Vibration Caused by Increased Recirculation Flow in a Boiling Water ReactorML031060310 |
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: |
03/09/1995 |
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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-95-016, NUDOCS 9503030302 |
Download: ML031060310 (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>. |
.7 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION .
WASHINGTON, D.C. 20555 March 9, 1995 NRC INFORMATION NOTICE 95-16: VIBRATION CAUSED BY INCREASED RECIRCULATION
FLOW IN A BOILING WATER REACTOR
Addressees
water
All holders of operating licenses or construction permits for boiling
reactors (BWRs).
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information by
notice to alert addressees to the potential for resonance vibration causedthat
an increase in reactor coolant recirculation flow rates. It is expected
facilities
recipients will review the information for applicability to their However, and consider actions, as appropriate, to avoid similar problems.
suggestions contained in this information notice are not NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
Unit 2 On June 21, 1994, the operators at Susquehanna Steam Electric Station rate of
raised the reactor coolant recirculation flow rate from the normal
Mlb/hr] as part of a testing
about 45 Mkg/hr [100 Mlb/hr] to 49 Mkg/hr [108 with the
program for an approved uprate in reactor power. The following day, noted
recirculation pump speed at 1570 to 1580 rpm (95 percent), the operators
These included
a number of abnormal indications of significant vibration. and
vibration of the containment instrument gas piping outside the containment
in the Lontrol
vibration of the suppression pool hatch covers. The operators
from the
room noted a low-frequency pulsating hum, which appeared to be coming
primary containment structure.
of the
The licensee attributed the excessive vibration to the increased speed
recirculation pumps. Consequently, on June 23 the operators systematically
speed of both
lowered the pump speed while monitoring the vibration. When the and noise
of the recirculation pumps was lowered to 1515 rpm, the vibration
had
levels returned to normal. The licensee estimated that the vibration at what
persisted for approximately 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />, although it was not clear then
a
time and flow rate the vibration actually started. The licensee performed and concluded
thorough evaluation of the effects of the vibration on the plant
that
that it had not caused any damage. The licensee also concluded flow rate of
maintaining the recirculation pumps at 1515 rpm, with a resulting
limited the
46.7 Mkg/hr [103 Mlb/hr], was acceptable and administratively
recirculation pumps to this speed.
9503030302 a
IN 95-16 March 9, 1995 The licensee conducted a second increased reactor recirculation flow test
program on Unit 2 during the second week in December 1994, increasing the flow
rate in steps from 46.7 Mkg/hr [103 Mlb/hr] to 49 Mkg/hr [108 Mlb/hr]. At
each pump speed plateau, the licensee deliberately varied the speed difference
between the two pumps from 0 to 2 percent of the average pump speed. When the
flow rate reached 47.6 Mkg/hr [105 Mlb/hr], the vibration noise phenomena
reappeared with the most pronounced effect occurring with a difference in
speed between the two pumps of 2 percent.
Discussion
The licensee has concluded that the vibration was caused by pressure pulses
emitted from the recirculation pumps as the pump impeller vanes passed the
pump openings. These pulses were amplified by an as yet undefined resonating
mechanism. The pumps are manufactured by Byron Jackson. They are of the
centrifugal type and have five vane impellers. The 1570-rpm to 1580-rpm pump
speed when multiplied by the number of vanes corresponds to the measured
131 Hz frequency of the vibration that was measured at the suppression pool
hatch covers. This frequency also correlates well with the natural frequency
of the hatch covers, which was measured to be 133 Hz. The low-frequency
modulation is caused by a slight difference in the frequency of the two
recirculation pumps, causing the two pumps to alternately go in and out of
synchronization with respect to vane passage of the respective pump openings.
As this occurs, the vane-generated pressure pulses tend to alternately
reinforce and cancel each other, resulting in a modulation of the frequency.
The licensee has established a working group to identify the vibration- amplifying mechanism. It is coordinating this investigation with General
Electric, the reactor supplier. The NRC staff will continue to monitor the
investigation.
Vibration attributable to high recirculation fl w-has been noted at several
nuclear power plants in the past. Hope C has experienced excessive
vibration on several occasions when the reactor recirculation flow was above
47.4 Mkg/hr [104.5 Mlb/hr]. On September 18, 1987, excessive vibration caused
two leaks from the recirculation flow instruments. The Hope Creek licensee
now monitors the recirculation system for excessive vibration during end-of- cycle coastdown periods and, if excessive vibration is detected, reduces
recirculation flow.
