|
|
Line 14: |
Line 14: |
| | page count = 4 | | | page count = 4 |
| }} | | }} |
| {{#Wiki_filter:11$S ORIGINAL SSINS No.: 6835 IN 86-57 UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:11$S ORIGINAL SSINS No.: |
| | IN 86-57 6835 UNITED STATES |
|
| |
|
| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
|
| |
|
| OFFICE OF INSPECTION | | OFFICE OF INSPECTION AND ENFORCEMENT |
|
| |
|
| ===AND ENFORCEMENT===
| | WASHINGTON, D.C. 20555 July 11, 1986 IE INFORMATION NOTICE NO. 86-57: OPERATING PROBLEMS WITH SOLENOID OPERATED |
| WASHINGTON, D.C. 20555 July 11, 1986 IE INFORMATION | |
|
| |
|
| NOTICE NO. 86-57: OPERATING
| | VALVES AT NUCLEAR POWER PLANTS |
| | |
| PROBLEMS WITH SOLENOID OPERATED VALVES AT NUCLEAR POWER PLANTS
| |
|
| |
|
| ==Addressees== | | ==Addressees== |
| : | | : |
| All nuclear power reactor facilities | | All nuclear power reactor facilities holding an operating license or a |
| | |
| holding an operating | |
| | |
| license or a construction | |
|
| |
|
| permit. | | construction permit. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| : This notice is to advise recipients | | : |
| | This notice is to advise recipients of a series of valve failures that have |
|
| |
|
| of a series of valve failures that have occurred recently at several nuclear power plants. It is expected that recipi-ents will review the events discussed
| | occurred recently at several nuclear power plants. It is expected that recipi- ents will review the events discussed below for applicability to their facili- ties and consider actions, if appropriate, to preclude similar valve failures |
|
| |
|
| below for applicability
| | occurring at their facilities. However, suggestions contained in this notice |
|
| |
|
| to their facili-ties and consider actions, if appropriate, to preclude similar valve failures occurring
| | do not constitute NRC requirements; therefore, no specific action or written |
|
| |
|
| at their facilities.
| | response is required. |
|
| |
|
| However, suggestions
| | ==Description of Circumstances== |
| | | : |
| contained
| | The NRC has received reports from licensees of operating nuclear power plants |
| | |
| in this notice do not constitute
| |
| | |
| NRC requirements;
| |
| therefore, no specific action or written response is required.Description
| |
| | |
| of Circumstances: | |
| The NRC has received reports from licensees | |
| | |
| of operating | |
| | |
| nuclear power plants involving | |
| | |
| failures of certain valves that are actuated by solenoid operated valves (SOVs) to operate properly.
| |
| | |
| These failures have adversely
| |
| | |
| affected the intended functions
| |
| | |
| of the main steam isolation
| |
| | |
| system, pressure relief and fluid control systems. Attachment
| |
| | |
| 1 to this information
| |
| | |
| notice describes
| |
| | |
| the failure events and the corrective
| |
| | |
| actions taken.Discussion:
| |
| In most of the cases described
| |
| | |
| in Attachment
| |
| | |
| 1, the cause for triggering
| |
|
| |
|
| the event was attributed
| | involving failures of certain valves that are actuated by solenoid operated |
|
| |
|
| to a malfunctioning | | valves (SOVs) to operate properly. These failures have adversely affected the |
|
| |
|
| SOV that served as a pilot valve. This in turn resulted in the malfunction
| | intended functions of the main steam isolation system, pressure relief and |
|
| |
|
| of the associated
| | fluid control systems. Attachment 1 to this information notice describes the |
|
| |
|
| main valve. The failures of the SOVs can be traced to the following
| | failure events and the corrective actions taken. |
|
| |
|
| different
| | Discussion: |
| | In most of the cases described in Attachment 1, the cause for triggering the |
|
| |
|
| causes: (1) potentially
| | event was attributed to a malfunctioning SOV that served as a pilot valve. This |
|
| |
|
| high-temperature
| | in turn resulted in the malfunction of the associated main valve. The failures |
|
| |
|
| ambient conditions
| | of the SOVs can be traced to the following different causes: (1) potentially |
|
| |
|
| are not being continuously | | high-temperature ambient conditions are not being continuously monitored in areas |
|
| |
|
| monitored
| | where SOVs are installed and operating in an energized state, (2) hydrocarbon |
|
| |
|
| in areas where SOVs are installed
| | contaminants, probably because backup air systems (e.g., plant service or shop |
|
| |
|
| and operating
| | air systems) are being used periodically and are not designed to "oil-free" |
| | | specifications as required for Class IE service, (3) chloride contaminants |
| in an energized
| |
| | |
| state, (2) hydrocarbon
| |
| | |
| contaminants, probably because backup air systems (e.g., plant service or shop air systems) are being used periodically
| |
| | |
| and are not designed to "oil-free" specifications | |
| | |
| as required for Class IE service, (3) chloride contaminants | |
|
| |
|
| causing open circuits in coils of the SOVs, possibly as a result of questionable | | causing open circuits in coils of the SOVs, possibly as a result of questionable |
|
| |
|
| handling, packaging, and storage procedures, (4) an active replacement | | handling, packaging, and storage procedures, (4) an active replacement parts |
| | |
| parts program associated | |
| | |
| with the elastomers
| |
| | |
| and other short-lived
| |
| | |
| subcomponents
| |
| | |
| used in SOVs has not been adequately
| |
| | |
| maintained, and (5) lubricants
| |
| | |
| have been used excessively
| |
| | |
| during maintenance.
