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| {{#Wiki_filter:UNITED STATES P/-3Y NUCLEAR REGULATORY | | {{#Wiki_filter:UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | P/-3Y |
| WASHINGTON, D.C. 20555 May 24, 1994 NRC INFORMATION
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| NOTICE 94-36: UNDETECTED
| | OFFICE OF NUCLEAR REACTOR REGULATION |
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| ACCUMULATION | | WASHINGTON, D.C. 20555 May 24, 1994 NRC INFORMATION NOTICE 94-36: UNDETECTED ACCUMULATION OF GAS IN REACTOR |
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| OF GAS IN REACTOR COOLANT SYSTEM
| | COOLANT SYSTEM |
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| ==Addressees== | | ==Addressees== |
| All holders of operating | | All holders of operating licenses or construction permits for nuclear power |
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| licenses or construction
| | reactors. |
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| permits for nuclear power reactors.
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| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information |
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| Commission (NRC) is issuing this information | |
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| notice to alert addressees
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| to problems that could result from unrecognized
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| evolution
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| and accumulation
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| of gas in reactor coolant system high points. It is expected that recipients
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| will review this information
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| for applicability
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| to their facilities
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| and consider actions, as appropriate, to avoid similar problems.
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| However, suggestions
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| contained
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| in this information
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| notice are not NRC requirements;
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| therefore, no specific action or written response is required.Description
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| | |
| of Circumstances
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| Sequoyah Unit I had been shut down in March 1993. In early September
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| 1993, after the unit had been refueled, the reactor vessel was reassembled
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| and the reactor coolant system was degassed, filled, and vented. The reactor coolant system was then depressurized
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| to atmospheric
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| pressure.
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| One pressurizer
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| power-operated relief valve (PORV) was open and the reactor coolant system average temperature
| | notice to alert addressees to problems that could result from unrecognized |
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| was being maintained
| | evolution and accumulation of gas in reactor coolant system high points. It |
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| at approximately
| | is expected that recipients will review this information for applicability to |
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| 49C [120'F]. Nitrogen cover gas was being supplied to the volume control tank at approximately
| | their facilities and consider actions, as appropriate, to avoid similar |
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| 239 kPa [20 psig] and reactor coolant was being circulated
| | problems. However, suggestions contained in this information notice are not |
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| by the charging system and the residual heat removal (RHR) system. The reactor vessel level indication
| | NRC requirements; therefore, no specific action or written response is |
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| system (RVLIS) was functional
| | required. |
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| for a significant
| | ==Description of Circumstances== |
| | Sequoyah Unit I had been shut down in March 1993. In early September 1993, after the unit had been refueled, the reactor vessel was reassembled and the |
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| portion of the event. Before this event, instrument
| | reactor coolant system was degassed, filled, and vented. The reactor coolant |
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| maintenance
| | system was then depressurized to atmospheric pressure. One pressurizer power- operated relief valve (PORV) was open and the reactor coolant system average |
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| stickers were placed on the RVLIS indicators
| | temperature was being maintained at approximately 49C [120'F]. Nitrogen |
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| for other maintenance
| | cover gas was being supplied to the volume control tank at approximately |
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| work. Although the RVLIS information
| | 239 kPa [20 psig] and reactor coolant was being circulated by the charging |
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| was available, the operators
| | system and the residual heat removal (RHR) system. The reactor vessel level |
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| were not monitoring
| | indication system (RVLIS) was functional for a significant portion of the |
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| this information | | event. Before this event, instrument maintenance stickers were placed on the |
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| because it was not procedurally
| | RVLIS indicators for other maintenance work. Although the RVLIS information |
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| required to be used in shutdown modes of operation.
| | was available, the operators were not monitoring this information because it |
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| Reactor coolant system inventory
| | was not procedurally required to be used in shutdown modes of operation. |
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| was being monitored | | Reactor coolant system inventory was being monitored using pressurizer cold |
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| using pressurizer
| | calibration level indications. |
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| cold calibration
| | On December 17, 1993, the operators began to pressurize the containment to |
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| level indications.