In the fall of 1989, Quad Cities Unit 2 experienced a harmonic vibration
during reactor recirculation system coastdown tests when the pump speed passed
420 rpm. The licensee attributed the vibration to the vane passing frequency
excitation phenomenon and established an administrative limit on recirculation
flow to minimize the possibility of a recurrence.
In September 1992, the Browns Ferry Unit 2 licensee increased the
recirculation pump speed in preparation for an end of cycle coastdown. The
reactor experienced a resonant vibration when the recirculation pump speed was
near 1500 rpm. The licensee administratively limited the pump speed to less
than this value.
IN 95-16 March 9, 1995 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager. /7
6 Brian K. Grimes, irector
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 415-2789 (301) 415-1402 T. Greene, NRR
(301) 415-1175 Attachment:
List of Recently Issued NRC Information Notices
Add
GeV L rr-A-ell4d-
I'Atachment
IN 95-16 March 9, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Subject Issuance Issued to
Notice No.
Inadequate Logic Testing 03/07/95 All holders of OLs or CPs
95-15 for nuclear power reactors.
of Safety-Related Circuits
Susceptibility of Con- 02/28/95 All holders of OLs or CPs
95-14 for nuclear power reactors.
tainment Sump Recircula- tion Gate Valves to
Pressure Locking
Potential for Data 02/24/95 All holders of OLs or CPs
95-13 for nuclear power reactors.
Collection Equipment to
Affect Protection System
Performance
Potentially Nonconforming 02/21/95 All holders of OLs or CPs
95-12 for nuclear power reactors.
Fasteners Supplied by
A&G Engineering II, Inc.
Failure of Condensate 02/24/95 All holders of OLs or CPs
95-11 for nuclear power reactors.
Piping Because of Erosion/
Corrosion at a Flow- Straightening Device
Potential for Loss of 02/10/95 All holders of OLs or CPs
95-10 for nuclear power reactors.
Supp. 1 Automatic Engineered
Safety Features
Actuation
Potential for Loss of 02/03/95 All holders of OLs or CPs
95-10 for nuclear power reactors.
Automatic Engineered
Safety Features
Actuation
Use of Inappropriate 01/31/95 All holders of OLs or CPs
95-09 for nuclear power reactors.
Guidelines and Criteria
for Nuclear Piping and
Pipe Support Evaluation
and Design
Inaccurate Data Obtained 01/30/95 All holders of OLs or CPs
95-08 for nuclear power reactors.
with Clamp-On Ultrasonic
Flow Measurement Instruments
OL = Operating License
CP = Construction Permit
4 I
"' < IN 95-16 March 9, 1995 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 415-2789 (301) 415-1402 T. Greene, NRR
(301) 415-1175 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-16.IN
- See orevious concurrences
OECB:DOPS* PUB:ADM*l EMEB:DE* PDI-1:DRPE*
DKirkpatrick MMejak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/94 11/8/94 10/18/94 C/EMEB:DE* D/DE* OECB:DOPS* SC/OECB:DOPS*
RWessman BSheron TGreene EGoodwin
01/29/95 02/08/95 02/13/a,5 02/21/95 OECB:DOPS* C/OECB:DOPS DA"
RKiessel AChaffee* LB 1_ __ __
02/21/95 03 & /95
02/21/95 OFFICIAL RECORD COPY
IN 95-xx
February xx, 1995 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 415-2789 (301) 415-1402 T. Greene, NRR
(301) 415-1175 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: S:\DOPS_SEC\RCIRCVIB
- See previous concurrences
OECB:DOPS* PUB:ADM* EMEB:DE* PDI-1:DRPE*
DKirkpatrick MMeJak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/94 11/8/94 10/18/94 C/EMEB:DE* D/DE* OECB:DOPS* SC/OECB:DOPS*
RWessman BSheron TGreene EGoodwin
01/29/95 02/08/95 02/13/95 02/21/95 OECB:DOPS* C/OECB:DOPS D/DOPS _
RKiessel AChaffee* BGrime_ _ _)_
02/21/95 02/21/95 02/ /95 OFFICIAL RECORD COPY
K> IN 95-xx
February xx, 1995 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 415-2789 (301) 415-1402 T. Greene, NRR
(301) 415-1175 Attachment:
List of Recently Issued NRC Information Notices
OECB:DOPS* PUB:ADM* lEMEB:DE* PDI-1:DRPE*
DKirkpatrick MMeJak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/94 11/8/94 10/18/94 C/EMEB:DE* D/DE* OECB:DOPS* SC/OECB:DOPS N
RWessman BSheron TGreene EGoodwin
1/29/95 2/08/95 2/13/95 2/2/5 OECB:DOPS* C/OECB:D1K9 D/DOPS
RKiessel AChaffee BGrimes
2/21/95 2/J /95 1 2/ /95
- See previous concurrences.
