Bursting of High Pressure Coolant Injection Steam Line Rupture Discs Injures Plant PersonnelML031070135 |
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, 05000349, 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: |
08/16/1993 |
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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-93-067, NUDOCS 9308100248 |
Download: ML031070135 (14) |
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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, 05000349, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[: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 [[:05000349]] 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 [[:05000349]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
U -AU
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 16, 1993 NRC INFORMATION NOTICE 93-67: BURSTING OF HIGH PRESSURE COOLANT INJECTION
STEAM LINE RUPTURE DISCS INJURES PLANT
PERSONNEL
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
information
The U.S. Nuclear Regulatory Commission (NRC) is issuing thissteam driven
notice to remind addressees of the hazards associated with
injection (HPCI)
coolant injection systems such as the high pressure coolant at BWRs and the
system and the reactor core isolation cooling (RCIC) system will
auxiliary feedwater system at PWRs. It is expected that recipients and consider
review the information for applicability to their facilities X
actions, as appropriate, to avoid similar problems. However, suggestions therefore, no
contained in this information notice are not NRC requirements;
specific action or written response is required.
Background
the HPCI turbine
The purpose of HPCI steam exhaust rupture discs is to protect event if the normal
casing and associated exhaust piping from an overpressure Quad Cities Station, exhaust path to the suppression pool becomes blocked. At
in series with a
two 40.6-cm [16-inch] stainless steel discs are installed sensor
6.4-cm [2.5-inch] spacer between them to allow for a pressure
while serving no control function, instrumentation line. The pressure sensor, to alert the
actuates an alarm in the control room at 68.9 kPa [10 psig]
of the HPCI
operators that the inner disc is leaking. The normal range The HPCI high
exhaust steam pressure is 172 to 207 kPa [25 to 30 psig].-
and is sensed by
exhaust pressure turbine trip setpoint is 689 kPa [100 psig] piping
the section of
pressure sensors located downstream from where piping. The
containing the rupture discs branches off from the exhaust vertically over the
section of piping containing the rupture discs is mounted
greater than
turbine exhaust and vents directly to the HPCI room. Pressure inner disc to rupture
1034 kPa [150 psig] in the exhaust line will cause the
steam into the HPCI room.
and impact the outer disc, releasing
Description of Circumstances
Edison
During a quarterly inservice test of the HPCI pump at the Commonwealth line rupture
9, 1993, the exhaust steam
Quad Cities Station, Unit 1, on June
9308100248 F QrRi
IN 93-67 August 16, 1993 discs burst, releasing steam into the HPCI room, burning, and slightly
contaminating, five workers. The rupture discs burst within one second after
the turbine was started. Fire doors between the Unit 1 and Unit 2 HPCI rooms
were blown off their hinges into the Unit 2 HPCI room. Both sets of double
doors that are part of the secondary containment boundary were also blown
open. The floor latch on the inner containment door was bent; the outer doors
were also slightly damaged, but were repaired, closed and sealed approximately
35 minutes after the event. The steam release was terminated by automatic
isolation of the steam supply line on high HPCI turbine area temperature about
20 seconds into the event.
Discussion
Upon investigating the event, the licensee determined that water had
accumulated in the turbine casing because the drain system level switches for
the Unit 1 HPCI system had failed. In April 1992, the licensee performed a
reliability-centered maintenance study which recommended the level switches be
included in the preventive maintenance program but the recommendation had not
been acted on at the time of the event. The Unit 2 HPCI drain system level
switches were also found to be inoperable.
The slug of water created during the HPCI turbine roll passed from the turbine
casing to the vertical exhaust line and compressed the air in the 40.6 cm
[16 inch] line containing the rupture discs. The resulting pressure pulse
caused the inner rupture disc to burst, which impacted the outer disc as
designed and caused it to burst as well. The exhaust line pressure sensors, located in the horizontal 61 cm [24 inch] exhaust line that tees off from the
vertical 40.6 cm [16 inch] rupture disc line, did not detect a high pressure
(see Figure 1). The pressure switches were within tolerance and should have
immediately isolated the steam supply upon sensing a high exhaust pressure
before the rupture discs burst. The fact that a high exhaust line pressure
was not detected indicates two possible causes for the disc rupture. Either
the inner rupture disc was degraded and burst at lower-than-design pressure, or the pressure pulse actually exceeded the design pressure and caused the
disc to burst, relieving the exhaust line pressure before the downstream
pressure sensors detected a high pressure condition.