| |
| | |
| ASCO provides installation
| |
| | |
| and maintenance
| |
| | |
| 8607090425 Attachment
| |
| | |
| 1 IN 86-57 July 11, 1986 b. Viton has superior high-temperature
| |
| | |
| performance
| |
| | |
| when compared to EP and is impervious
| |
| | |
| to hydrocarbons.
| |
| | |
| Its major disadvantage
| |
| | |
| is that it is less resistant
| |
| | |
| to radiation
| |
| | |
| than EP by a factor of ten. ASCO recommends
| |
| | |
| Viton for applications
| |
| | |
| that are not oil-free and where radiation
| |
| | |
| levels do not exceed 20 megarads.On the basis of a licensee review of the Brunswick
| |
| | |
| ===Station maintenance===
| |
| history, which showed the performance
| |
| | |
| of Viton to be satisfactory
| |
| | |
| in ASCO valves, and the available
| |
| | |
| literature
| |
| | |
| and industry experience, the licensee replaced all Unit 2 dual solenoid valves with valves having Viton seats and seals. Because Viton has a 20-megarad
| |
| | |
| limit, the licensee plans to replace these elastomers
| |
| | |
| every 3.3 years to meet environmental
| |
| | |
| qualifica- tion requirements
| |
| | |
| for the MSIV application.
| |
| | |
| After replacing
| |
| | |
| the faulty valves with valves having Viton disc and seal material, the licensee experienced
| |
| | |
| several SOV failures resulting
| |
| | |
| from open circuits of the dc coils on Unit 2. (Brunswick
| |
| | |
| Station employs ASCO NP8323A36V
| |
| | |
| valves that use one ac coil and one dc coil in applications
| |
| | |
| using the subject dual solenoid valve.)On October 5, 1985, the dc coils of two MSIVs failed during the perfor-mance of post-maintenance
| |
| | |
| testing of the MSIVs. Investigation
| |
| | |
| into the failures indicated
| |
| | |
| an open circuit in the dc coils. The coils were replaced and the valves subsequently
| |
| | |
| retested satisfactorily.
| |
|
| |
|
| On October 15, 1985, an unplanned
| | program associated with the elastomers and other short-lived subcomponents used |
|
| |
|
| closure of an MSIV occurred while Unit 2 was operating
| | in SOVs has not been adequately maintained, and (5) lubricants have been used |
|
| |
|
| at 99 percent full power. Closure of the MSIV occurred when the ac solenoid coil portion of the MSIV associated
| | excessively during maintenance. ASCO provides installation and maintenance |
|
| |
|
| SOV was de-energized
| | 8607090425 |
|
| |
|
| in accordance
| | Attachment 1 IN 86-57 July 11, 1986 b. Viton has superior high-temperature performance when compared to EP |
|
| |
|
| with a periodic test procedure.
| | and is impervious to hydrocarbons. Its major disadvantage is that it |
|
| |
|
| It was not known then that there was an open circuit in the associated
| | is less resistant to radiation than EP by a factor of ten. ASCO |
|
| |
|
| dc solenoid coil portion of the dual SOV. Consequently, when the ac coil was de-energized, closure of the MSIV resulted.
| | recommends Viton for applications that are not oil-free and where |
|
| |
|
| The failed dc coil was replaced and then retested satisfactorily.
