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| | issue date = 01/29/1990 | | | issue date = 01/29/1990 |
| | title = Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels | | | title = Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels |
| | author name = Rossi C E | | | author name = Rossi C |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:UNITED STATES |
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| |
|
| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
|
| |
|
| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| WASHINGTON, D.C. 20555 January 29, 1990 NRC INFORMATION
| |
|
| |
|
| NOTICE NO. 90-06: POTENTIAL
| | WASHINGTON, D.C. 20555 January 29, 1990 |
| | SHUTDOWN COOLING |
|
| |
|
| FOR LOSS OF SHUTDOWN COOLING WHILE AT LOW REACTOR COOLANT LEVELS | | NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF COOLANT LEVELS |
| | |
| | WHILE AT LOW REACTOR |
|
| |
|
| ==Addressees== | | ==Addressees== |
| : | | : |
| All holders of operating
| | nuclear power |
|
| |
|
| licenses or construction | | All holders of operating licenses or construction permits for |
|
| |
|
| permits for nuclear power reactors.
| | reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| : This information | | : |
| | to a potential problem |
|
| |
|
| notice is intended to alert addressees | | This information notice is intended to alert addressees (RHR) system during |
|
| |
|
| to a potential
| | affecting the operability of the residual heat removal |
|
| |
|
| problem affecting
| | is expected that re- operating conditions involving mid-loop operation. It to their facilities |
|
| |
|
| the operability | | -cipients will review the information for applicability problems. However, and consider actions, as appropriate, to avoid similar constitute NRC |
|
| |
|
| of the residual heat removal (RHR) system during operating
| | suggestions contained in this information notice do not |
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| |
|
| conditions
| | response is required. |
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| |
|
| involving
| | requirements; therefore, no specific action or written |
|
| |
|
| mid-loop operation.
| | ==Description of Circumstances== |
| | : |
| | the residual heat |
|
| |
|
| It is expected that re--cipients
| | On July 18, 1989, at Comanche Peak Unit 1, train 'Al ofloading. The air |
|
| |
|
| will review the information
| | removal system was in operation prior to initial fuel |
|
| |
|
| for applicability
| | being used to |
|
| |
|
| to their facilities
| | operated RHR heat exchanger flow control valve (FCV) was water level was |
|
| |
|
| and consider actions, as appropriate, to avoid similar problems.
| | maintain system flow below 2000 gpm. The reactor vessel |
|
| |
|
| However, suggestions
| | legs. |
|
| |
|
| contained
| | being maintained slightly abpve the center line of the hot |
|
| |
|
| in this information
| | FCV failed. The loss |
|
| |
|
| notice do not constitute
| | The inverter supplying power to the controller for the to its emergency core |
|
| |
|
| NRC requirements;
| | of power to the controller resulted in the FCV failing open valve caused |
| therefore, no specific action or written response is required.Description
| |
|
| |
|
| of Circumstances: | | cooling system (ECCS) position of being fully open. The flow caused |
| On July 18, 1989, at Comanche Peak Unit 1, train 'Al of the residual heat removal system was in operation
| |
|
| |
|
| prior to initial fuel loading. The air operated RHR heat exchanger
| | an increase in system flow to 4400 gpm. This sudden, increased |
|
| |
|
| flow control valve (FCV) was being used to maintain system flow below 2000 gpm. The reactor vessel water level was being maintained
| | the RHR pipe con- conditions where vortexing was expected at the suction of |
|
| |
|
| slightly abpve the center line of the hot legs.The inverter supplying
| | nection to the RCS. |
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| |
|
| power to the controller
| | to an alternate |
|
| |
|
| for the FCV failed. The loss of power to the controller
| | The power supply for the controllers was manually transferred |
|
| |
|
| resulted in the FCV failing to its emergency
| | terminating the event. |
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| |
|
| core cooling system (ECCS) position of being fully open. The open valve caused an increase in system flow to 4400 gpm. This sudden, increased
| | source and the FCV was throttled, thus |
|
| |
|
| flow caused conditions | | Discussion: |
| | flow through the |
|
| |
|
| where vortexing
| | The FCV is manually throttled to maintain a desired rate of to control the |
|
| |
|
| was expected at the suction of the RHR pipe con-nection to the RCS.The power supply for the controllers
| | RHR heat exchanger. The heat exchanger flow rate is adjusted |
|
| |
|
| was manually transferred
| | to the vessel. Total system flow is |
|
| |
|
| to an alternate source and the FCV was throttled, thus terminating
| | temperature of the water being returned with the |
|
| |
|
| the event.Discussion: | | regulated by throttling the heat exchanger bypass valve coincident |
| The FCV is manually throttled
| |
|
| |
|
| to maintain a desired rate of flow through the RHR heat exchanger.
