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| | issue date = 03/10/1986 | | | issue date = 03/10/1986 |
| | title = Loss of Offsite Power Caused by Problems in Fiber Optics Systems | | | title = Loss of Offsite Power Caused by Problems in Fiber Optics Systems |
| | author name = Jordan E L | | | author name = Jordan E |
| | author affiliation = NRC/IE | | | author affiliation = NRC/IE |
| | addressee name = | | | addressee name = |
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| | page count = 3 | | | page count = 3 |
| }} | | }} |
| {{#Wiki_filter:SSINS No.: 6835 HU OlIN 86-15 UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:SSINS No.: 6835 HU OlIN 86-15 UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| OFFICE OF INSPECTION | | OFFICE OF INSPECTION AND ENFORCEMENT |
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| ===AND ENFORCEMENT===
| | WASHINGTON, D.C. 20555 March 10, 1986 IE INFORMATION NOTICE NO. 86-15: LOSS OF OFFSITE POWER CAUSED BY PROBLEMS |
| WASHINGTON, D.C. 20555 March 10, 1986 IE INFORMATION | |
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| NOTICE NO. 86-15: LOSS OF OFFSITE POWER CAUSED BY PROBLEMS IN FIBER OPTICS SYSTEMS
| | IN FIBER OPTICS SYSTEMS |
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| ==Addressees== | | ==Addressees== |
| : | | : |
| All nuclear power reactor facilities | | All nuclear power reactor facilities holding an operating license (OL) or a |
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| holding an operating
| | construction permit (CP). |
| | |
| license (OL) or a construction
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| | |
| permit (CP). | |
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| ==Purpose== | | ==Purpose== |
| : This notice is to alert addressees | | : |
| | This notice is to alert addressees to recent instances of loss of offsite power |
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| to recent instances | | caused by problems with fiber optics systems used to control switchyard circuit |
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| of loss of offsite power caused by problems with fiber optics systems used to control switchyard
| | breakers. Recipients are expected to review the information for applicability |
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| circuit breakers.
| | to their facilities and consider actions, if appropriate, to preclude similar |
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| Recipients
| | problems occurring at their facilities. However, suggestions contained in this |
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| |
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| are expected to review the information
| | notice do not constitute NRC requirements; therefore, no specific action or |
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| for applicability
| | written response is required. |
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| to their facilities
| | ==Description of Circumstances== |
| | | : |
| and consider actions, if appropriate, to preclude similar problems occurring
| | Three recent instances of total loss of offsite power at nuclear power plants |
| | |
| at their facilities.
| |
| | |
| However, suggestions
| |
| | |
| contained
| |
| | |
| in this notice do not constitute
| |
| | |
| NRC requirements;
| |
| therefore, no specific action or written response is required.Description
| |
| | |
| of Circumstances: | |
| Three recent instances | |
| | |
| of total loss of offsite power at nuclear power plants were caused by problems with fiber optics control systems. Fiber optics systems are sometimes | |
| | |
| thought to be immune to radio frequency
| |
| | |
| interference
| |
| | |
| problems.However, at least one of these instances
| |
| | |
| was probably caused by interference
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| | |
| from a hand-held
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| | |
| radio in close proximity
| |
| | |
| to the tone relaying trip receivers
| |
| | |
| of the fiber optics system.On October 3, 1985, the Palo Verde Unit 1 nuclear power plant tripped from 52 percent power because of a total loss of offsite power. The loss of offsite power was caused by the apparent malfunction
| |
| | |
| of a multiplexer
| |
| | |
| in the fiber optics system that in turn controlled
| |
| | |
| breakers in the plant switchyard.
| |
| | |
| The loss of offsite power caused the starting and loading of the emergency
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| | |
| diesel generators
| |
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| |
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| that restored power to the engineered
| | were caused by problems with fiber optics control systems. Fiber optics systems |
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| safety features buses.On October 7, 1985, while shut down in Mode 3, Palo Verde Unit 1 again experienced
| | are sometimes thought to be immune to radio frequency interference problems. |
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| a loss of offsite power apparently
| | However, at least one of these instances was probably caused by interference |
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| because of a failure of the multiplexer.