| | radiation levels do not exceed 20 megarads. |
|
| |
|
| Investigation
| | On the basis of a licensee review of the Brunswick Station maintenance |
|
| |
|
| into the failures of the dc coil by the licensee determined
| | history, which showed the performance of Viton to be satisfactory in ASCO |
|
| |
|
| that the failures appeared to be separation
| | valves, and the available literature and industry experience, the licensee |
|
| |
|
| of the very fine coil wire at the junction point where it connects to the much larger field lead. This connection
| | replaced all Unit 2 dual solenoid valves with valves having Viton seats |
|
| |
|
| point is a soldered connection
| | and seals. Because Viton has a 20-megarad limit, the licensee plans to |
|
| |
|
| that is then taped and lacquered.
| | replace these elastomers every 3.3 years to meet environmental qualifica- tion requirements for the MSIV application. |
|
| |
|
| Further analysis of the coils (two failed dc coils plus five spares from storage) by the CP&L Research Center indicated
| | After replacing the faulty valves with valves having Viton disc and seal |
|
| |
|
| the separation | | material, the licensee experienced several SOV failures resulting from |
|
| |
|
| might be corrosion
| | open circuits of the dc coils on Unit 2. (Brunswick Station employs ASCO |
|
| |
|
| induced by chloride contaminants.
| | NP8323A36V valves that use one ac coil and one dc coil in applications |
|
| |
|
| To date, the licensee and ASCO are unable to determine
| | using the subject dual solenoid valve.) |
| | On October 5, 1985, the dc coils of two MSIVs failed during the perfor- mance of post-maintenance testing of the MSIVs. Investigation into the |
|
| |
|
| the source of the chloride. | | failures indicated an open circuit in the dc coils. The coils were |
|
| |
|
| However, followup investigation
| | replaced and the valves subsequently retested satisfactorily. |
|
| |
|
| by the NRC revealed that ASCO had previously
| | On October 15, 1985, an unplanned closure of an MSIV occurred while Unit 2 was operating at 99 percent full power. Closure of the MSIV occurred when |
|
| |
|
| experienced
| | the ac solenoid coil portion of the MSIV associated SOV was de-energized |
|
| |
|
| similar dc coil open circuit anomalies
| | in accordance with a periodic test procedure. It was not known then that |
|
| |
|
| after a surface ship-ment of SOVs overseas to Japan. At that time, ASCO believed that the salt water ambient conditions
| | there was an open circuit in the associated dc solenoid coil portion of |
|
| |
|
| during shipping may have been the source of the chlorine-induced
| | the dual SOV. Consequently, when the ac coil was de-energized, closure of |
|
| |
|
| failures.
| | the MSIV resulted. The failed dc coil was replaced and then retested |
|
| |
|
| ASCO recommends
| | satisfactorily. |
|
| |
|
| specific handling, packaging, and storage conditions
| | Investigation into the failures of the dc coil by the licensee determined |
|
| |
|
| for spare parts and valves at facilities.
| | that the failures appeared to be separation of the very fine coil wire at |
|
| |
|
| Attachment
| | the junction point where it connects to the much larger field lead. This |
|
| |
|
| 1 IN 86-57 July 11, 1986 The licensee initiated
| | connection point is a soldered connection that is then taped and |
|
| |
|
| a temporary
| | lacquered. |
|
| |
|
| surveillance
| | Further analysis of the coils (two failed dc coils plus five spares from |
|
| |
|
| program to monitor opera-bility of the solenoid coils on October 16, 1985. A modification
| | storage) by the CP&L Research Center indicated the separation might be |
|
| |
|
| was performed
| | corrosion induced by chloride contaminants. To date, the licensee and |
|
| |
|
| to install a voltage dropping resistor in the individual | | ASCO are unable to determine the source of the chloride. However, followup investigation by the NRC revealed that ASCO had previously |
|
| |
|
| coil circuits so that they can be monitored | | experienced similar dc coil open circuit anomalies after a surface ship- ment of SOVs overseas to Japan. At that time, ASCO believed that the salt |
|
| |
|
| directly from cabinets in the control room. This allows continuity
| | water ambient conditions during shipping may have been the source of the |
|
| |
|
| of the coil circuitry
| | chlorine-induced failures. ASCO recommends specific handling, packaging, and storage conditions for spare parts and valves at facilities. |
|
| |
|