| | adjustment of the FCV. |
|
| |
|
| The heat exchanger
| | 001230175 Z (( |
| | ' D*1 IC, |
| | eo uachr |
|
| |
|
| flow rate is adjusted to control the temperature | | IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion. However, the increased system flow corresponded to the rate at which vortexing had |
|
| |
|
| of the water being returned to the vessel. Total system flow is regulated
| | been calculated to occur based on the existing RCS level. The licensee had |
|
| |
|
| by throttling
| | previously determined maximum permitted flow rates for various reduced levels |
|
| |
|
| the heat exchanger | | of the RCS to prevent the possibility of vortexing and air entrainment into |
|
| |
|
| bypass valve coincident
| | the RHR pump. |
|
| |
|
| with the adjustment
| | Although RHR pump operation was never actually impaired, the potential existed |
|
| |
|
| of the FCV.001230175 Z ( (' D*1 IC, eo uachr
| | for air to be introduced to the pump's suction. This concern is exacerbated by |
|
| |
|
| IN 90-06 January 29, 1990 During this event, there were no indications
| | * the fact that the heat exchanger FCVs for both trains of RHR are powered from |
|
| |
|
| of pump air ingestion. | | the same inverter. Since the FCVs open fully on a loss of power, both trains |
|
| |
|
| However, the increased
| | of RHR could become inoperable on a loss of power during mid-loop operation. |
|
| |
|
| system flow corresponded
| | (A loss of instrument air would also cause the FCVs to fail to the full open |
|
| |
|
| to the rate at which vortexing
| | position and could also result in the loss of both trains of the RHR system). |
|
| |
|
| had been calculated
| | During most modes of operation, having the FCVs go -fully open on loss of |
|
| |
|
| to occur based on the existing RCS level. The licensee had previously
| | power or instrument air is not a safety concern because having the valves |
|
| |
|
| determined
| | fully open does not normally prevent the system from performing its safety |
|
| |
|
| maximum permitted
| | function. However, having the valves go fully open while at mid-loop could |
|
| |
|
| flow rates for various reduced levels of the RCS to prevent the possibility
| | result in the loss of decay heat removal capability. This loss could persist |
|
| |
|
| of vortexing
| | until electrical power or instrument air is restored and air is vented from |
|
| |
|
| and air entrainment
| | the RHR system. |
|
| |
|
| into the RHR pump.Although RHR pump operation
| | The licensee has revised procedures for mid-loop operation to require manually |
|
| |
|
| was never actually impaired, the potential
| | positioning the cold leg injection isolation valves to limit the maximum flow |
|
| |
|
| existed for air to be introduced
| | through the system, even with the FCVs fully open. This lineup will be used |
|
| |
|
| to the pump's suction. This concern is exacerbated
| | whenever the unit is at mid-loop and protects against the consequences of |
|
| |
|
| by* the fact that the heat exchanger
| | failure of either electrical power or instrument air. |
|
| |
|
| FCVs for both trains of RHR are powered from the same inverter.
| | Several generic communications have been issued informing licensees of the |
|
| |
|
| Since the FCVs open fully on a loss of power, both trains of RHR could become inoperable
| | consequences of the loss of residual (decay) heat removal and the operating |
|
| |
|
| on a loss of power during mid-loop operation.(A loss of instrument
| | conditions under which the probability of a loss increases; i.e., reduced |
|
| |
|
| air would also cause the FCVs to fail to the full open position and could also result in the loss of both trains of the RHR system).During most modes of operation, having the FCVs go -fully open on loss of power or instrument
| | inventory conditions. The most recent publications include Generic Letter |
|
| |
|
| air is not a safety concern because having the valves fully open does not normally prevent the system from performing
| | (GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System |
|
| |
|
| its safety function.
| | is Partially Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In- formation Notice (IN)87-23, "Loss of Decay Heat Removal During Low Reactor |
|
| |
|
| However, having the valves go fully open while at mid-loop could result in the loss of decay heat removal capability.
