Control Room Staffing Below Minimum Regulatory RequirementsML031060197 |
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 |
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Issue date: |
04/24/1995 |
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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-95-023, NUDOCS 9504180074 |
Download: ML031060197 (9) |
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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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Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear 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 STATt' ' '
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 April 24, 1995 NRC INFORMATION NOTICE 95-23: CONTROL ROOM STAFFING BELOW MINIMUM
REGULATORY REQUIREMENTS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors and all licensed operators and senior operators at those reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to several instances in which control room staffing
fell below regulatory requirements. It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as appropriate, to avoid similar problems. This information notice
establishes no new NRC requirements; therefore, no specific action or written
response is required.
Description of Circumstances
From 1992 through 1994, a number of events occurred where facilities failed to
maintain the required number of licensed reactor operators (ROs) or senior
reactor operators (SROs) in the control room or at the controls of the
facility as required by 10 CFR 50.54(k), 10 CFR 50.54(m)(2)(iii), and facility
Technical Specifications and procedures.
On June 3, 1992, the senior nuclear shift supervisor (a licensed SRO) at Hope
Creek turned over responsibility for the control room to the nuclear shift
supervisor (also a licensed SRO) in order to attend a staff meeting. Sometime
later, the nuclear shift supervisor, believing that he had turned over command
of the control room to another licensed SRO, in this case the shift technical
advisor, left the control room to check an equipment problem in the plant.
The shift technical advisor, believing that the turnover of responsibility was
yet to occur, returned to the work control office outside the control room.
The nuclear shift supervisor and the shift technical advisor left the control
room via different exits, thinking that the other would remain in the control
room. The ROs noted their absence and paged the shift technical advisor, who
returned within 3 minutes.
On October 9, 1992, the only SRO in the Nine Mile Point 1 control room (the
shift supervisor) violated 10 CFR 50.54(m)(2)(iii) when he left the control
room for 5 minutes with the plant at full power.
On February 14, 1993, the only SRO in the South Texas Project Unit 2 control
room (the unit supervisor) violated 10 CFR 50.54(m)(2)(iii) when he left the
95041800744Add ok PD9 T h0f-ce
hE Us of 7,5OWN
IN 95-23 April 24, 1995 control room to observe an RO perform a portion of a surveillance procedure.
The unit supervisor was gone for about 40 seconds while the plant was in hot
shutdown; he immediately realized his error and returned to the control room.
On October 14, 1993, the control room staffing at the Byron Station went below
the minimum requirements in 10 CFR 50.54(m)(2)(iii) for approximately
22 minutes while one unit was shutdown and the other unit was at full power.
The senior control room engineer (a licensed SRO) in charge of the dual-unit
control room was relieved by the Unit 2 shift foreman (a licensed SRO not
usually stationed in the control room) for a routine facility tour. The
Unit 2 shift foreman, then the only SRO in the control room, subsequently left
to investigate an equipment problem. The ROs did not realize that an SRO was
not present until an equipment operator contacted the control room to speak to
the senior control room engineer. The Unit 2 shift foreman subsequently
returned to the control room.
On April 22, 1994, the licensed operators at H. B. Robinson violated
10 CFR 50.54(m)(2)(iii) when they all vacated the Nat the controls" area for a
period of 5 to 10 seconds while the plant was at full power. The on-duty
shift technical advisor, who was not a licensed RO or SRO, noted that the last
operator had departed and informed that operator that he was required to stay
in the "at the controls' area. The operator returned immediately.
On September 28, 1994, the nuclear shift supervisor at the Hope Creek Station, who had responsibility for the control room, inadvertently walked out of the
control room to the adjacent work control office for approximately 18 seconds, thereby leaving the control room with no SRO with an active license.
On November 28, 1994, the control room staffing at Shearon Harris fell below
the minimum requirements in 10 CFR 50.54(m)(2)(iii) for approximately
4 minutes while the plant was at power. The 2 ROs on shift vacated the
control room, leaving the SRO and 3 nonlicensed operators to watch the plant.