| to be verified by measuring | | Attachment 1 IN 86-57 July 11, 1986 The licensee initiated a temporary surveillance program to monitor opera- bility of the solenoid coils on October 16, 1985. A modification was |
|
| |
|
| a voltage drop across the resistor. | | performed to install a voltage dropping resistor in the individual coil |
|
| |
|
| According
| | circuits so that they can be monitored directly from cabinets in the |
|
| |
|
| to the licensee, until the cause for failure can be determined, plans are to check the coil circuitry
| | control room. This allows continuity of the coil circuitry to be verified |
|
| |
|
| for continuity
| | by measuring a voltage drop across the resistor. According to the |
|
| |
|
| on a daily basis.2. Scram Discharge
| | licensee, until the cause for failure can be determined, plans are to |
|
| |
|
| Solenoid Valve Failure In November 1985, Carolina Power and Light's Brunswick
| | check the coil circuitry for continuity on a daily basis. |
|
| |
|
| facility experi-enced problems with several scram discharge
| | 2. Scram Discharge Solenoid Valve Failure |
|
| |
|
| SOVs. The problems were identified | | In November 1985, Carolina Power and Light's Brunswick facility experi- enced problems with several scram discharge SOVs. The problems were |
|
| |
|
| during periodic surveillance | | identified during periodic surveillance testing to determine the single |
|
| |
|
| testing to determine
| | rod insertion times and resulted in several rods with slow insertion |
|
| |
|
| the single rod insertion | | times. Initial troubleshooting isolated the problem to the SOVs in the |
|
| |
|
| times and resulted in several rods with slow insertion times. Initial troubleshooting
| | scram discharge line for two of the control rods, which were subsequently |
| | |
| isolated the problem to the SOVs in the scram discharge
| |
| | |
| line for two of the control rods, which were subsequently | |
|
| |
|
| replaced and tested satisfactorily. | | replaced and tested satisfactorily. |
|
| |
|
| The licensee disassembled | | The licensee disassembled the failed SOVs, which were manufactured by ASCO |
| | |
| the failed SOVs, which were manufactured | |
| | |
| by ASCO (Model HV-90-405-2A), for failure analysis. | |
| | |
| When the valves were disas-sembled, it was noted that copious amounts of silicone lubricant
| |
| | |
| had been applied by the licensee to all gaskets, seals, and diaphragms
| |
| | |
| internal to the valves during previous routine maintenance..
| |
| | |
| The licensee believes that the excessive
| |
| | |
| amount of lubricant
| |
| | |
| may have blocked some of the valves' internal passages or caused sticking of the diaphragms, thereby contributing
| |
| | |
| to the slow insertion
| |
| | |
| times. The technical
| |
| | |
| manual for the subject valves states that body passage gaskets should be lubricated
| |
| | |
| with moderate amounts of Dow Corning's
| |
| | |
| Valve Seal Silicone Lubricant
| |
| | |
| or an equivalent
| |
| | |
| high-grade
| |
| | |
| silicone grease.The licensee conducted
| |
| | |
| successful
| |
| | |
| scram tests on all other rods. A periodic retest of 10 percent of the control rods every 120 days as required by the Technical
| |
| | |
| Specifications
| |
| | |
| provides sufficient
| |
| | |
| assurance that this problem does not exist in other SOVs. In addition, the licensee stated that maintenance
| |
| | |
| procedures
| |
| | |
| and practices
| |
|
| |
|
| would be reviewed and modified, as required, to prevent the application
| | (Model HV-90-405-2A), for failure analysis. When the valves were disas- sembled, it was noted that copious amounts of silicone lubricant had been |
|
| |
|
| of excessive
| | applied by the licensee to all gaskets, seals, and diaphragms internal to |
|
| |
|
| amounts of lubricant
| | the valves during previous routine maintenance.. The licensee believes |
|
| |
|
| during repair or overhaul of components.
| | that the excessive amount of lubricant may have blocked some of the |
|
| |
|
| Haddam Neck Nuclear Power Plant On September
| | valves' internal passages or caused sticking of the diaphragms, thereby |
|
| |
|
| 10, 1985, the Haddam Neck Nuclear Power Plant was operating
| | contributing to the slow insertion times. The technical manual for the |
|
| |
|
| at 100 percent power when one of the six SOVs in the auxiliary
| | subject valves states that body passage gaskets should be lubricated with |
|
| |
|
| feedwater
| | moderate amounts of Dow Corning's Valve Seal Silicone Lubricant or an |
|
| |
|
| system (AFW)failed to change state when de-energized.