| | 191 kPa [13 psig] in order to perform a containment integrated leak rate test. |
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| On December 17, 1993, the operators
| | As containment pressure increased, the operators noticed a decrease in |
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| began to pressurize
| | pressurizer water level and, over a period of time, added approximately 31,400 |
| | liters [8,300 gallons] of water to maintain the pressurizer level. Licensee |
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| the containment
| | personnel evaluated this situation and recognized that gas was accumulating in |
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| to 191 kPa [13 psig] in order to perform a containment | | the reactor coolant system. However, they failed to recognize the magnitude |
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| integrated
| | 9405190137 po\ fit JEote qq-f3tn 9t1S EsoI |
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| leak rate test.As containment
| | 'I' |
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| pressure increased, the operators
| | :..~-IN94-36 May 24, 1994 or cause of the problem. Three days later, as the containment was being |
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| noticed a decrease in pressurizer
| | depressurized upon completion of the containment leak test, the operators |
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| water level and, over a period of time, added approximately | | noted that approximately the same amount of water had to be removed from the |
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| 31,400 liters [8,300 gallons] of water to maintain the pressurizer
| | reactor coolant system to maintain the level. On December 21, 1993, on the |
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| level. Licensee personnel
| | basis of operators' observations of the changing coolant system Inventory |
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| evaluated
| | during the containment leak test, the reactor vessel head was vented. It was |
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| this situation
| | subsequently vented several times to maintain appropriate reactor vessel |
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| and recognized
| | inventory based on RYLIS information. The reactor vessel gas voiding |
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| that gas was accumulating
| | conditions went undetected from early September 1993, when the reactor coolant |
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| in the reactor coolant system. However, they failed to recognize
| | system was verified to be filled, until December 21, 1993, when the reactor |
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| the magnitude 9405190137 po\ fit JE ote qq-f3tn 9t1S EsoI'I'
| | head was vented. |
| :..~ -IN 94-36 May 24, 1994 or cause of the problem. Three days later, as the containment
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| was being depressurized
| | The gas evolution resulted from the temperature in the volume control tank |
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| upon completion
| | being much lower than that normally expected. (This lower temperature was due |
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| of the containment
| | to unusually low component cooling water temperatures and to a maintenance |
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| leak test, the operators noted that approximately
| | problem with a cooling water valve that resulted in the reduction of the heat |
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| the same amount of water had to be removed from the reactor coolant system to maintain the level. On December 21, 1993, on the basis of operators' | | sink temperature in the letdown heat exchanger.) The lower temperatures |
| observations
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| of the changing coolant system Inventory during the containment | | increased the solubility of gas in the volume control tank water so that more |
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| leak test, the reactor vessel head was vented. It was subsequently
| | gas was dissolved in the water. This gas evolved when the water was |
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| vented several times to maintain appropriate
| | transferred to the reactor coolant system by the charging system and heated up |
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| reactor vessel inventory | | in the reactor vessel. |
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| based on RYLIS information.
| | Further details concerning this event are in NRC Inspection Report No. 50-327; |
| | | 50-328/94-04. |
| The reactor vessel gas voiding conditions
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| went undetected
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| from early September
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| 1993, when the reactor coolant system was verified to be filled, until December 21, 1993, when the reactor head was vented.The gas evolution
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| resulted from the temperature
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| in the volume control tank being much lower than that normally expected. (This lower temperature
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| was due to unusually
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| low component
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| cooling water temperatures
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| and to a maintenance
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| problem with a cooling water valve that resulted in the reduction
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| of the heat sink temperature
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| in the letdown heat exchanger.)