| | Coolant Level Operation;" IN 88-36, 'Possible Sudden Loss of RCS Inventory |
|
| |
|
| This loss could persist until electrical
| | During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat |
|
| |
|
| power or instrument
| | Removal Caused by Accumulator Nitrogen Injection." The event described |
|
| |
|
| air is restored and air is vented from the RHR system.The licensee has revised procedures
| | above introduces a subtle failure scenario which licensees may not have |
|
| |
|
| for mid-loop operation
| | considered. |
|
| |
|
| to require manually positioning
| | IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If |
|
| |
|
| the cold leg injection | | you have any questions about the information in this notice, please contact |
|
| |
|
| isolation
| | one of the technical contacts listed below or the appropriate NRR project manager. |
|
| |
|
| valves to limit the maximum flow through the system, even with the FCVs fully open. This lineup will be used whenever the unit is at mid-loop and protects against the consequences
| | Charles E. Rossi, irector |
|
| |
|
| of failure of either electrical | | Division of Operational Events Assessment |
|
| |
|
| power or instrument
| | Office of Nuclear Reactor Regulation |
|
| |
|
| air.Several generic communications
| | Technical Contacts: Nick Fields, NRR |
|
| |
|
| have been issued informing
| | (301) 492-1173 Steve Bitter, RIV |
|
| |
|
| licensees
| | (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| of the consequences
| | I |
|
| |
|
| of the loss of residual (decay) heat removal and the operating conditions | | IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion However |
|
| |
|
| under which the probability
| | the increased system flow enrraenan~nA n~ -~ neto. Hwvr |
|
| |
|
| of a loss increases;
| | Attachment ~ |
| i.e., reduced inventory
| | q ) sx 90-06 Jasmary 2§ 1990 |
| | Page I of I |
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| |
|
| conditions.
| | LIST OF RECEITLT ISSUED |
|
| |
|
| The most recent publications
| | NIR INFORtAT1011 OTICES |
|
| |
|
| include Generic Letter (GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System is Partially
| | JCW -- |
| | lnfonation Issuance Issued te |
|
| |
|
| Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In-formation
| | Notice No. SubJect |
|
| |
|
| Notice (IN) 87-23, "Loss of Decay Heat Removal During Low Reactor Coolant Level Operation;" IN 88-36, 'Possible
| | 90-05 Inter-System Discharge of 1/26/9O All holders of ULs |
|
| |
|
| Sudden Loss of RCS Inventory During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat Removal Caused by Accumulator
| | Reactor Coelant or Ch for nuclear |
|
| |
|
| Nitrogen Injection." The event described above introduces
| | power reactors. |
|
| |
|
| a subtle failure scenario which licensees
| | 90-04 Cracking of the Upper Shall- 1/26/90 All holders of OLs |
|
| |
|
| may not have considered.
| | to-Transition Cone Girth or CPs.for Westinghouse. |
|
| |
|
| IN 90-06 January 29, 1990 This information
| | Melds Is Steam Generators designed and Combustion |
|
| |
|
| notice requires no specific action or written response.
| | Engineering-disigned |
| | |
| If you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact one of the technical
| |
| | |
| contacts listed below or the appropriate
| |
| | |
| NRR project manager.Charles E. Rossi, irector Division of Operational
| |
| | |
| ===Events Assessment===
| |
| Office of Nuclear Reactor Regulation
| |
| | |
| Technical
| |
| | |
| Contacts:
| |
| Nick Fields, NRR (301) 492-1173 Steve Bitter, RIV (817) 897-1500 Attachment:
| |
| List of Recently Issued NRC Information
| |
| | |
| Notices
| |
| | |
| I IN 90-06 January 29, 1990 During this event, there were no indications
| |
| | |
| of pump air ingestion
| |
| | |
| However the increased
| |
| | |
| system flow enrraenan~nA
| |
| | |
| n~ -~ neto. Hwvr Attachment
| |
| | |
| ~q ) sx 90-06 Jasmary 2§ 1990 Page I of I LIST OF RECEITLT ISSUED NIR INFORtAT1011 OTICES JCW --lnfonation
| |
| | |
| Notice No.90-05 90-04 SubJect Inter-System
| |
| | |
| Discharge
| |
| | |
| of Reactor Coelant Issuance 1/26/9O Cracking of the Upper Shall- 1/26/90 to-Transition
| |
|
| |
|
| ===Cone Girth Melds Is Steam Generators===
| | nuclear power reactors. |
| Issued te All holders of ULs or Ch for nuclear power reactors.All holders of OLs or CPs.for Westinghouse.
