAME 1EFGoodwin* _RKiessel 42 AEChaffee _ DMCrutchfeld l
DATE 105/15/95 109/J3 /95 T 09/.5 1fj1 /95 09/ /95
^rIrY0 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
C" = Copy without attachmentlenclosure 'E' = Copy with attachment/enclosure ON' - No copy
To receive a copy of this document, Indicate In the box:
C A M:PUB 1 N [OECB:DOPS E SC/TERB:DOTS C/TERB:DOTS lE KE
OFFICE TERB:DOTS
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
- . - _
ISC/fECBRiOPS-
-- v -.. A I
I- N IOECB:DOPS
_ I IM/utCu:VUVp I I uIuurP . -- 1 11 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 IE SC/TERB:DOTS IE 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 IC/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 -
A - ..
Exposure of charcoal to chemical compounds can result in a degradation of the .-14-.,-I.
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'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 IE 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'
OFFICE T TECH ED l OECB 14F 1 SC:TERB ,,Jir-C:TERB/DOTS I Cl
NAME ayes RABeneaict,' RLEmch , CiMiller cogllJ
DATE 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 1J
EFGoodwin AEChaffee BKGrimes
05/ /95 05/ /95 05/ /95
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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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