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| ===The lower temperatures===
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| increased
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| the solubility
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| of gas in the volume control tank water so that more gas was dissolved
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| in the water. This gas evolved when the water was transferred
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| to the reactor coolant system by the charging system and heated up in the reactor vessel.Further details concerning
| |
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| this event are in NRC Inspection | |
| | |
| Report No. 50-327;50-328/94-04. | |
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| Discussion | | Discussion |
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| The licensee completed | | The licensee completed a final evaluation in January 1994 and determined that |
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| a final evaluation
| | during this event the reactor vessel water level had decreased to slightly |
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| in January 1994 and determined
| | below the top of the hot leg, and that the steam generator tubes were nearly |
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| that during this event the reactor vessel water level had decreased
| | empty. The reactor coolant system inventory was being monitored solely on the |
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| to slightly below the top of the hot leg, and that the steam generator
| | basis of pressurizer level, which was not indicative of the reactor vessel and |
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| tubes were nearly empty. The reactor coolant system inventory
| | steam generator levels. Calculations by the licensee indicated that an |
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| was being monitored | | equilibrium had been reached during the event so that the water level was |
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| solely on the basis of pressurizer
| | approximately 1.6 meters [5.25 feet] above the top of the core. Any |
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| level, which was not indicative
| | additional gas evolved in the reactor vessel would be expected to be vented |
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| of the reactor vessel and steam generator
| | through the hot leg and surge line to the pressurizer and out through the open |
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| levels. Calculations
| | pressurizer PORV. |
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| by the licensee indicated
| | The reactor water level at which equilibrium was established at Sequoyah was |
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| that an equilibrium
| | sufficiently high so as not to interfere with reactor coolant flow through the |
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| had been reached during the event so that the water level was approximately
| | RHR cooling system. However, at other plants, the equilibrium level, which is |
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| 1.6 meters [5.25 feet] above the top of the core. Any additional
| | related to pressurizer surge line geometry and RHR suction line location, might be such that a similar event could interfere with shutdown cooling. |
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| gas evolved in the reactor vessel would be expected to be vented through the hot leg and surge line to the pressurizer
| | Another potential safety concern is related to the capability of the steam |
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| and out through the open pressurizer
| | generators to transfer heat from the reactor coolant to secondary coolant. In |
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| PORV.The reactor water level at which equilibrium
| | the equilibrium condition at Sequoyah, the steam generator tubes were almost |
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| was established
| | empty during at least a portion of the duration of this event. During this |
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| at Sequoyah was sufficiently
| | IN 94-36 |
| | --JMay 24, 1994 period, the steam generators were assumed to be available as an alternate |
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| high so as not to interfere
| | means for shutdown cooling. It is not clear that cooling through the steam |
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| with reactor coolant flow through the RHR cooling system. However, at other plants, the equilibrium
| | generators could have been established, if needed, especially because the |
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| level, which is related to pressurizer
| | plant operators were unaware that the tubes were empty. |
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| surge line geometry and RHR suction line location, might be such that a similar event could interfere
| | Several factors involving licensee performance contributed to the delay in the |
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| with shutdown cooling.Another potential
| | identification and evaluation of this event. They included (1) lack of |
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| safety concern is related to the capability
| | consideration on the part of licensee personnel with respect to compression of |
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| of the steam generators
| | gas in the system caused by containment pressure transmitted to the reactor |
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| to transfer heat from the reactor coolant to secondary
| | coolant system water through the open pressurizer PORV; (2) misunderstanding |
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| coolant. In the equilibrium
| | by the operators about the operability of RVLIS; (3) failure to stop the |
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| condition
| | containment leak test when water level changes were first noted so that the |
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| at Sequoyah, the steam generator
| | situation could have been adequately evaluated; (4) an apparent lack of |
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| tubes were almost empty during at least a portion of the duration of this event. During this