| | equivalent high-grade silicone grease. |
|
| |
|
| This failure was detected during the performance
| | The licensee conducted successful scram tests on all other rods. A |
|
| |
|
| of a preventive | | periodic retest of 10 percent of the control rods every 120 days as |
|
| |
|
| maintenance
| | required by the Technical Specifications provides sufficient assurance |
|
| |
|
| procedure
| | that this problem does not exist in other SOVs. In addition, the licensee |
|
| |
|
| developed
| | stated that maintenance procedures and practices would be reviewed and |
|
| |
|
| to periodically | | modified, as required, to prevent the application of excessive amounts of |
|
| |
|
| cycle each of the six SOVs to prevent a sticking problem similar to SOV fail-ures previously
| | lubricant during repair or overhaul of components. |
|
| |
|
| experienced
| | ===Haddam Neck Nuclear Power Plant=== |
| | On September 10, 1985, the Haddam Neck Nuclear Power Plant was operating at 100 |
| | percent power when one of the six SOVs in the auxiliary feedwater system (AFW) |
| | failed to change state when de-energized. This failure was detected during the |
|
| |
|
| on November 2, 1984. In that earlier event, two feedwater
| | performance of a preventive maintenance procedure developed to periodically |
|
| |
|
| bypass valves failed to open automatically
| | cycle each of the six SOVs to prevent a sticking problem similar to SOV fail- ures previously experienced on November 2, 1984. In that earlier event, two |
|
| |
|
| and the cause was deter-mined to be sticking SOVs. The faulty SOV was ASCO Model NP8320A-185E | | feedwater bypass valves failed to open automatically and the cause was deter- mined to be sticking SOVs. The faulty SOV was ASCO Model NP8320A-185E and the |
|
| |
|
| and the licensee has been unable to determine
| | licensee has been unable to determine the cause of the malfunction. The |
|
| |
|
| the cause of the malfunction.
| | Attachment 2 IN 86-57 July 11, 1986 LIST OF RECENTLY ISSUED |
|
| |
|
| The
| | IE INFORMATION NOTICES |
|
| |
|
| Attachment
| | Information Date of |
|
| |
|
| 2 IN 86-57 July 11, 1986 LIST OF RECENTLY ISSUED IE INFORMATION
| | Notice No. Subject Issue Issued to |
|
| |
|
| NOTICES Information
| | 86-56 Reliability Of Main Steam 7/10/86 All PWR facilities |
|
| |
|
| Date of Notice No. Subject Issue Issued to 86-56 Reliability
| | Safety Valves holding an OL or CP |
|
| |
|
| Of Main Steam Safety Valves 7/10/86 All PWR facilities
| | 86-55 Delayed Access To Safety- 7/10/86 All power reactor |
|
| |
|
| holding an OL or CP 86-55 86-54 Delayed Access To Safety-Related Areas And Equipment During Plant Emergencies
| | Related Areas And Equipment facilities holding |
|
| |
|
| Criminal Prosecution
| | During Plant Emergencies an OL or CP |
|
| |
|
| Of A Former Radiation | | 86-54 Criminal Prosecution Of A 6/27/86 All holders of by- Former Radiation Safety product, source, or |
|
| |
|
| ===Safety Officer Who Willfully Directed An Unqualified===
| | Officer Who Willfully special nuclear |
| Individual
| |
|
| |
|
| ===To Perform Radiography===
| | Directed An Unqualified material |
| Improper Use Of Heat Shrink-able Tubing 7/10/86 6/27/86 6/26/86 86-53 86-52 Conductor
| |
|
| |
|
| Insulation
| | Individual To Perform |
|
| |
|
| Degrada- 6/26/86 tion On Foxboro Model E Controllers
| | Radiography |
|
| |
|
| Excessive
| | 86-53 Improper Use Of Heat Shrink- 6/26/86 All power reactor |
|
| |
|
| Pneumatic
| | able Tubing facilities holding |
|
| |
|
| Leakage 6/18/86 In The Automatic
| | an OL or CP |
|
| |
|
| Depressuriza- tion System All power reactor facilities
| | 86-52 Conductor Insulation Degrada- 6/26/86 All power reactor |
|
| |
|
| holding an OL or CP All holders of by-product, source, or special nuclear material All power reactor facilities | | tion On Foxboro Model E facilities holding |
|
| |
|
| holding an OL or CP All power reactor facilities
| | Controllers an OL or CP |
|
| |
|
| holding an OL or CP All BWR facilities
| | 86-51 Excessive Pneumatic Leakage 6/18/86 All BWR facilities |
|
| |
|
| holding an OL or CP All power reactor facilities | | In The Automatic Depressuriza- holding an OL or CP |
|
| |
|
| holding an OL or CP All power reactor facilities
| | tion System |
|
| |
|
| holding an OL or CP All BWR facilities
| | 86-50 Inadequate Testing To Detect 6/18/86 All power reactor |
|
| |
|
| holding an OL or CP 86-51 86-50 86-49 Inadequate | | Failures Of Safety-Related facilities holding |
|
| |
|
| Testing To Detect Failures Of Safety-Related
| | Pneumatic Components Or an OL or CP |
|
| |
|
| Pneumatic