While inspection of the rupture discs did not reveal any degradation from
corrosion or aging, the vendor, Black Sivalls & Bryson, Inc, stated that the
discs are warranted for one year of service under normal conditions. The HPCI
and RCIC rupture discs at Quad Cities Station had been in service for 20 years
and were not part of any scheduled inspection or preventive maintenance
program. When consulted about the event, the vendor advised against using the
spare discs in the plant storeroom because they were purchased at the same
time as the failed discs. The licensee later replaced the failed discs with
new units. Before this event, the licensee recently replaced a HPCI rupture
disc during a refueling outage at the Dresden Station, a plant similar to Quad
Cities, after finding a crack in the disc during an inspection. The rupture
discs were inspected at the Dresden station as part of an enhancement to the
preventive maintenance program that was recommended by a reliability-centered
analysis.
I I
IN 93-67 August 16, 1993 The steam injured five workers, four of whom were participating in the HPCI
pump surveillance test. The fifth, and m6st severely. injured worker was a
health physics technician in the room on routine rounds, who was not aware of
the danger posed by the surveillance test. The test procedure contained no
specific guidance on room occupancy. Interviews with the workers revealed
that they had performed the surveillance in the past and were familiar with
the process. This familiarity may have led to a relaxed attitude toward
personal safety. The workers stated that during previous surveillances they
sometimes evacuated the room before rolling the turbine, or stood near the
doors to be ready to escape. The licensee made no routine announcement over
the plant paging system to alert plant personnel before the HPCI-turbine
start, and the workers were not prepared for the turbine to start.
A lack of constant communication between the workersand the control room may
have contributed to the personnel injuries. If a control room operator had
been in contact with the workers in the HPCI room during the turbine roll, the
workers would have been aware of the impending turbine start and, after start, the steam supply might have been manually-isolated or the turbine manually
tripped before the automatic isolation caused by the high area temperatureoin
the HPCI room.
When the Unit 1 HPCI rupture disc failure caused the fire doors to be blown
off their hinges and into the Unit 2 HPCI room, one of the doors impacted a
pipe hanger in the room and moved it 5.1 centimeters [2 inches]. If the steam
release had resulted from a high energy line break from the inlet side of the
HPCI steam line instead of the exhaust line, the damage to the Unit 2 HPCI
system could have been more severe. While high energy line breaks have been
analyzed for safety systems at all plants, the doors to rooms containing high
energy steam lines may not have been included in the analysis. For example, at Duane Arnold Energy Center, the licensee discovered that while the HPCI and
RCIC rooms were qualified for pressures of 26.2 kPa [3.8 psig], the doors
between these rooms and the reactor building would yield at 6.9 kPa [1 psig].
The licensee for the Quad Cities Station will implement a preventive
maintenance schedule for both the HPCI and RCIC rupture discs and the level
switches. The licensee will review the surveillance test procedure and
evaluate the missile hazard created by the fire doors. The licensee replaced
the rupture discs for the Unit 2 HPCI and RCIC systems with new ones after the
event at Unit 1 and is considering burst testing the removed discs to
determine if they are degraded.