The nonlicensed operators were assigned to the primary and balance-of-plant
controls and to the SRO desk. Each was in training under the direct
supervision of a licensed RO, but they were not performing any licensed duties
at the time. When the trainee at the balance-of-plant position realized that
he was without the direct supervision of a licensed operator, the SRO paged an
RO to return to the control room.
Discussion
10 CFR 50.54(k) and 10 CFR 50.54(m)(2)(Iii) require that an SRO be in the
control room at all times when a nuclear power unit is in an operational mode
other than cold shutdown or refueling. In addition to that SRO, the
regulations further require that an RO or another SRO be present at the
controls at all times. Furthermore, 10 CFR 55.53(d) states that all licensed
operators are subject to, and must observe, all applicable rules, regulations, and orders of the NRC. The NRC has taken enforcement action against both
facility licensees and individual licensed operators for failing to meet these
requirements in certain of the above instances.
IN 95-23 April 24, 1995 Several facilities have identified root causes of failing to meet manning
requirements; those causes span human error, inadequate communications, lack
of understanding of proficiency watch requirements, false perceptions of
adequate shift staffing, and failure to understand supervisory
responsibilities. Among the corrective actions and preventive measures
licensees have adopted to address this problem are counseling and discipline, specific training on regulatory requirements, and physical adaptations to
security cards such as clips or bands that serve as reminders to operators not
to leave the control room.
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. Grmes, Director Xr
Division of Projects Supportl
Office of Nuclear Reactor Regulation
Technical contacts: Stuart A. Richards, NRR
(301) 415-1031 Neal K. Hunemuller, NRR
(301) 415-1152 Attachment:
List of Recently Issued NRC Information Notices
Attachment
IN 95-23 April 24, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
95-22 Hardened or Contaminated 04/21/95 All holders of OLs or CPs
Lubricants Cause Metal
Clad Circuit Breaker
Failures
95-21 Unexpected Degradation 04/20/95 All holders of OLs or CPs
of Lead Storage Batteries for nuclear power reactors.
94-64, Reactivity Insertion 04/06/95 All holders of OLs or CPs
Supp. 1 Transient and Accident for nuclear power reactors
Limits for High Burnup
Fuel
95-18, Potential Pressure-Locking 03/31/95 All holders of OLs or CPs
Supp. 1 of Safety-Related Power- for nuclear power reactors.
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
95-19 Failure of Reactor Trip 03/22/95 All holders of OLs or CPs
Breaker to Open Because for nuclear power reactors.
of Cutoff Switch Material
Lodged in the Trip Latch
Mechanism
95-18 Potential Pressure-Locking 03/15/95 All holders of OLs or CPs
of Safety-Related Power- for nuclear power reactors.
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.
95-16 Vibration Caused by 03/09/95 All holders of OLs or CPs
Increased Recirculation for boiling water reactors.
Flow in a Boiling Water
Reactor
OL - Operating License
CP - Construction Permit
IN 95-23 April 24, 1995 Several facilities have identified root causes of failing to meet manning
requirements; those causes span human error, inadequate communications, lack
of understanding of proficiency watch requirements, false perceptions of
adequate shift staffing, and failure to understand supervisory
responsibilities. Among the corrective actions and preventive measures
licensees have adopted to address this problem are counseling and discipline, specific training on regulatory requirements, and physical adaptations to
security cards such as clips or bands that serve as reminders to operators not
to leave the control room.
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 Projects Support
Office of Nuclear Reactor Regulation
Technical contacts: Stuart A. Richards, NRR
(301) 415-1031 Neal K. Hunemuller, NRR
(301) 415-1152 Attachment:
List of Recently Issued NRC Information Notices
DOCUMENT NAME: 95-23.IN
with attachment/enclosure K
To receive a copy of this document, indicate in the box C=Copy w/o attachment/enclosure E=Copy
OFFICE *HOLB/DRCH lIE_l *HOLB/DRCH E *HOLB/DRCH E *TECH/ED
NAME GUsova:rc AMendila SRichards RSanders
DATE 02/16/95 02/17/95 02/28/95 02/21/95 lOFFICE *DIR/DRCH *OECB OECB* D:DOPS/NRR l
NAM BBoger NHunemuller AChaffee/RLD BKGrimes
DATE 03/13/95 03/14/95 03/15/95 04/ I95 Aj
OFFICIAL RECORD COPY
IN 95-XX
April XX, 1995 adequate shift staffing, and failure to understand supervisory
responsibilities. Among the corrective actions and preventive measures
licensees have adopted to address this problem are counseling and discipline, specific training on regulatory requirements, and physical adaptations to
security cards such as clips or bands that serve as reminders to operators not
to leave the control room.