| |
|
| |
|
| designed and Combustion
| | 90-03 malfunction of Borg-Varner 1/23/90 All holders of OLs |
|
| |
|
| Engineering-disigned
| | SBlted Sonnet Check Valves or CPs for uclewr |
|
| |
|
| nuclear power reactors.All holders of OLs or CPs for uclewr power reactors.All holders of OLs or CPs for Slis.All holders of NRC materials
| | Causd by Failure of the power reactors. |
|
| |
|
| licenses.90-03 malfunction
| | Swing Arm |
|
| |
|
| of Borg-Varner | | 90-02 Potential Degradation of 1/29D All holders of OLs |
|
| |
|
| SBlted Sonnet Check Valves Causd by Failure of the Swing Arm 90-02 Potential
| | Secondary Contaient or CPs for Slis. |
|
| |
|
| Degradation
| | 90-01 lIportace of Proper 1/12/90 All holders of NRC |
|
| |
|
| of Secondary
| | Response to Self-Identifted materials licenses. |
|
| |
|
| Contaient 90-01 lIportace
| | Violations by Licensees |
|
| |
|
| of Proper Response to Self-Identifted | | 89-90 Pressurizer Safety Valv 12/28/84 All holder of OMs |
|
| |
|
| Violations
| | Lift Setpoint Shift or Ch for Pilb. |
|
| |
|
| by Licensees 89-90 Pressurizer
| | 89-8 Event Notificatton 12/26/89 All holders of CLs |
|
| |
|
| Safety Valv Lift Setpoint Shift 89-8 Event Notificatton
| | Workshents or en for nuclear |
|
| |
|
| Workshents
| | powerreactors. |
|
| |
|
| 89-88 Recent XRC-Sponsored | | 89-88 Recent XRC-Sponsored 12/26189 All holders of Ots |
|
| |
|
| Testing of motor-Operated | | Testing of motor-Operated or CPsfor nutlear |
|
| |
|
| Valves 8647 Disablilg | | Valves poer reactors. |
|
| |
|
| of Emergency Diesel Generators | | 8647 Disablilg of Emergency 12/19189 All helders of OLs |
|
| |
|
| by Their Neutral Ground-Fault | | Diesel Generators by or CVs for nuclear |
|
| |
|
| Protection
| | Their Neutral Ground-Fault power reactors. |
|
| |
|
| Circuitry 8945. etalclad. | | Protection Circuitry |
|
| |
|
| Lou-Voltage | | 8945. etalclad. Lou-Voltage 12/IS/19 All holders of OLs |
|
| |
|
| Supp. 2 Power Circuit Dreakars Refurbished | | Supp. 2 Power Circuit Dreakars or CPsfor nuclear |
|
| |
|
| with Substandard | | Refurbished with power reactors. |
|
| |
|
| Parts 1/23/90 1/29D 1/12/90 12/28/84 All holder of OMs or Ch for Pilb.12/26/89 All holders of CLs or en for nuclear power reactors.12/26189 All holders of Ots or CPs for nutlear poer reactors.12/19189 All helders of OLs or CVs for nuclear power reactors.12/IS/1 9 All holders of OLs or CPs for nuclear power reactors.OL*OpitunceS | | Substandard Parts |
|
| |
|
| -_CV s Construction | | OL*OpitunceS - _ |
| | CV s Construction Permit |
|
| |
|
| Permit UNITED STATES NUCLEAR REGULATORY
| | UNITED STATES |
|
| |
|
| COMMISSION
| | IPOSTAGE & FEES PAOID |
|
| |
|
| WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. 8300 IPOSTAGE & FEES PAOID ISNiRC 1 IN 90-06 January 29, 1990 This information | | NUCLEAR REGULATORY COMMISSION ISNiRC 1 WASHINGTON, D.C. 20555 OFFICIAL BUSINESS |
|
| |
|
| notice requires no specific action or written response.