| | from a hand-held radio in close proximity to the tone relaying trip receivers of |
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| Although some failed components
| | the fiber optics system. |
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| |
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| were identified, the ultimate cause of these failures of the fiber optics multiplexer
| | On October 3, 1985, the Palo Verde Unit 1 nuclear power plant tripped from 52 percent power because of a total loss of offsite power. The loss of offsite |
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| was never determined. | | power was caused by the apparent malfunction of a multiplexer in the fiber optics |
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| ===As a corrective===
| | system that in turn controlled breakers in the plant switchyard. The loss of |
| measure, control of the affected switchyard
| |
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| |
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| breakers was hardwired
| | offsite power caused the starting and loading of the emergency diesel generators |
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| and the multiplexer
| | that restored power to the engineered safety features buses. |
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| control was bypassed.8603050394 IN 86-15 March 10, 1986 On January 1, 1986, the River Bend nuclear power station experienced
| | On October 7, 1985, while shut down in Mode 3, Palo Verde Unit 1 again experienced |
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| a total loss of offsite power caused by the tripping of the preferred | | a loss of offsite power apparently because of a failure of the multiplexer. |
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| station transformers
| | Although some failed components were identified, the ultimate cause of these |
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| A and C at 0941, and approximately
| | failures of the fiber optics multiplexer was never determined. As a corrective |
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| 1 hour later, the tripping of the preferred station transformers
| | measure, control of the affected switchyard breakers was hardwired and the |
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| B and D. The plant was shut down at the time because of a reactor scram that occurred approximately
| | multiplexer control was bypassed. |
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| 6 hours earlier for unrelated
| | 8603050394 |
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| reasons.Investigation
| | IN 86-15 March 10, 1986 On January 1, 1986, the River Bend nuclear power station experienced a total |
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| indicated
| | loss of offsite power caused by the tripping of the preferred station transformers |
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| that the loss of offsite power event was not caused by a valid signal. Testing did show that hand-held
| | A and C at 0941, and approximately 1 hour later, the tripping of the preferred |
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| radios could have caused the loss of offsite power event. Two hand-held
| | station transformers B and D. The plant was shut down at the time because of |
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| radios, one 4 watts at 150 MHz and the other 5 watts at 450 MHz, caused system trips when keyed within 12 feet of the transmitters
| | a reactor scram that occurred approximately 6 hours earlier for unrelated reasons. |
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| and receivers
| | Investigation indicated that the loss of offsite power event was not caused by |
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| for the fiber optics system. Mobile radios of greater power located outside the building containing
| | a valid signal. Testing did show that hand-held radios could have caused the |
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| the fiber optics system would not cause spurious trips.At River Bend, the fiber optics transmitting
| | loss of offsite power event. Two hand-held radios, one 4 watts at 150 MHz and |
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| and receiving
| | the other 5 watts at 450 MHz, caused system trips when keyed within 12 feet of |
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| equipment
| | the transmitters and receivers for the fiber optics system. Mobile radios of |
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| is located in the turbine building and the Fancy Point substation, a distance of about 0.8 miles. The corrective
| | greater power located outside the building containing the fiber optics system |
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| measures adopted at River Bend include shielding
| | would not cause spurious trips. |
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| of the fiber optics transmitters
| | At River Bend, the fiber optics transmitting and receiving equipment is located |
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| and receivers, posting signs that prohibit use of radios near the fiber optics equipment, rewiring the equipment | | in the turbine building and the Fancy Point substation, a distance of about 0.8 miles. The corrective measures adopted at River Bend include shielding of the |
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| so that two channels instead of one are required for tripping, providing
| | fiber optics transmitters and receivers, posting signs that prohibit use of |
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| control room annunciation
| | radios near the fiber optics equipment, rewiring the equipment so that two |
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| of system status, training personnel | | channels instead of one are required for tripping, providing control room |
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| on restricted | | annunciation of system status, training personnel on restricted use of radios, installing a sequence-of-events recorder to diagnose any future events, and |
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| use of radios, installing
| | training personnel on resetting lockouts, including posting of operator aids. |
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| a sequence-of-events
| | Other problems caused by use of hand-held radios in nuclear power plants were |
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| recorder to diagnose any future events, and training personnel
| | discussed in IE Information Notice No. 83-83, "Use of Portable Radio Transmitters |
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| on resetting | | Inside Nuclear Power Plants," published on December 19, 1983. |
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| lockouts, including
| | No specific action or written response is required by this information notice. |
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| posting of operator aids.Other problems caused by use of hand-held