IN 93-67 August 16, 1993 This information notice requires no specific action
you have any questions about the information in this or written response. If
the technical contact listed below or the appropriate notice, please contact
Reactor Regulation (NRR) project manager. Office of Nuclear
Brian K. Grim s, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, RIII
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachments:
1. Figure 1, "Simplified Layout of Quad Cities
Station HPCI Turbine Exhaust Steam Line"
2. List of Recently Issued NRC Information Notices
Cq~
0cr 1 cO
Cd)h r-
4
0 OUTER RUPTURE DISC _____
\TO VENT TO
HPCI ROOM
INNER RUPTURE DISC
[1 In]
2 40.6 cm
[16 in]
CLOSABLE CHECK
CHECK VALVE VALVE I
SUPPRESSION
50.8 cm
LOCKED I [20 In] STEAM INLET LINE
OPEN I FROM "B" MAIN
I 61 cm STEAM LINE
I [24 In]
I
25 cm
RX BLDG HPCI ROOM [10 In]
I
I
POOL I
I
D NOTES:
1. PRESSURE SWITCH ACTUATES ALARM IN CONTROL ROOM WHEN PRESSURE BETWEEN THE INNER RUPTURE DISC AND OUTER
RUPTURE DISC IS GREATER THAN 68.9 kPa [10 psig]. ALARM IS FOR INNER RUPTURE DISC LEAK DETECTION.
2. REDUNDANT PRESSURE SWITCHES IN EXHAUST STEAM LINE TRIP THE HPCI TURBINE IF PRESSURE IS GREATER THAN 689 kPa [100 psig].
3. RUPTURE DISC MAXIMUM DESIGN BURST PRESSURE IS 1034 kPa [150 psig].
Figure 1 - Simplified Layout of Quad Cities Station HPCI Turbine Exhaust Steam Line
Attachment 2 IN 93-67 August 16, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-66 Switchover to Hot-Leg 08/16/93 All holders of OLs or CPs
Injection Following for pressurized water
A Loss-of-Coolant reactors.
Accident in Pres- surized Water Reactors
93-65 Reactor Trips Caused 08/13/93- All holders of OLs or CPs
by Breaker Testing for nuclear power reactors.
with Fault Protection
Bypassed
93-64 Periodic Testing and 08/12/93 All holders of OLs or CPs
Preventive Maintenance for nuclear power reactors.
of Molded Case Circuit
Breakers
93-63 Improper Use of Soluble 08/11/93 All holders of OLs or CPs
Weld Purge Dam Material for nuclear power reactors.
93-62 Thermal Stratification 08/10/93 All holders of OLs or CPs
of Water in BWR Reactor for boiling water reactors.
Vessels
93-61 Excessive Reactor Coolant 08/09/93 All holders of OLs or CPs
Leakage Following A Seal for nuclear power reactors.
Failure in A Reactor
Coolant Pump or Reactor
Recirculation Pump
93-60 Reporting Fuel Cycle and 08/04/93 All fuel cycle and materials
Materials Events to the licensees.
NRC Operations Center
93-59 Unexpected Opening of 07/26/93 All holders of OLs or CPs
Both Doors in An for nuclear power reactors.
Airlock
93-58 Nonconservatism in Low- 07/26/93 All holders of OLs or CPs
Temperature Overpressure for pressurized-water
Protection for Pressurized- reactors.
Water Reactors
OL = Operating License
CP = Construction Permit
l
IN 93-67 August 16, 1993 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 CIGrimes/for
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, RIII
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachments:
1. Figure 1, "Simplified Layout of Quad Cities
Station HPCI Turbine Exhaust Steam Line"
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE.
OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-III
NAME DSkeen JMain PWen CVanderniet
DATE 07/08/93 , 07/08/93 07/14/93 07/14/93 OFC
NAME
DATE
GWright
[ 07/14/93 I *SC:OEAB:DORS
RDennig
107/15/93
AEChaffee
07/15/93
CEMcCracken
]07/16/93
_ I__ i
OFC *D:DSSA *C/OGCB:DORS D/DORS A^r
NAME AThadani GMarcus BGrimes t
DATE 07/24/93 07/29/93 0,S/\o/93 V
[OFFICIAL RECORD COPY]
DOCUMENT NAME: 93-67.IN
\- IN 93-XX
July XX, 1993 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 Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, RIII
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachment:
List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE.
AThadani
07/24/93 OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-III
NAME DSkeen JMain PWen CVanderniet
DATE J07/08/93 07/08/93 07/14/93 07/14/93 OFC *C:DRS:R-III *SC:OEAB:DORS *C/OEAB/DORS *C:SPLB:DSSA
NAME GWright RDennig AEChaffee CEMcCracken
DATE J07/14/93
.Y.
