Unexpected Degradation of Lead Storage BatteriesML031060209 |
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: |
04/20/1995 |
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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-95-021, NUDOCS 9504140211 |
Download: ML031060209 (11) |
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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 April 20, 1995 NRC INFORMATION NOTICE 95-21: UNEXPECTED DEGRADATION OF LEAD STORAGE
BATTERIES
Addressees
power
All holders of operating licenses or construction permits for nuclear
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuinglead this information
notice to alert addressees to possible degradation of storage batteries
within the first two years of service. It is expected that recipients will
consider
review the information for applicability to their facilities and suggestions
actions, as appropriate, to avoid similar problems. However, no
contained in this information notice are not NRC requirements; therefore, specific action or written response is required.
Discription of Circumstances
Palo Verde
Arizona Public Service Company (APS, the licensee) installed AT&T round cell
originally
batteries at Palo Verde, after continued problems with the Palo Verde Unit 2 installed batteries. During a 1994 maintenance outage at were less than two
the licensee tested performance on the AT&T batteries which the
years old. The capacities of the batteries were lower than expected;
capacities had decreased instead of increasing.
Train B (Battery Banks B and D) had been declared inoperable90 onpercent October 1,
1994, because the measured capacity was slightly less than
capacity. On October 7, 1994, Train A (Battery Banks A and C) was declared
test results indicated that
inoperable because a projection of the capacity Palo Verde Technical
the battery capacities would be below 90 percent. The
is at least
Specifications acceptance criterion for the AT&T batteryto capacitya performance
90 percent of the manufacturer's rating when subjected
discharge test.
Oconee Unit 2 Replacement Exide batteries of the standard lead calcium cells 2CA (rectangular)
ago. In testing batteries and 2CB,
were installed less than two years
certain cells were found to have capacities lower than expected.
9504140211 Pn X N t-\ o5 Lao
Y/k/fMoI
1\l'
K- IN 95-21 April 20, 1995 At Oconee Unit 2, Battery 2CB was tested on Januarywas 4, 1995. The test
indicated that the overall capacity of the battery only 77 percent.
Battery 2CA was tested on January 12, 1995, and its overall capacity was about
80 percent. The Oconee design commitments require that the battery capacity
should exceed 80 percent. The two batteries were installed in January 1993, and the testing took place within two years of installation.
Discussion
for Maintenance, Testing
IEEE Standard 450-1987, "IEEE Recommended PracticeStationary
and Replacement of Vented Lead-Acid Batteries for Applications,"
test of the battery capacity should be made
recommends that a performance that battery
within the first two years of service. It is typically expected often shows a
capacity will not decrease in that period and, in fact, it
slight increase.
Although the designs differ, in both cases the batteries indicated a
consistent with the
significant decrease in capacity, and a decrease is not
normal behavior expected for either of these batteries.
Both licensees are taking steps to rectify the degradation in the batteries by
banks.
replacing the defective cells or entire battery degradation. In addition, they are
At Palo Verde, attempting to find the root cause of the abnormal the projected
the licensee determined that adequate margin existed between
battery capacities and worst case design loading.
the root cause of the
With respect to the AT&T batteries, APS maintains thatcontamination
involves and an
drop in capacity in the Unit 2 cells likely rate during the
inadequate curing process because of an increase in production
manufactured. These problems apparently
time the Palo Verde Unit 2 cells were manufactured. After
did not exist when the Palo Verde Unit 1 and 3 cells were
the licensee noted the degradation of the Unit 2 batteries, spare cells in
in expected capacity. In
Units 1 and 3 were found to have no decrease used as the Class IE dc
addition, the licensee has learned that the AT&T cells
not
sources in McGuire and Byron/Braidwood nuclear plants were also
manufactured in this time of very high production.
Although not as significant as the capacity loss noted above, APS and AT&T
toward early
have found additional cells that show some of the same tendency in the
loss of capacity. This may be due to existing variations occurring the effect on
materials selection and manufacturing process. To minimizededication process
final battery capacity, APS and AT&T developed a specific and
to be used during the manufacture acceptance testing phase to identify
reject cells that show early loss of capacity.
AT&T and APS also believe that some of the drop induring capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen the dedication
testing of the new cells purchased for replacement, is due to the additional
in a
testing which has involved a number of discharge and recharge cycles
relatively short period of time.