| | Systems |
|
| |
|
| Components
| | 86-49 Age/Environment Induced 6/16/86 All power reactor |
|
| |
|
| Or Systems Age/Environment
| | Electrical Cable Failues facilities holding |
|
| |
|
| Induced Electrical
| | an OL or CP |
|
| |
|
| Cable Failues Inadequate
| | 86-48 Inadequate Testing Of Boron 6/13/86 All BWR facilities |
|
| |
|
| Testing Of Boron Solution Concentration
| | Solution Concentration In The holding an OL or CP |
|
| |
|
| In The Standby Liquid Control System 6/18/86 6/16/86 6/13/86 86-48 OL = Operating
| | Standby Liquid Control System |
|
| |
|
| License CP = Construction | | OL = Operating License |
|
| |
|
| Permit}} | | CP = Construction Permit}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Operating Problems with Solenoid Operated Valves at Nuclear Power PlantsML031220718 |
Person / Time |
---|
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Issue date: |
07/11/1986 |
---|
From: |
NRC/IE |
---|
To: |
|
---|
References |
---|
IN-86-057, NUDOCS 8607090425 |
Download: ML031220718 (4) |
|
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, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
---|
Category:NRC Information Notice
MONTHYEARInformation Notice 2020-02, Flex Diesel Generator Operational Challenges2020-09-15015 September 2020 Flex Diesel Generator Operational Challenges ML20225A0322020-09-0303 September 2020 NRC Choice Letter to NAC International with Attached Safety Inspection Report, IR 0721015/2020201, February 24-27, 2020 and July 22, 2020, Inspection of NAC International in Norcross, Georgia Information Notice 2012-09, PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs.2019-11-30030 November 2019 PWROG-16043-NP-A, Revision 2, PWROG Program to Address NRC Information Notice 2012-09: Irradiation Effects on Fuel Assembly Spacer Grid Crush Strength for Westinghouse and CE PWR Fuel Designs. Information Notice 2011-20, NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011)2019-07-24024 July 2019 NRC060 - NRC Information Notice 2011-20: Concrete Degradation by Alkali-Silica Reaction (Nov. 18, 2011) ML19196A2452019-07-15015 July 2019 Public Notice - Sequoyah Nuclear Plant, Unit 2 - Exigent Amendment to Facility Operating License Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations2019-03-12012 March 2019 Inadequate Evaluation of Temporary Alterations ML16028A3082016-04-27027 April 2016 NRC Information Notice; IN 2016-05: Operating Experience Regarding Complications From a Loss of Instrumentation Air Information Notice 2015-05, Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability of Auxiliary and Emergency Feedwater Auto Start Circuits on Loss of Main Feedwater Pumps Information Notice 2015-05, Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps2015-05-12012 May 2015 Inoperability Of Auxiliary And Emergency Feedwater Auto Start Circuits On Loss Of Main Feedwater Pumps Information Notice 2013-20, OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 OFFICIAL EXHIBIT - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-20, Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143)2013-10-0303 October 2013 Official Exhibit - NYS000538-00-BD01 - NRC Information Notice 2013-20: Steam Generator Channel Head and Tubesheet Degradation (October 3, 2013) (ML13204A143) Information Notice 2013-11, OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 OFFICIAL EXHIBIT - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) Information Notice 2013-11, Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013)2013-07-0303 July 2013 Official Exhibit - NYS000551-00-BD01 - NRC Information Notice 2013-11: Crack-Like Indication at Dents/Dings and in the Freespan Region of Thermally Treated Alloy 600 Steam Generator Tubes (July 3, 2013) 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 Notice 2010-12: Contain2012-08-17017 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 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 Notice 2010-12: Con2012-08-17017 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 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 [[: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 [[: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 [[: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 [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
11$S ORIGINAL SSINS No.:
IN 86-57 6835 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 July 11, 1986 IE INFORMATION NOTICE NO. 86-57: OPERATING PROBLEMS WITH SOLENOID OPERATED
VALVES AT NUCLEAR POWER PLANTS
Addressees
All nuclear power reactor facilities holding an operating license or a
construction permit.