DOCUMENT NAME: G:\DON\RCIRCVIB
V. IN 95-xx
February xx, 1995 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 415-2789 (301) 415-1402 T. Greene, NRR
(301) 415-1175 Attachment:
List of Recently Issued NRC Information Notices
OECB:DOPS* PUB:ADM* EMEB:DE* PDI-1:DRPE*
DKirkpatrick MMejak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/9A 11/8/94 10/18/94
- C/EMEB:DE* D/D a OECB:DOPS _SC/OECB:DOPS l 9 EGoodwin
"'2P
RWessman BShg 7 A TGreene
1/29/95 2/ /95 2//3/95 2/ /95 OECB:DOPS C/OECB:DOPS D/DOPS l
RKiessel & e AChaffee BGrimes
21/95 2/ /95 2/ /95 See previous concurrences.
.7
<
K> IN 95-xx
Januray xx, 1995 This information notice requires no specific action or written response. If
you have any questions ibbut 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: P. Y. Chen, NRR C. Poslusny, NRR
(301) >8K-2789 (301) 50-1402
4Ar
T. Greene, NRR
(301) 9Sq-1175
4,1 Attachment:
List of Recently Issued NRC Information Notices
OECB:DOPS* PUB:ADM* EMEB:DE* PDI-1:DRPE*
DKirkpatrick lMMejak (Tech Ed) PYChen CPoslusny
- 10/12/94 10/13/94 11/8/94 10/18/94 C/EMEB:DE D/DE If yv OECB:DOPS SC/OECB:DOPS
RWessman BSheron TGreene EGoodwin
1 /95 IM I/ /95 1/ /95 I/ /95 OECB:DOPS C/OECB:DOPS D/DOPS
RKiessel AChaffee BGrimes l
1/ /95 1/ /95 1/ /95
- See previous concurrences.
1X3 V-( I IuC
z
K> IN 94-xx
November xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this hotice, 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: P. Y. Chen, NRR C. Poslusny, NRR
(301) 504-2789 (301) 504-1402 T. Greene, NRR
(301) 504-1175 Attachment:
List of Recently Issued NRC Information Notices
OECB:DOPS* PUB:ADM* EMEB:DE PDI-1:DRPE*
DKirkpatrick MMejak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/94 11/8 /94 10/18/94 C/EMEB:DE D/DE OECB:DOPS SC/OECB:DOPS
RWessman BSheron TGreene EGoodwin
11/ 1// /9r 11/ /94 OECB:DOPS C/OECB:DOPS D/DOPS
RKiessel AChaffee BGrimes
11/ /94 11/ /94 11/ /94
- See previous concurrences.
I
IN 94-xx
October xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Project Support
Office of Nuclear Reactor Regulation
Technical contacts: P. Y. Chen, NRR C. Poslusny, NRR
(301) 504-2789 (301) 504-1402 T. Greene, NRR
(301) 504-1175 Attachment:
List of Recently Issued NRC Information Notices
1-0
%&%-"4Q'i. 111
. V
OECB:DOPS* PUB:ADM* EMEB:DE PDI-1:DRPE d
DKirkpatrick MMejak (Tech Ed) PYChen CPoslusny
10/12/94 10/13/94 10/ /94 10/ %/94 C/EMEB:DE D/DE OECB:DOPS SC/OECB:DOPS
RWessman BSheron TGreene EGoodwin
10/ /94 10/ /94 10/ /94 10/ /94 OECB:DOPS C/OECB:DOPS DD/DOPS D/DOPS
RKiessel AChaffee BLiaw BGrimes
10/ /94 10/ /94 10/ /94 10/ /94
- See previous concurrences.
|
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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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