IN 95-21 April 20, 1995 APS has replaced the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the design basis
Palo Verde Unit 2 loading, and that meet the specific dedication criteria
developed by APS and AT&T. The licensee is also studying the influence of the
recharging methodology on battery performance.
AT&T and APS plan an extensive test program to establish the cause of the
unexpected capacity decrease in the replacement cells. Exide is still in the
process of establishing the root cause for the degradation at Oconee.
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 contact: S. N. Saba, NRR
(301) 415-2781 Thomas Koshy, NRR
(301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
At&,chment
IN 95-21 April 20, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-64, Reactivity Insertion 04/06/95 All holders of OLs or CPs
Transient and Accident for nuclear power reactors.
Supp. 1 Limits for High Burnup
Fuel
95-18, Potential Pressure&Locking 03/31/95 All holders of OLs or CPs
of Safety-Related Power- for nuclear power reactors.
Supp. 1 Operated Gate Valves
95-20 Failures in Rosemount 03/22/95 All holders of OLs or CPs
Pressure Transmitters for nuclear power reactors.
due to Hydrogen Per- meation into the Sensor
Cell
Failure of Reactor Trip 03/22/95 All holders of OLs or CPs
95-19 for nuclear power reactors.
Breaker to Open Because
of Cutoff Switch Material
Lodged in the Trip Latch
Mechanism
Potential Pressure-Locking 03/15/95 All holders of OLs or CPs
95-18 for nuclear power reactors.
of Safety-Related Power- Operated Gate Valves
95-17 Reactor Vessel Top Guide 03/10/95 All holders of OLs or CPs
and Core Plate Cracking for boiling water reactors.
Vibration Caused by 03/09/95 All holders of OLs or CPs
95-16 for boiling water reactors.
Increased Recirculation
Flow in a Boiling Water
Reactor
Inadequate Logic Testing 03/07/95 All holders of OLs or CPs
95-15 for nuclear power reactors.
of Safety-Related Circuits
95-14 Susceptibility of Con- 02/28/95 All holders of OLs or CPs
tainment Sump Recircula- for nuclear power reactors.
tion Gate Valves to
Pressure Locking
OL - Operating License
CP = Construction Permit
IN 95-21 April 20, 1995 APS has replaced the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the design basis
Palo Verde Unit 2 loading, and that meet the specific dedication criteriaof the
developed by APS and AT&T. The licensee is also studying the influence
recharging methodology on battery performance.
AT&T and APS plan an extensive test program to establish the cause of the the
unexpected capacity decrease in the replacement cells. Exide is still in
process of establishing the root cause for the degradation at Oconee.
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.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: S. N. Saba, NRR Thomas Koshy, NRR
(301) 415-2781 (301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-21.IN
- See previous concurrence E-Copy with attachment/encLosure N a No copy
To receive a copy of this document, indicate in the box C=Copy w/o attachment/enclosure
E SC/EELB:DE E SC/EELB:DE E lC/EELB:DE E
OFFICE EELB:DE
NAME SNSaba:nkw * DThatcher* EWWeiss * CHBerlinger*
DATE 02 /24/95 02/27 /95 02/28 /95 03/02 /95 OFFICE ADM:PUB l OECB:DOPS SC/OECB:DOPS l IYi RPW&RIVIl
NAME RSanders* TKoshy* EGoodwin* BHolian*
03/08/95 03/16/95 3/ 15 / 7 DATE 03/02/95 OFFICE D/DE l OECB:DOPS C/OECB:DOPS
NAME BSheron* RKiessel* AChaffee* 0 /95 DATE 03/28/95 03/30/95 04/07/95 04// Yl95l
OFFICIAL RECORD COPY
IN 95-XX
March xx, 1995 AT&T and APS also believe that some of the drop in capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen during the dedication
testing of the new cells purchased for replacement, is due to the additional
testing which has involved a number of discharge and recharge cycles in a
relatively short period of time.
APS has replaced the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the design basis
Palo Verde Unit 2 loading, and that meet the specific dedication criteria
developed by APS and AT&T. The licensee is also studying the recharging
methodology to better understand it's influence on battery performance.
AT&T and APS have committed to conduct an extensive test program to establish
the cause of the unexpected capacity decrease in the replacement cells. Exide
is still in the process of establishing the root cause for the degradation at
Oconee.