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 Projects Support
Office of Nuclear Reactor Regulation
Technical contacts: Stuart A. Richards, NRR
(301) 415-1031 Neal K. Hunemuller, NRR
(301) 415-1152 Attachment: List of Recently Issued
NRC Information Notices
DOCUMENT NAME: G:\NKH\IN-OUT.SXG
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DATE 03/13/95 03 .14.95j /__/n,
03/15/95 ____95_-
OFFILIAL KLLUKU LUPY
IN 95-XX
March XX, 1995 adequate shift staffing, and failure to understand supervisory
responsibilities. Among the corrective actions and preventive measures
licensees have adopted to address this problem are counseling and discipline, specific training on 10 CFR requirements, and physical adaptations to security
cards such as clips or bands that serve as reminders to operators not to leave
the control room.
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 Projects Support
Office of Nuclear Reactor Regulation
Technical contacts: Stuart A. Richards, NRR
(301) 415-1031 Neal K. Hunemuller, NRR
(301) 415-1152 Attachment: List of Recently Issued
NRC Information Notices
DOCUMENT NAME: G:\NKH\IN-OUT.SXG
- See previous concurrence 'N' - No copy
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IN 95-XX
March XX, 1995 Discussion
Facilities should consider reviewing their procedures and training programs to
ensure that the control room manning requirements of 10 CFR Part 50 are met at
all times.
Several facilities have identified root causes of failing to meet these
requirements; those causes span human error, inadequate communications, lack
of understanding of proficiency watch requirements, false perceptions of
adequate shift staffing, and failure to understand supervisory
responsibilities. Among the corrective actions and preventive measures
licensees have adopted to address this problem are counseling and discipline, specific training on 10 CFR requirements, and physical adaptations to security
cards such as clips or bands that serve as reminders to operators not to leave
the control room.
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 Projects Support
Office of Nuclear Reactor Regulation
Technical contact: Stuart A. Richards, NRR \ tJlged
JAP
(301) 415-1031 AJAX I '
Attachments: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G: WSOV\IN-OUT.SXG
- See previous concurrence wEe Copy with attachment/enclosure 'N' - No copy
To receive a copy of this document, Indicate in the box: ACT - Copy without attachment/enciosure =
OFFICE I*HOLB/DRCH E
- HOLB/DRCH E *HOLB/DRCH I E *TECH/ED DDIR/DRCH
AMendiola 1SRichards RSanders CThoamy-l
NAME GUsova:rc
DATE 102/16/95 02/17/95 102/28/95 , 02/21/95 Luz/ /95m
OFFICE DIR/DRCH l fl ECB OECB DOPS
NAME
DATE
JBoger
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/95 BKGrimes
/95
. elOFFICIAL RECORD COPY
t
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
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Projects Support
Office of Nuclear Reactor Regulation
Technical contact: Stuart A. Richards, NRR
(301) 415-1031 Attachments: List of Recently Issued NRC Information Notices
DOCUMENT NAME: G:\USOVA\IN-OUT.GMU
To receive a copy of this document. Indicate In the hax: C'
- COnv withnut attArhment1^nLb*. 'FW - CODY with *nachnantlrn'i *r E - lN -.Nnt
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NAME GUsova:rc AMendiola SRi chards ill--' RSanders CThomas
DATE 02/16/95 02/17/95 L /f8 /95 / /95
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NAME
DIR/DRCH
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AChaffee
102/21/95 DOPS
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DATE I / /95 / /95 / /95 / /95
0 1/ UMi-ILIAL KtLUKU LUPY
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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, Water hammer)
- 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, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- 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, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- 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, Topic: Hardened grease)
- 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, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- 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, Overspeed)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Overspeed)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Exemption Request, Overspeed, Manual Operator Action)
- 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, Underdose)
- 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: Commercial Grade, 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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