| | thorough evaluation of previously published information on similar events. |
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| |
|
| IN 94-36--JMay 24, 1994 period, the steam generators
| | The event discussed in this information notice highlights the potential for |
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| were assumed to be available
| | gas evolution and accumulation in the reactor coolant system in locations and |
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| as an alternate means for shutdown cooling. It is not clear that cooling through the steam generators
| | quantities that may not be evident to operators. Changes in temperature and |
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| could have been established, if needed, especially
| | pressure can have significant effects on the solubility of gas in water, especially at or near atmospheric pressure conditions. During cold shutdown, this phenomenon can permit significant quantities of cover gas to be dissolved |
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| |
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| because the plant operators
| | in lower-temperature, higher-pressure volumes such as the volume control tank |
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| |
|
| were unaware that the tubes were empty.Several factors involving
| | and to evolve into a large gas bubble in the reactor vessel (a lower-pressure, higher-temperature area). This phenomenon can occur without a sudden change |
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| |
|
| licensee performance
| | in pressurizer level, which is the indicator normally used by the operators to |
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| |
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| contributed
| | monitor water inventory. Use of available instrumentation in shutdown modes |
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| |
|
| to the delay in the identification | | to monitor reactor vessel water level can provide detection of unexpected |
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| and evaluation
| | system conditions when reduced vessel inventory is not planned as well as in |
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| of this event. They included (1) lack of consideration
| | reduced inventory evolutions. |
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| on the part of licensee personnel
| | On April 12, 1994, a similar gas accumulation event was identified at the |
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| with respect to compression
| | Salem Generating Station (Unit 1) shortly after it entered Mode 5 (cold |
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| of gas in the system caused by containment | | shutdown) operation. Although this occurrence did not involve amounts of gas |
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| pressure transmitted
| | accumulation as large as in the Sequoyah event, many similarities existed |
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| |
|
| to the reactor coolant system water through the open pressurizer
| | regarding both the process of gas formation and the lack of operator awareness |
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| |
|
| PORV; (2) misunderstanding
| | of the abnormal condition. In both events, reactor vessel level information |
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| |
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| by the operators
| | was or could have been made available for prompt identification of the |
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| about the operability
| | problem. |
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|
| of RVLIS; (3) failure to stop the containment
| | Related Generic Communications |
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| |
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| leak test when water level changes were first noted so that the situation
| | * NRC Information Notice 93-12, "Off-Gassing in Auxiliary Feedwater |
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| |
|
| could have been adequately
| | System Raw Water Sources," discusses similar solubility |
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| |
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| evaluated;
| | considerations related to air pockets in piping at the McGuire |
| (4) an apparent lack of thorough evaluation
| |
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| |
|
| of previously
| | Nuclear Station. |
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| |
|
| published
| | * NRC Information Notice 87-46, "Undetected Loss of Reactor |
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| |
|
| information
| | Coolant," discusses undetected loss of reactor coolant inventory |
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| |
|
| on similar events.The event discussed
| | at North Anna Unit 1 resulting from inadequate use of available |
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| |
|
| in this information
| | indications and failure to perform mass inventory balances. |
|
| |
|
| notice highlights | | - \ > |
| | <_IN 94-36 May 24, 1994 This information notice requires no specific action or written response. If |
|
| |
|
| the potential | | you have any questions about the information in this notice, please contact |
|
| |
|
| for gas evolution
| | one of the technical contacts listed below or the appropriate Of ice of |
|
| |
|
| and accumulation
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| in the reactor coolant system in locations
| | Brian K. Grimes, Director |
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| |
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| and quantities
| | Division of Operating Reactor Support |
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| |
|
| that may not be evident to operators.
| | Office of Nuclear Reactor Regulation |
|
| |
|
| Changes in temperature
| | Technical contacts: R. Benedict, NRR |
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| |
|
| and pressure can have significant
| | (301) 504-1157 S. M. Shaeffer, RII |
|
| |
|
| effects on the solubility
| | (615) 842-8001 Attachment: |
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| |
|
| of gas in water, especially | | ===List of Recently Issued NRC Information Notices=== |
|
| |
|
| at or near atmospheric
| | I At,.thment |
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| |
|
| pressure conditions.