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: S. N. Saba, NRR Thomas Koshy, NRR
(301) 415-2781 (301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TXK\ATT.BAT
- See previous concurrence with attachment/enclosure N a No copy
To receive
- copy of this document, indicate in the box cMcopy W/oattschment/enclosure E-Copy
OFFICE lEELB:DE i iE SC/EELB:DE E SC/EELB:DE E C/EELB:DE E
NAME [SNSaba:nkw * DThatcher* EWWeiss * CHBerlinger*
DATE [02 /24/95 02/27 /95 02/28 /95 03/02 /95 OFFICE ADM:PUB OECB:DOPS jSC/OECB:DOPS PDIV2:DRPW&RIV
NAME RSanders* TKoshy* EGoodwin* BHolian*
DATE 03/02/95 03/08/95 03/16/95 3/ 15 /95 OFFICE D/DE l OECB:DOPS C/00 :DOPS D/DOPS l
NAME BSheron* RKiessel* AAif ffee BGrimesi
DATE 103/28/95 03/30/95 I1/7 /95 _/ J / /95 OFFICIAL RECORD COPY
IN 95-XX
March xx, 1995 AT&T and APS also believe that some of the drop in capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen during the dedication
testing of the new cells purchased for replacement, is due to the additional
testing which has involved a number of discharge and recharge cycles in a
relatively short period of time.
APS has replaced the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the design basis
Palo Verde Unit 2 loading, and that meet the specific dedication criteria
developed by APS and AT&T. The licensee is also studying the recharging
methodology to better understand it's influence on battery performance.
AT&T and APS have committed to conduct an extensive test program to establish
the cause of the unexpected capacity decrease in the replacement cells. Exide
is still in the process of establishing the root cause for the degradation at
Oconee.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contacts listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: S. N. Saba, NRR Thomas Koshy, NRR
(301) 415-2781 (301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TXK\ATT.BAT
To receive a copy of this document, indicate in the box CaCopy w/o attachment/enctosure EnCopy with attachment/enctosure N
OFFICE
NAME
DATE
l DEELB:jDE
SNSaba:nkw
02 /24/95
ljEj SC/EELB:DE
DThatcher*
02/27 /95 E SC/EELB:DE
EWWeiss *
02/28 /95 I
E lC/EELB:DEjljEl
CHBerlinger*
03/02 /95 OFFICE ADM:PUB OECB: DOPS i SC/OECB:DOPS PDIV2:DRPW&RIV
NAME RSanders* TKoshy L EGoodwin BHolian*
DATE 03/0,/95 03/08 /95 S /)2/95 3/ 15 /95 OFFICE OECB:DOPS C/OECB:DOPS l (D/DOIPSIl
NAME I
t sRKiessel iI AChaffee BGrimes
DATE 3 _Xis /_95 1/ /95 / /95 UItILIAL KLLUKU Murv
02,*Y
W
- SJ IN 95-XX
March xx, 1995 AT&T and APS also believe that some of the drop in capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen during the dedication
testing of the new cells purchased for replacement, is due to the additional
testing which has involved a number of discharge and recharge cycles in a
relatively short period of time.
APS intends to replace the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the Palo Verde
Unit 2 loading, and that meet the specific screening criteria developed by APS
and AT&T.
AT&T and APS have committed to conduct an extensive test program to establish
the cause of the unexpected capacity decrease in the replacement cells. Exide
is still in the process of establishing the root cause for the degradation at
Oconee.
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 contacts: S. N. Saba, NRR Thomas Koshy, NRR
(301) 415-2781 (301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TXK\ATT.BAT
To receive a c of this docment, indicate in the box CzCp Wo/ attachment/enctosure ExCopy with attachment/enclosure N
OFFICE EELB:DE E SC/EELB:DE E SC/EELB:DE E C/EELB:DE E
NAME SNSaba:nkw * DThatcher* EWWeiss * CHBerlinger*
DATE 02 /24/95 02/27 /95 02/28 /95 03/02 195 OFFICE ADM:PUB l OECB:DOPS lE SC/OECB:DOPS l PDIV-2:DRPW Il
NAME RSanders* TKoshy ff i EGoodwin BHolian
DATE 103/02/95 03/08 /95 [ /95 I /95 OFFICE D/DE l OECB:DOPS l C/OECB:DOPS l / I III
NAME BSheron RKiessel AChaffee BGrimes
DATE I _/95 I /95 I /95 /95 OFFICIAL RECORD COPY
IN 95-XX
March xx, 1995 AT&T and APS also believe that some of the drop in capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen during the dedication
testing of the new cells purchased for replacement, is due to the additional
testing which has involved a number of discharge and recharge cycles in a
relatively short period of time.