| | PENALTY FOR PRIVATE USE. 8300 |
|
| |
|
| If you have any questions | | IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If |
|
| |
|
| about the information | | you have any questions about the information in this notice, please contact |
|
| |
|
| in this notice, please contact one of the technical
| | one of the technical contacts listed below or the appropriate NRR project manager. |
|
| |
|
| contacts listed below or the appropriate
| | Charles E. Rossi, Director |
|
| |
|
| NRR project manager.Charles E. Rossi, Director Division of Operational
| | Division of Operational Events Assessment |
|
| |
|
| ===Events Assessment===
| |
| Office of Nuclear Reactor Regulation | | Office of Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical Contacts: Nick Fields, NRR |
|
| |
|
| Contacts: Nick Fields, NRR (301) 492-1173 Steve Bitter, RIV (817) 897-1500 Attachment:
| | (301) 492-1173 Steve Bitter, RIV |
| List of Recently Issued NRC Information
| |
|
| |
|
| Notices*SEE PREVIOUS CONCURRENCE | | (817) 897-1500 |
| | Attachment: List of Recently Issued NRC Information Notices |
|
| |
|
| EAB:NRR*NFields:
| | *SEE PREVIOUS CONCURRENCE |
| db 1/12/90 TECH:EDITOR
| |
|
| |
|
| *BCalure 1/13/90 EAB:NRR C:EAB:NRR*DCFischer
| | EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR NRR:SRXB |
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| *CJHaughney | | *NFields: db *BCalure *DCFischer *CJHaughney *CHBerlinger *RJones |
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| 1/16/90 1/16/90 C:OGCB:NRR | | 1/12/90 1/13/90 1/16/90 1/16/90 1/17/90 1/23/90 |
| | 1/Z3'90 |
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| |
|
| *CHBerlinger
| | K)j V%2IN 90- |
| | January , 1990 No specific action or written response is required by this information notice. |
|
| |
|
| 1/17/90 NRR:SRXB*RJones 1/23/90 1 /Z3'90
| | If you have any questions about this matter, please contact one of the technical |
| K)j V%2IN 90-January , 1990 No specific action or written response is required by this information
| |
|
| |
|
| If you have any questions
| | contacts listed below or the Regional Administrator of the appropriate regional |
|
| |
|
| about this matter, please contact one of the contacts listed below or the Regional Administrator
| | office. |
|
| |
|
| of the appropriate
| | Charles E. Rossi, Director |
|
| |
|
| office.notice.technical regional Charles E. Rossi, Director Division of Operational
| | Division of Operational Events Assessment |
|
| |
|
| ===Events Assessment===
| |
| Office of Nuclear Reactor Regulation | | Office of Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 |
| | | Attachment: List of Recently Issued NRC Information Notices |
| Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 Attachment: | |
| List of Recently Issued NRC Information | |
| | |
| Notices*SEE PREVIOUS CONCURRENCE | |
| | |
| EAB:NRR*NFields:db
| |
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| |
|
| / /90 D:DOEA:NRR
| | *SEE PREVIOUS CONCURRENCE |
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| |
|
| CERossi/ /90 TECH:EDITOR
| | EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR N R B |
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| *BCalure/ /90 EAB:NRR*DCFischer | | *DCFischer *CJHaughney* *CHBerlinger RJV es |
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| / /90 C:EAB:NRR*CJHaughney*
| | *NFields:db *BCalure |
| / /90 C:OGCB:NRR
| |
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| *CHBerlinger
| | / /90 / /90 / /90 / /90 / /90 I j:/90 |
| | D:DOEA:NRR |
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| / /90 N R B RJV es I j:/90
| | CERossi |
| IN 90-January , 1990%...Z'age
| |
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| |
|
| 3 of 3 No specific action or written response is required by this infornation
| | / /90 |
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| |
|
| notice. If you have any questions
| | IN 90- |
| | January , 1990 |
| | %...Z'age 3 of 3 No specific action or written response is required by this |
|
| |
|
| about this matter, please contact the technical | | infornation notice. If you have any questions about this matter, please contact the technical contact listed below or the Regional |
|
| |
|
| contact listed below or the Regional Administrator
| | Administrator of the appropriate regional office. |
|
| |
|
| of the appropriate
| | Charles E. Rossi, Director |
|
| |
|
| regional office.Charles E. Rossi, Director Division of Operational
| | Division of Operational Events Assessment |
|
| |
|
| ===Events Assessment===
| |
| Office of Nuclear Reactor Regulation | | Office of Nuclear Reactor Regulation |
|
| |
|
| Technical | | Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 |
| | | Attachment: List of Recently Issued NRC Information Notices |
| Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500 List of Recently Issued NRC Information | |
| | |
| Notices Attachment: | |
| AJF EAB:NRR NFields:db
| |
| | |
| Jr //,/90 C0Wvtn Au t VIU46x1 4fhire0rAtU
| |
| | |
| rAI TECH:EDITOR
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Potential for Loss of Shutdown Cooling While at Low Reactor Coolant LevelsML031130325 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
01/29/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-90-006, NUDOCS 9001230175 |
Download: ML031130325 (7) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater 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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 January 29, 1990
SHUTDOWN COOLING
NRC INFORMATION NOTICE NO. 90-06: POTENTIAL FOR LOSS OF COOLANT LEVELS
WHILE AT LOW REACTOR
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
to a potential problem
This information notice is intended to alert addressees (RHR) system during
affecting the operability of the residual heat removal
is expected that re- operating conditions involving mid-loop operation. It to their facilities
-cipients will review the information for applicability problems. However, and consider actions, as appropriate, to avoid similar constitute NRC
suggestions contained in this information notice do not
response is required.