| | IN 94-36 May 24, 1994 LIST OF RECENTLY ISSUED |
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|
| During cold shutdown, this phenomenon
| | NRC INFORMATION NOTICES |
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| |
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| can permit significant
| | Information Date of |
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| |
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| quantities
| | Notice No. Subject Issuance Issued to |
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| |
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| of cover gas to be dissolved in lower-temperature, higher-pressure
| | 91-81, Switchyard Problems that 05/19/94 All holders of OLs or CPs |
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| |
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| volumes such as the volume control tank and to evolve into a large gas bubble in the reactor vessel (a lower-pressure, higher-temperature
| | Supp. 1 Contribute to Loss of for nuclear power reactors. |
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| |
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| area). This phenomenon
| | Offsite Power |
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| |
|
| can occur without a sudden change in pressurizer
| | 94-35 NIOSH Respirator User 05/16/94 All holders of OLs or CPs |
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| |
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| level, which is the indicator
| | Notices, "Inadvertent for nuclear power reactors, Separation of the Mask- and all licensed fuel |
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| |
|
| normally used by the operators
| | Mounted Regulator (MMR) facilities. |
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| |
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| to monitor water inventory.
| | from the Facepiece on the |
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| |
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| Use of available
| | Mine Safety Appliances (MSA) |
| | Company MMR Self-Contained |
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| |
|
| instrumentation
| | Breathing Apparatus (SCBA) |
| | and Status Update |
|
| |
|
| in shutdown modes to monitor reactor vessel water level can provide detection
| | 94-34 Thermo-Lag 330-660 05/13/94 All holders of OLs or CPs |
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| |
|
| of unexpected
| | Flexi-Blanket Ampacity for nuclear power reactors. |
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| |
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| system conditions
| | Derating Concerns |
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| |
|
| when reduced vessel inventory
| | 94-33 Capacitor Failures in 05/09/94 All holders of OLs or CPs |
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| |
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| is not planned as well as in reduced inventory
| | Westinghouse Eagle 21 for nuclear power reactors. |
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| |
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| evolutions.
| | Plant Protection Systems |
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| |
|
| On April 12, 1994, a similar gas accumulation
| | 93-53, Effect of Hurricane 04/29/94 All holders of OLs or CPs |
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| |
|
| event was identified
| | Supp. 1 Andrew on Turkey Point for nuclear power reactors. |
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| |
|
| at the Salem Generating
| | Nuclear Generating |
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| |
|
| Station (Unit 1) shortly after it entered Mode 5 (cold shutdown) | | Station and Lessons Learned |
| operation.
| |
|
| |
|
| Although this occurrence
| | 94-32 Revised Seismic Hazard 04/29/94 All holders of OLs or CPs |
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| |
|
| did not involve amounts of gas accumulation
| | Estimates for nuclear power reactors. |
|
| |
|
| as large as in the Sequoyah event, many similarities
| | 94-31 Potential Failure of 04/14/94 All holders of OLs or CPs |
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| |
|
| existed regarding
| | Wilco, Lexan-Type HN-4-L for nuclear power reactors. |
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| |
|
| both the process of gas formation
| | Fire Hose Nozzles |
|
| |
|
| and the lack of operator awareness of the abnormal condition.
| | 90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs |
|
| |
|
| ===In both events, reactor vessel level information===
| | Supp. 1 of Reactor Coolant Pump for pressurized water |
| was or could have been made available
| |
|
| |
|
| for prompt identification
| | Bolts reactors. |
|
| |
|
| of the problem.Related Generic Communications | | 94-30 Leaking Shutdown Cooling 04/12/94 All holders of OLs or CPs |
|
| |
|
| * NRC Information
| | Isolation Valves at for nuclear power reactors. |
|
| |
|
| Notice 93-12, "Off-Gassing
| | Cooper Nuclear Station |
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| |
|
| in Auxiliary
| | OL - Operating License |
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| |
|
| Feedwater System Raw Water Sources," discusses
| | CP - Construction Permit |
|
| |
|
| similar solubility
| | IN 94-xx |
|
| |
|
| considerations
| | May xx, 1994 This information notice requires no specific action or written response. If |
|
| |
|
| related to air pockets in piping at the McGuire Nuclear Station.* NRC Information
| | you have any questions about the information in this notice, please contact |
|
| |
|
| Notice 87-46, "Undetected
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| Loss of Reactor Coolant," discusses
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| undetected
| | Brian K. Grimes, Director |
|
| |
|
| loss of reactor coolant inventory at North Anna Unit 1 resulting
| | Division of Operating Reactor Support |
|
| |
|
| from inadequate
| | Office of Nuclear Reactor Regulation |
|
| |
|
| use of available indications
| | Technical contacts: R. Benedict, NRR |
|
| |
|
| and failure to perform mass inventory
| | (301) 504-1157 S. M. Shaeffer, R11 |
| | (615) 842-8001 Attachment: |
| | List of Recently Issued NRC Information Notices |
|
| |
|
| balances.