07/15/93 107/15/93 J07/16/93 OFC C/OGCB:DORS D/DORS
NAME GMarcus ifM BGrimes T
DATE 07/.9/93 07/ /93
[OFFICIAL RECORD COPY]
DOCUMENT NAME: IN93 XX.QC1
IN 93-XX
July xx, 1993 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 Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, R-III
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachment: List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-III
NAME DSkeen JMain l PWen CVanderniet
1'I
DATE 07/08/93 07/08/93 07/14/93 07/14/93
- C:DRS:RIII *SC:OEAB:DORS *C:OEAB:DORS C:SPLBAS* D: DSS 3q %
GWright RDenning AChaffee CEMcCracken ACThadani
07/14/93 [07/15/93 07/15/93 -07/2/f93 07/2A/93 C:OGCB:DORS D: DORS
GHMarcus BKGrimes
07/ /93 07/ /93 DOCUMENT NAME: QCHPCIIN.WEN C 5 G-4J -z--l - 2'J 43--
- k k- 9 CJ-
IN 93-XX
July xx, 1993 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 Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, R-III
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachment: List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-III
NAME DSkeen JMain PWen CVanderniet
DATE 07/08/93 L, 07/08/93 I_,__. . _,
07 114/93
. . . _I_ __
, I
07/14/93
-
- C:DRS:RIII S ODORS EAB:DORS C:SPLB:DSSA D:DSSA
GWright R enn afee
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07/14/93 [ 3 07/j</93 07/ /93 07/ /93 C:OGCB:DORS D:DORS
GHMarcus BKGrimes
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07/ /93 07/ /93 DOCUMENT NAME: QCHPCIIN.WEN
- E7/14/93 12:53 787905538417463837
?03 P. 0',
IN 93-XX
July xx. 1993 This infiIrmation notice requires no specific action noticet please contact
or written response. It
you have any questions about the information inthis
the tech lcal contmct listed below or the appropriate Office of Nuclear
Roactor r.gulmtion (NRR) project manager.
Brian K. Grimes, Director
Division of sOrating RGOM Support
Office of Nuclear Reactor Regulation
Technic~l contacts Clark Vanderniet, R-II1
(708) 790-5594 Oavid Skeen NRR
(301) 604-1174 Attach 4 nt: List of Recently Issued NRC Information Notices
._
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J \1 IN 93-XX
July xx, 1993 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 Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Clark Vanderniet, R-III
(708) 790-5594 David Skeen, NRR
(301) 504-1174 Attachment: List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE I
OFFICE *OEAB:DORS *TECH:ED _ i'O
_GC W DRS:R-III
NAME DSkeen JMain PWen CVanderniet
DATE 07/08/93 07/08/93 07/ W/93 07/ /93 C:DRS:RIII SC:OEAB:DORS C:OEAB:DORS C:SPLB:DSSA D:DSSA
GWright RDenning AChaffee CEMcCracken ACThadani
07/ /93 J07/ .
/93
.I
07/ /93 07/ /93 07/ /93 C:OGCB:DORS D:DORS
GHMarcus BKGrimes
07/ /93 07/ /93 DOCUMENT NAME: QCHPCIIN.WEN
I
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OFC OEAB:DORS SC/OEAB:DORS PUB:ADM C/OEAB:DORS
NAME DSkeen o RDennig Tech Ed T7avLY AChaffee
[DATE 17 /g/93 / /93 7/P /93 / /93 OFC OGCB:DORS C/DRS/R-III DRS/R-III
NAME PWen GWright CVanderniet
DATE / /93 / /93 / /93 OFC TECH BRANCH CHF TECH BR C/OGCB:DORS D/DORS
NAME l GMarcus l BGrimes
DATE / /93 / /93 / /93 1 / /93 l
[OFFICIAL RECORD COPY]
DOCUMENT NAME: IN93 XX.QC1
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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