requirements; therefore, no specific action or written
Description of Circumstances
the residual heat
On July 18, 1989, at Comanche Peak Unit 1, train 'Al ofloading. The air
removal system was in operation prior to initial fuel
being used to
operated RHR heat exchanger flow control valve (FCV) was water level was
maintain system flow below 2000 gpm. The reactor vessel
legs.
being maintained slightly abpve the center line of the hot
FCV failed. The loss
The inverter supplying power to the controller for the to its emergency core
of power to the controller resulted in the FCV failing open valve caused
cooling system (ECCS) position of being fully open. The flow caused
an increase in system flow to 4400 gpm. This sudden, increased
the RHR pipe con- conditions where vortexing was expected at the suction of
nection to the RCS.
to an alternate
The power supply for the controllers was manually transferred
terminating the event.
source and the FCV was throttled, thus
Discussion:
flow through the
The FCV is manually throttled to maintain a desired rate of to control the
RHR heat exchanger. The heat exchanger flow rate is adjusted
to the vessel. Total system flow is
temperature of the water being returned with the
regulated by throttling the heat exchanger bypass valve coincident
adjustment of the FCV.
001230175 Z ((
' D*1 IC,
eo uachr
IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion. However, the increased system flow corresponded to the rate at which vortexing had
been calculated to occur based on the existing RCS level. The licensee had
previously determined maximum permitted flow rates for various reduced levels
of the RCS to prevent the possibility of vortexing and air entrainment into
the RHR pump.
Although RHR pump operation was never actually impaired, the potential existed
for air to be introduced to the pump's suction. This concern is exacerbated by
- the fact that the heat exchanger FCVs for both trains of RHR are powered from
the same inverter. Since the FCVs open fully on a loss of power, both trains
of RHR could become inoperable on a loss of power during mid-loop operation.
(A loss of instrument air would also cause the FCVs to fail to the full open
position and could also result in the loss of both trains of the RHR system).
During most modes of operation, having the FCVs go -fully open on loss of
power or instrument air is not a safety concern because having the valves
fully open does not normally prevent the system from performing its safety
function. However, having the valves go fully open while at mid-loop could
result in the loss of decay heat removal capability. This loss could persist
until electrical power or instrument air is restored and air is vented from
the RHR system.
The licensee has revised procedures for mid-loop operation to require manually
positioning the cold leg injection isolation valves to limit the maximum flow
through the system, even with the FCVs fully open. This lineup will be used
whenever the unit is at mid-loop and protects against the consequences of
failure of either electrical power or instrument air.
Several generic communications have been issued informing licensees of the
consequences of the loss of residual (decay) heat removal and the operating
conditions under which the probability of a loss increases; i.e., reduced
inventory conditions. The most recent publications include Generic Letter
(GL) No. 87-12, "Loss of Decay Heat Removal While the Reactor Coolant System
is Partially Filled;" GL No. 88-17, *Loss of Decay Heat Removal;" NRC In- formation Notice (IN)87-23, "Loss of Decay Heat Removal During Low Reactor
Coolant Level Operation;" IN 88-36, 'Possible Sudden Loss of RCS Inventory
During Low Coolant Level Operation;" and IN 89-67, "Loss of Residual Heat
Removal Caused by Accumulator Nitrogen Injection." The event described
above introduces a subtle failure scenario which licensees may not have
considered.
IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, irector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields, NRR
(301) 492-1173 Steve Bitter, RIV
(817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
I
IN 90-06 January 29, 1990 During this event, there were no indications of pump air ingestion However
the increased system flow enrraenan~nA n~ -~ neto. Hwvr
Attachment ~
q ) sx 90-06 Jasmary 2§ 1990
Page I of I
LIST OF RECEITLT ISSUED
NIR INFORtAT1011 OTICES
JCW --
lnfonation Issuance Issued te
Notice No. SubJect
90-05 Inter-System Discharge of 1/26/9O All holders of ULs
Reactor Coelant or Ch for nuclear
power reactors.
90-04 Cracking of the Upper Shall- 1/26/90 All holders of OLs
to-Transition Cone Girth or CPs.for Westinghouse.
Melds Is Steam Generators designed and Combustion
Engineering-disigned
nuclear power reactors.
90-03 malfunction of Borg-Varner 1/23/90 All holders of OLs
SBlted Sonnet Check Valves or CPs for uclewr
Causd by Failure of the power reactors.
Swing Arm
90-02 Potential Degradation of 1/29D All holders of OLs
Secondary Contaient or CPs for Slis.
90-01 lIportace of Proper 1/12/90 All holders of NRC
Response to Self-Identifted materials licenses.
Violations by Licensees
89-90 Pressurizer Safety Valv 12/28/84 All holder of OMs
Lift Setpoint Shift or Ch for Pilb.
89-8 Event Notificatton 12/26/89 All holders of CLs
Workshents or en for nuclear
powerreactors.
89-88 Recent XRC-Sponsored 12/26189 All holders of Ots
Testing of motor-Operated or CPsfor nutlear
Valves poer reactors.
8647 Disablilg of Emergency 12/19189 All helders of OLs
Diesel Generators by or CVs for nuclear
Their Neutral Ground-Fault power reactors.
Protection Circuitry
8945. etalclad. Lou-Voltage 12/IS/19 All holders of OLs
Supp. 2 Power Circuit Dreakars or CPsfor nuclear
Refurbished with power reactors.
Substandard Parts
OL*OpitunceS - _
CV s Construction Permit
UNITED STATES
IPOSTAGE & FEES PAOID
NUCLEAR REGULATORY COMMISSION ISNiRC 1 WASHINGTON, D.C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. 8300
IN 90-06 January 29, 1990 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields, NRR
(301) 492-1173 Steve Bitter, RIV
(817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR NRR:SRXB
- NFields: db *BCalure *DCFischer *CJHaughney *CHBerlinger *RJones
1/12/90 1/13/90 1/16/90 1/16/90 1/17/90 1/23/90
1/Z3'90
K)j V%2IN 90-
January , 1990 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact one of the technical
contacts listed below or the Regional Administrator of the appropriate regional
office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
EAB:NRR TECH:EDITOR EAB:NRR C:EAB:NRR C:OGCB:NRR N R B
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IN 90-
January , 1990
%...Z'age 3 of 3 No specific action or written response is required by this
infornation notice. If you have any questions about this matter, please contact the technical contact listed below or the Regional
Administrator of the appropriate regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Nick Fields (301) 492-1173 Steve Bitter (817) 897-1500
Attachment: List of Recently Issued NRC Information Notices
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list | - Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990)
- Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990, Topic: Liquid penetrant)
- Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990, Topic: Nondestructive Examination, Thermal fatigue)
- Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990)
- Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990)
- Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990)
- Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990)
- Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990)
- Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990, Topic: Decommissioning Funding Plan, Uranium Hexafluoride)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990)
- Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990)
- Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990)
- Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990, Topic: Brachytherapy)
- Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990, Topic: Earthquake)
- Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990)
- Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990)
- Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990)
- Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990)
- Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990, Topic: Reactor Vessel Water Level)
- Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990)
- Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990, Topic: Exclusive Use)
- Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990)
- Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990)
- Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990, Topic: Uranium Hexafluoride)
- Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990)
- Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990, Topic: Nondestructive Examination, Liquid penetrant)
- Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999, Topic: Dissimilar Metal Weld)
- Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990, Topic: Process Control Program)
- Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990)
- Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990, Topic: Overexposure)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990, Topic: Siren)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990, Topic: Siren)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990)
- Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990, Topic: Weak link)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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