| | *See Dnrvinim- wBw |
|
| |
|
| -\ > <_IN 94-36 May 24, 1994 This information
| | concurrence |
|
| |
|
| notice requires no specific action or written response.
| | -_. _ . |
|
| |
|
| If you have any questions
| | --- - 1 _._ |
| | OFFICE *OEAB:DORS *DRP:RII *OGCB:DORS *SC/DRP:RII *TECH ED |
|
| |
|
| about the information
| | NAME RBenedict SMShaeffer PCWen MLesser MFMejac |
|
| |
|
| in this notice, please contact one of the technical
| | lDATE 05/04/L94 05/05/94 05/05/94 05/05/94 05/05/94 |
| | [*AC/SRXB:DSSA *AD/DSSA *C/OEAB:DORS *AC/OGCB:DORS D/DORS |
|
| |
|
| contacts listed below or the appropriate
| | TECollins MVirgilio AChaffee AJKugler BKGrimes |
|
| |
|
| Of ice of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | 05/06/94 05/09/94 05/09/94 05.12/94 / /94 DOCUMENT NAME: SLQGAbIN.KV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | informed of the development of this information notice and they have |
| Technical
| |
|
| |
|
| contacts:
| | reviewed the draft information notice. |
| R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, RII (615) 842-8001 Attachment:
| |
| List of Recently Issued NRC Information
| |
|
| |
|
| Notices
| | Peter Wen, 5/10/94 |
|
| |
|
| ===I At,.thment===
| | IN 94-xx |
| IN 94-36 May 24, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION | |
|
| |
|
| NOTICES Information
| | May xx, 1994 This information notice requires no specific action or written response. |
|
| |
|
| Date of Notice No. Subject Issuance Issued to 91-81, Supp. 1 94-35 94-34 94-33 93-53, Supp. 1 94-32 94-31 90-68, Supp. 1 94-30 Switchyard
| | you have any questions about the information in this notice, please contactIf |
|
| |
|
| Problems that Contribute
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| to Loss of Offsite Power NIOSH Respirator
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| User Notices, "Inadvertent
| | Brian K. Grimes, Director |
|
| |
|
| Separation
| | Division of Operating Reactor Support |
|
| |
|
| of the Mask-Mounted Regulator (MMR)from the Facepiece | | Office of Nuclear Reactor Regulation |
|
| |
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| on the Mine Safety Appliances (MSA)Company MMR Self-Contained
| | Technical Contacts: R. Benedict, NRR |
|
| |
|
| Breathing
| | (301) 504-1157 S. M. Shaeffer, RI! |
| | (615) 842-8001 Attachment: |
| | List of Recently Issued NRC Information Notices |
|
| |
|
| Apparatus (SCBA)and Status Update Thermo-Lag
| | *See previous concurrence |
|
| |
|
| 330-660 Flexi-Blanket
| | OFFICE *OEAB:DORS *DRP:RII *OGCB:DORS *SC/DRP:RII *TECH ED |
|
| |
|
| Ampacity Derating Concerns Capacitor
| | NAME RBenedict SMShaeffer PCWen MLesser MFMejac |
|
| |
|
| Failures in Westinghouse
| | DATE 05/04/94 05/05/94 05/05/94 05/05/94 05/05/94 |
| | *AC/SRXB:DSSA *AD/DSSA *C/OEAB:DORS *AC/OGCB:DORS D/DORS |
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| |
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| Eagle 21 Plant Protection
| | TECollins 8EXI MVirgilio I AChaffee AJKugler BKGrimes |
|
| |
|
| Systems Effect of Hurricane Andrew on Turkey Point Nuclear Generating
| | 05/06/94 1 05/09/94 05/09/94 05/12/94 / /94 nnlflMFNT IAMr. eCnveCTitn .* niti |
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| Station and Lessons Learned Revised Seismic Hazard Estimates Potential
| | .-- -- I ia11 I EAdIL* .JLA(Un4.1 r A |
|
| |
|
| Failure of Wilco, Lexan-Type
| | NOTE: The PMs for Sequoyah (D.LaBarge) and Salem (J.Stone) have been |
|
| |
|
| HN-4-L Fire Hose Nozzles Stress Corrosion
| | informed of the development of this information notice and they have |
|
| |
|