| | If you have questions about this matter, please contact the Regional Adminis- trator of the appropriate NRC regional office or this office. |
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| radios in nuclear power plants were discussed
| | EdwarqV. Jordan, Director |
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| in IE Information
| | Divisi of Emergency Preparedness |
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| Notice No. 83-83, "Use of Portable Radio Transmitters
| | and Engineering Response |
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| |
|
| Inside Nuclear Power Plants," published
| | Office of Inspection and Enforcement |
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| |
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| on December 19, 1983.No specific action or written response is required by this information
| | ===Technical Contact:=== |
|
| |
|
| notice.If you have questions
| | ===Eric Weiss, IE=== |
| | (301) 492-9005 Attachment: List of Recently Issued IE Information Notices |
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| |
|
| about this matter, please contact the Regional Adminis-trator of the appropriate
| | i |
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| NRC regional office or this office.EdwarqV. Jordan, Director Divisi of Emergency
| | Attachment 1 IN 86-15 March 10, 1986 LIST OF RECENTLY ISSUED |
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| |
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| ===Preparedness===
| | IE INFORMATION NOTICES |
| and Engineering
| |
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| |
|
| Response Office of Inspection
| | Information Date of |
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| |
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| and Enforcement
| | Notice No. Subject Issue Issued to |
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| |
|
| Technical
| | 86-14 PWR Auxiliary Feedwater Pump 3/10/86 All power reactor |
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| |
|
| Contact: Eric Weiss, IE (301) 492-9005 Attachment:
| | Turbine Control Problems facilities holding |
| List of Recently Issued IE Information
| |
|
| |
|
| Notices
| | an OL or CP |
|
| |
|
| i Attachment
| | 86-13 Standby Liquid Control 2/21/86 All BWR facilities |
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| |
|
| 1 IN 86-15 March 10, 1986 LIST OF RECENTLY ISSUED IE INFORMATION
| | System Squib Valves Failure holding an OL or CP |
|
| |
|
| NOTICES Information
| | To Fire |
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| |
|
| Date of Notice No. Subject Issue Issued to 86-14 86-13 86-12 86-11 84-69 Sup. 1 PWR Auxiliary
| | 86-12 Target Rock Two-Stage SRV 2/25/86 All power reactor |
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| |
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| Feedwater
| | Setpoint Drift facilities holding |
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| |
|
| Pump Turbine Control Problems Standby Liquid Control System Squib Valves Failure To Fire Target Rock Two-Stage
| | an OL or CP |
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|
| SRV Setpoint Drift Inadequate
| | 86-11 Inadequate Service Water 2/25/86 All power reactor |
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| Service Water Protection
| | Protection Against Core Melt facilities holding |
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| |
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| Against Core Melt Frequency Operation
| | Frequency an OL or CP |
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| |
|
| Of Emergency | | 84-69 Operation Of Emergency Diesel 2/24/86 All power reactor |
|
| |
|
| ===Diesel Generators===
| | Sup. 1 Generators facilities holding |
| Safety Parameter
| |
|
| |
|
| ===Display System Malfunctions===
| | an OL or CP |
| Failure Of Check And Stop Check Valves Subjected
| |
|
| |
|
| ===To Low Flow Conditions===
| | 86-10 Safety Parameter Display 2/13/86 All power reactor |
| Licensee Event Report (LER)Format Modification
| |
|
| |
|
| ===Lack Of Detailed Instruction===
| | System Malfunctions facilities holding |
| And Inadequate
| |
|
| |
|
| Observance
| | an OL or CP |
|
| |
|
| Of 3/10/86 2/21/86 2/25/86 2/25/86 2/24/86 2/13/86 2/3/86 2/3/86 2/3/86 All power reactor facilities | | 86-09 Failure Of Check And Stop 2/3/86 All power reactor |
|
| |
|
| holding an OL or CP All BWR facilities | | Check Valves Subjected To facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | Low Flow Conditions an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | 86-08 Licensee Event Report (LER) 2/3/86 All power reactor |
|
| |
|
| holding an OL or CP All power reactor facilities | | Format Modification facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | 86-07 Lack Of Detailed Instruction 2/3/86 All power reactor |
|
| |
|
| holding an OL or CP All power reactor facilities | | And Inadequate Observance Of facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | Precautions During Maintenance an OL or CP |
|
| |
|
| holding an OL or CP 86-10 86-09 86-08 86-07 Precautions
| | And Testing Of Diesel Generator |
|
| |
|
| ===During Maintenance===
| | Woodward Governors |
| And Testing Of Diesel Generator Woodward Governors OL = Operating
| |
|
| |
|
| License CP = Construction | | OL = Operating License |
|
| |
|
| Permit}} | | CP = Construction Permit}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Loss of Offsite Power Caused by Problems in Fiber Optics SystemsML031220597 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
03/10/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-015, NUDOCS 8603050394 |
Download: ML031220597 (3) |
|
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Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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 [[: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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </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 [[: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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
SSINS No.: 6835 HU OlIN 86-15 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 March 10, 1986 IE INFORMATION NOTICE NO. 86-15: LOSS OF OFFSITE POWER CAUSED BY PROBLEMS
IN FIBER OPTICS SYSTEMS
Addressees
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose
This notice is to alert addressees to recent instances of loss of offsite power
caused by problems with fiber optics systems used to control switchyard circuit
breakers. Recipients are expected to review the information for applicability
to their facilities and consider actions, if appropriate, to preclude similar
problems occurring at their facilities. However, suggestions contained in this
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Description of Circumstances
Three recent instances of total loss of offsite power at nuclear power plants
were caused by problems with fiber optics control systems. Fiber optics systems
are sometimes thought to be immune to radio frequency interference problems.