Purpose
This notice is to advise recipients of a series of valve failures that have
occurred recently at several nuclear power plants. It is expected that recipi- ents will review the events discussed below for applicability to their facili- ties and consider actions, if appropriate, to preclude similar valve failures
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
The NRC has received reports from licensees of operating nuclear power plants
involving failures of certain valves that are actuated by solenoid operated
valves (SOVs) to operate properly. These failures have adversely affected the
intended functions of the main steam isolation system, pressure relief and
fluid control systems. Attachment 1 to this information notice describes the
failure events and the corrective actions taken.
Discussion:
In most of the cases described in Attachment 1, the cause for triggering the
event was attributed to a malfunctioning SOV that served as a pilot valve. This
in turn resulted in the malfunction of the associated main valve. The failures
of the SOVs can be traced to the following different causes: (1) potentially
high-temperature ambient conditions are not being continuously monitored in areas
where SOVs are installed and operating in an energized state, (2) hydrocarbon
contaminants, probably because backup air systems (e.g., plant service or shop
air systems) are being used periodically and are not designed to "oil-free"
specifications as required for Class IE service, (3) chloride contaminants
causing open circuits in coils of the SOVs, possibly as a result of questionable
handling, packaging, and storage procedures, (4) an active replacement parts
program associated with the elastomers and other short-lived subcomponents used
in SOVs has not been adequately maintained, and (5) lubricants have been used
excessively during maintenance. ASCO provides installation and maintenance
8607090425
Attachment 1 IN 86-57 July 11, 1986 b. Viton has superior high-temperature performance when compared to EP
and is impervious to hydrocarbons. Its major disadvantage is that it
is less resistant to radiation than EP by a factor of ten. ASCO
recommends Viton for applications that are not oil-free and where
radiation levels do not exceed 20 megarads.
On the basis of a licensee review of the Brunswick Station maintenance
history, which showed the performance of Viton to be satisfactory in ASCO
valves, and the available literature and industry experience, the licensee
replaced all Unit 2 dual solenoid valves with valves having Viton seats
and seals. Because Viton has a 20-megarad limit, the licensee plans to
replace these elastomers every 3.3 years to meet environmental qualifica- tion requirements for the MSIV application.
After replacing the faulty valves with valves having Viton disc and seal
material, the licensee experienced several SOV failures resulting from
open circuits of the dc coils on Unit 2. (Brunswick Station employs ASCO
NP8323A36V valves that use one ac coil and one dc coil in applications
using the subject dual solenoid valve.)
On October 5, 1985, the dc coils of two MSIVs failed during the perfor- mance of post-maintenance testing of the MSIVs. Investigation into the
failures indicated an open circuit in the dc coils. The coils were
replaced and the valves subsequently retested satisfactorily.
On October 15, 1985, an unplanned closure of an MSIV occurred while Unit 2 was operating at 99 percent full power. Closure of the MSIV occurred when
the ac solenoid coil portion of the MSIV associated SOV was de-energized
in accordance with a periodic test procedure. It was not known then that
there was an open circuit in the associated dc solenoid coil portion of
the dual SOV. Consequently, when the ac coil was de-energized, closure of
the MSIV resulted. The failed dc coil was replaced and then retested
satisfactorily.
Investigation into the failures of the dc coil by the licensee determined
that the failures appeared to be separation of the very fine coil wire at
the junction point where it connects to the much larger field lead. This
connection point is a soldered connection that is then taped and
lacquered.
Further analysis of the coils (two failed dc coils plus five spares from
storage) by the CP&L Research Center indicated the separation might be
corrosion induced by chloride contaminants. To date, the licensee and
ASCO are unable to determine the source of the chloride. However, followup investigation by the NRC revealed that ASCO had previously
experienced similar dc coil open circuit anomalies after a surface ship- ment of SOVs overseas to Japan. At that time, ASCO believed that the salt
water ambient conditions during shipping may have been the source of the
chlorine-induced failures. ASCO recommends specific handling, packaging, and storage conditions for spare parts and valves at facilities.