| Cracking of Reactor Coolant Pump Bolts Leaking Shutdown Cooling Isolation
| | reviewed the draft information notice. |
|
| |
|
| Valves at Cooper Nuclear Station 05/19/94 05/16/94 05/13/94 05/09/94 04/29/94 04/29/94 04/14/94 04/14/94 04/12/94 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors, and all licensed fuel facilities.
| | Peter Wen, 5/10/94 |
|
| |
|
| All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of 01 or CPs for pressurized
| | IN 94-xx |
|
| |
|
| water reactors.All holders of OLs or CPs for nuclear power reactors.OL -Operating
| | May xx, 1994 This information notice requires no specific action or written response. If |
|
| |
|
| License CP -Construction
| | you have any questions about the information in this notice, please contact |
|
| |
|
| Permit
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| IN 94-xx May xx, 1994 This information
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| notice requires no specific action or written response.
| | Brian K. Grimes, Director |
|
| |
|
| If you have any questions
| | Division of Operating Reactor Support |
|
| |
|
| about the information
| | Office of Nuclear Reactor Regulation |
|
| |
|
| in this notice, please contact one of the technical
| | Technical Contacts: R. Benedict, NRR |
|
| |
|
| contacts listed below or the appropriate
| | (301) 504-1157 S. M. Shaeffer, R11 |
| | (615) 842-8001 Attachment: |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | ===List of Recently Issued NRC Information Notices=== |
| | See previous concurrence |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | OFFICE l *OEAB:DORS *DRP:RII *OGCB:DORS l *SC/DRP:RII *TECH ED |
| Technical
| |
|
| |
|
| contacts: R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, R11 (615) 842-8001 Attachment:
| | NAME } RBenedict SMShaeffer PCWen MLesser MFMejac |
| List of Recently Issued NRC Information
| |
|
| |
|
| Notices*See Dnrvinim- concurrence
| | DATE 1 05/04/94 1_05/05/94 1 05/05/94 _ 05/05/94 1 05/05/94 |
| | *AC/SRXB:DSSA *AD/DSSA j *C/OEAB:DORS AC/OGCB:DORS D/DORS |
|
| |
|
| ---- wBw _. _ .-1 _._OFFICE *OEAB:DORS
| | TECollins MVirgilio AChaffee AJKugler i(: BKGrimes |
|
| |
|
| *DRP:RII *OGCB:DORS
| | 05/06/94 = 05/09/94 05/09/94 5/1V94 / /94 DOCUMENT NAME: SEQGASIN.RV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been |
|
| |
|
| *SC/DRP:RII
| | informed of the development of this information notice and they have |
|
| |
|
| *TECH ED NAME RBenedict
| | reviewed the draft information notice. |
|
| |
|
| SMShaeffer
| | Peter Wen, 5/10/94 |
|
| |
|
| PCWen MLesser MFMejaclDATE 05/04/L94
| | IN 94-xx |
| 05/05/94 05/05/94 05/05/94 05/05/94[*AC/SRXB:DSSA
| |
|
| |
|
| *AD/DSSA *C/OEAB:DORS
| | May xx, 1994 This information notice requires no specific action or writttten response. If |
|
| |
|
| *AC/OGCB:DORS
| | you have any questions about the information in this notice, please contact |
|
| |
|
| D/DORS TECollins
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| MVirgilio
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| AChaffee AJKugler BKGrimes 05/06/94 05/09/94 05/09/94 05.12/94 / /94 DOCUMENT NAME: SLQGAbIN.KV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J.informed of the development
| | Brian K. Grimes, Director |
|
| |
|
| of this information | | Division of Operating Reactor Support |
|
| |
|
| reviewed the draft information
| | Office of Nuclear Reactor Regulation |
|
| |
|
| notice.Stone) have been notice and they have Peter Wen, 5/10/94 IN 94-xx May xx, 1994 This information
| | Technical Contacts: R. Benedict, NRR |
|
| |
|
| notice requires no specific action or written response.