However, at least one of these instances was probably caused by interference
from a hand-held radio in close proximity to the tone relaying trip receivers of
the fiber optics system.
On October 3, 1985, the Palo Verde Unit 1 nuclear power plant tripped from 52 percent power because of a total loss of offsite power. The loss of offsite
power was caused by the apparent malfunction of a multiplexer in the fiber optics
system that in turn controlled breakers in the plant switchyard. The loss of
offsite power caused the starting and loading of the emergency diesel generators
that restored power to the engineered safety features buses.
On October 7, 1985, while shut down in Mode 3, Palo Verde Unit 1 again experienced
a loss of offsite power apparently because of a failure of the multiplexer.
Although some failed components were identified, the ultimate cause of these
failures of the fiber optics multiplexer was never determined. As a corrective
measure, control of the affected switchyard breakers was hardwired and the
multiplexer control was bypassed.
8603050394
IN 86-15 March 10, 1986 On January 1, 1986, the River Bend nuclear power station experienced a total
loss of offsite power caused by the tripping of the preferred station transformers
A and C at 0941, and approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> later, the tripping of the preferred
station transformers B and D. The plant was shut down at the time because of
a reactor scram that occurred approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> earlier for unrelated reasons.
Investigation indicated that the loss of offsite power event was not caused by
a valid signal. Testing did show that hand-held radios could have caused the
loss of offsite power event. Two hand-held radios, one 4 watts at 150 MHz and
the other 5 watts at 450 MHz, caused system trips when keyed within 12 feet of
the transmitters and receivers for the fiber optics system. Mobile radios of
greater power located outside the building containing the fiber optics system
would not cause spurious trips.
At River Bend, the fiber optics transmitting and receiving equipment is located
in the turbine building and the Fancy Point substation, a distance of about 0.8 miles. The corrective measures adopted at River Bend include shielding of the
fiber optics transmitters and receivers, posting signs that prohibit use of
radios near the fiber optics equipment, rewiring the equipment so that two
channels instead of one are required for tripping, providing control room
annunciation of system status, training personnel on restricted use of radios, installing a sequence-of-events recorder to diagnose any future events, and
training personnel on resetting lockouts, including posting of operator aids.
Other problems caused by use of hand-held radios in nuclear power plants were
discussed in IE Information Notice No. 83-83, "Use of Portable Radio Transmitters
Inside Nuclear Power Plants," published on December 19, 1983.
No specific action or written response is required by this information notice.
If you have questions about this matter, please contact the Regional Adminis- trator of the appropriate NRC regional office or this office.
EdwarqV. Jordan, Director
Divisi of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact:
Eric Weiss, IE
(301) 492-9005 Attachment: List of Recently Issued IE Information Notices
i
Attachment 1 IN 86-15 March 10, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
86-14 PWR Auxiliary Feedwater Pump 3/10/86 All power reactor
Turbine Control Problems facilities holding
an OL or CP
86-13 Standby Liquid Control 2/21/86 All BWR facilities
System Squib Valves Failure holding an OL or CP
To Fire
86-12 Target Rock Two-Stage SRV 2/25/86 All power reactor
Setpoint Drift facilities holding
an OL or CP
86-11 Inadequate Service Water 2/25/86 All power reactor
Protection Against Core Melt facilities holding
Frequency an OL or CP
84-69 Operation Of Emergency Diesel 2/24/86 All power reactor
Sup. 1 Generators facilities holding
an OL or CP
86-10 Safety Parameter Display 2/13/86 All power reactor
System Malfunctions facilities holding
an OL or CP
86-09 Failure Of Check And Stop 2/3/86 All power reactor
Check Valves Subjected To facilities holding
Low Flow Conditions an OL or CP
86-08 Licensee Event Report (LER) 2/3/86 All power reactor
Format Modification facilities holding
an OL or CP
86-07 Lack Of Detailed Instruction 2/3/86 All power reactor
And Inadequate Observance Of facilities holding
Precautions During Maintenance an OL or CP
And Testing Of Diesel Generator
Woodward Governors
OL = Operating License
CP = Construction Permit
|
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|
list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986, Topic: Feedwater Heater)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986, Topic: GOTHIC)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Fire Barrier, Overspeed trip, Overspeed, Water hammer)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib, Local Leak Rate Testing, Integrated leak rate test)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
... further results |
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