Attachment 1 IN 86-57 July 11, 1986 The licensee initiated a temporary surveillance program to monitor opera- bility of the solenoid coils on October 16, 1985. A modification was
performed to install a voltage dropping resistor in the individual coil
circuits so that they can be monitored directly from cabinets in the
control room. This allows continuity of the coil circuitry to be verified
by measuring a voltage drop across the resistor. According to the
licensee, until the cause for failure can be determined, plans are to
check the coil circuitry for continuity on a daily basis.
2. Scram Discharge Solenoid Valve Failure
In November 1985, Carolina Power and Light's Brunswick facility experi- enced problems with several scram discharge SOVs. The problems were
identified during periodic surveillance testing to determine the single
rod insertion times and resulted in several rods with slow insertion
times. Initial troubleshooting isolated the problem to the SOVs in the
scram discharge line for two of the control rods, which were subsequently
replaced and tested satisfactorily.
The licensee disassembled the failed SOVs, which were manufactured by ASCO
(Model HV-90-405-2A), for failure analysis. When the valves were disas- sembled, it was noted that copious amounts of silicone lubricant had been
applied by the licensee to all gaskets, seals, and diaphragms internal to
the valves during previous routine maintenance.. The licensee believes
that the excessive amount of lubricant may have blocked some of the
valves' internal passages or caused sticking of the diaphragms, thereby
contributing to the slow insertion times. The technical manual for the
subject valves states that body passage gaskets should be lubricated with
moderate amounts of Dow Corning's Valve Seal Silicone Lubricant or an
equivalent high-grade silicone grease.
The licensee conducted successful scram tests on all other rods. A
periodic retest of 10 percent of the control rods every 120 days as
required by the Technical Specifications provides sufficient assurance
that this problem does not exist in other SOVs. In addition, the licensee
stated that maintenance procedures and practices would be reviewed and
modified, as required, to prevent the application of excessive amounts of
lubricant during repair or overhaul of components.
Haddam Neck Nuclear Power Plant
On September 10, 1985, the Haddam Neck Nuclear Power Plant was operating at 100
percent power when one of the six SOVs in the auxiliary feedwater system (AFW)
failed to change state when de-energized. This failure was detected during the
performance of a preventive maintenance procedure developed to periodically
cycle each of the six SOVs to prevent a sticking problem similar to SOV fail- ures previously experienced on November 2, 1984. In that earlier event, two
feedwater bypass valves failed to open automatically and the cause was deter- mined to be sticking SOVs. The faulty SOV was ASCO Model NP8320A-185E and the
licensee has been unable to determine the cause of the malfunction. The
Attachment 2 IN 86-57 July 11, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
86-56 Reliability Of Main Steam 7/10/86 All PWR facilities
Safety Valves holding an OL or CP
86-55 Delayed Access To Safety- 7/10/86 All power reactor
Related Areas And Equipment facilities holding
During Plant Emergencies an OL or CP
86-54 Criminal Prosecution Of A 6/27/86 All holders of by- Former Radiation Safety product, source, or
Officer Who Willfully special nuclear
Directed An Unqualified material
Individual To Perform
Radiography
86-53 Improper Use Of Heat Shrink- 6/26/86 All power reactor
able Tubing facilities holding
an OL or CP
86-52 Conductor Insulation Degrada- 6/26/86 All power reactor
tion On Foxboro Model E facilities holding
Controllers an OL or CP
86-51 Excessive Pneumatic Leakage 6/18/86 All BWR facilities
In The Automatic Depressuriza- holding an OL or CP
tion System
86-50 Inadequate Testing To Detect 6/18/86 All power reactor
Failures Of Safety-Related facilities holding
Pneumatic Components Or an OL or CP
Systems
86-49 Age/Environment Induced 6/16/86 All power reactor
Electrical Cable Failues facilities holding
an OL or CP
86-48 Inadequate Testing Of Boron 6/13/86 All BWR facilities
Solution Concentration In The holding an OL or CP
Standby Liquid Control System
OL = Operating License
CP = Construction Permit
|
---|
|
list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986)
- 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)
- 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)
- 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)
- 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)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991)
- 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)
- 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)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl)
- 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 |
---|