APS has replaced the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the design basis
Palo Verde Unit 2 loading, and that meet the specific dedication criteria
developed by APS and AT&T. The licensee is also studying the recharging
methodology to better understand it's influence on battery performance.
AT&T and APS have committed to conduct an extensive test program to establish
the cause of the unexpected capacity decrease in the replacement cells. Exide
is still in the process of establishing the root cause for the degradation at
Oconee.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contacts listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: S. N. Saba, NRR Thomas Koshy, NRR
(301) 415-2781 (301) 415-1176 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TXK\ATT.BAT
attachment/enclosure N
To receive a copy of this document, indicate in the box C=Copy w/o a ttachment/enclosure EaCopy with
OFFICE EELB:DE lIE SC/EELB:DE E SC/EELB:DE E C/EELB:DE E
NAME SNSaba:nkw * DThatcher* EWWeiss * ICHBerlinger*
DATE 02 /24/95 02/27 /95 02/28 /95 03/02 /95 OFFICE ADM:PUB l OECB:DOPS l .SC/OECB:DOPS PDIV-2:DRPW
NAME RSanders* TKoshy 4f- EGoodwin BHolian -b'Pt\
DATE 03/02/95 j03/08 /95 / /95 4-/'5 /95 OFFICE E OECB:DOPS [C/OECB:DOPS l D/DOPSIl
NAME BSheron RKiessel AChaffee BGrimes
DATE / 95 . / /95 / /95 / /95 OFFICIAL RECORD COPY
IN 95-XX
March xx, 1995 AT&T and APS also believe that some of the drop in capacity in the Palo Verde
Unit 2 cells, as well as the unexpected drop seen during the dedication
testing of the new cells purchased for replacement, is due to the additional
testing which has involved a number of discharge and recharge cycles in a
relatively short period of time.
APS intends to replace the Unit 2 battery cells with new AT&T cells that have
undergone factory testing for at least two discharge/recharge cycles, that
still show substantially greater capacity than is needed for the Palo Verde
Unit 2 loading, and that meet the specific screening criteria developed by APS
and AT&T.
AT&T and APS have committed to conduct an extensive test program to establish
the cause of the unexpected capacity decrease in the replacement cells. Exide
is still in the process of establishing the root cause for the degradation at
Oconee.
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: S. N. Saba, NRR
(301) 415-2781 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\TXK\ATT.BAT
To receive a cnnv of this document. indicate in the box C=Coov w/o attachment/enctosure E=Coov with attachment/enclosure N a No copy
OFFICE EELB:DE l SC/EELB:DE SC*EELB:DE
MC=*gELBX
NAME SNSaba:nkw DThatcher EWWeiss CHBerlinger
DATE I /95 / /95 / /95 / /95 OFFICE ADM:PUB l OECB:DOPS l SC/OECB:DOPS PDIV-2:DRPW
NAME RSanders* TKoshy EGoodwin BHolian
DATE 03/02/95 3 /h /95 / /95 / /95 OFFICE D/DE OECB:DOPS C/OECB:DOPS _ D/DOPS
NAME BSheron RKiessel AChaffee BGrimes
DATE / /95 / /95 / /95 / /95 OFFICIAL RECORD COPY
4b
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacth': S. N. Saba, (301)415-2781 Attachment:
Li st of Recently Issued NRC Information Notices
To receive a copy of this document, indicate in the box C=Copy wlo attachmentlenclosure E=Copy with attachmentlenclosure Na
No copy
OFFIC EELB:DE:NRR SC/EELB:DE:NRR SC/EELB:DE:NRR I C/EELB:DE:NRR
NAME SNSaba:nkw DThatcher EWWeiss CHBerlinger
DATE 02/ /95 02/ /95 02/ /95 02/ /95 OFFICE Tech Editor OECB SC/OECB:DOPS BC/OECB:DOPS
NAtE TKoshy EGoodwin AChaffee
DATE 6.2/o95 02/ /95 02/ /95 02/ /95 OFFICIAL RETORD COPY
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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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