| | (301) 504-1157 S. M. Shaeffer, RII |
|
| |
|
| If you have any questions
| | (615) 842-8001 Attachment: |
|
| |
|
| about the information
| | ===List of Recently Issued NRC Information Notices=== |
| | OFFICE IOEABDOR5 DRP:RIIpcyJ OGCB__ _ SC/DRP:RI TECH ED |
|
| |
|
| in this notice, please contact the technical
| | NAME Benedict 'MShaeffer PCWen Lesser |
|
| |
|
| contact listed below or the appropriate
| | DATE </A/94 5 /5/94 5 / 94/94 5//94 5 / 5/94 AC/SRXB:DSSA , AD/DSSA jC/OEAB:DORS AC/OGCB:DORS D/DORS |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | TEColli MVirgil ' A2 fe AJKugler BKGrimes |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | _____94 |
| Technical
| | /$\/94 /947/94 94 / /94 UULUMtN I NAML: btbAbI1 N.KV1 x 01 I J//q jp' |
| | A4Mi: THE R& FR FoY(AH (-. LAMRPE) Azb 6MPA (j. ) |
| | ROeia^ SoF'E Deospwt oF Ttts um. waIce ARD |
|
| |
|
| Contacts: R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, RI!(615) 842-8001 Attachment:
| | 'NW ME .F) T"E JPV OD0e bWf^ . |
| List of Recently Issued NRC Information
| |
|
| |
|
| Notices*See previous concurrence
| | &4-vhiw S/o/oA4. |
|
| |
|
| OFFICE *OEAB:DORS
| | IN 94-36 May 24, 1994 This information notice requires no specific action or written response. If |
|
| |
|
| *DRP:RII *OGCB:DORS
| | you have any questions about the information in this notice, please contact |
|
| |
|
| *SC/DRP:RII
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| *TECH ED NAME RBenedict
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| SMShaeffer
| | orig /s/'d by BKGrimes |
|
| |
|
| PCWen MLesser MFMejac DATE 05/04/94 05/05/94 05/05/94 05/05/94 05/05/94*AC/SRXB:DSSA
| | Brian K. Grimes, Director |
|
| |
|
| *AD/DSSA *C/OEAB:DORS
| | Division of Operating Reactor Support |
|
| |
|
| *AC/OGCB:DORS
| | Office of Nuclear Reactor Regulation |
|
| |
|
| D/DORS TECollins
| | Technical contacts: R. Benedict, NRR |
|
| |
|
| 8EXI MVirgilio
| | (301) 504-1157 S. M. Shaeffer, R11 |
| | (615) 842-8001 Attachment: |
|
| |
|
| I AChaffee AJKugler BKGrimes 05/06/94 1 05/09/94 05/09/94 05/12/94 / /94 nnlflMFNT
| | ===List of Recently Issued NRC Information Notices=== |
| | E |
|
| |
|
| IAMr. eCnveCTit
| | *See Previous concurrence |
|
| |
|
| niti.-- -- I ia11 I EAdIL* .JLA(Un4.1 n .* r A NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J.informed of the development
| | OFFICE |
|
| |
|
| of this information
| | NAME |
|
| |
|
| reviewed the draft information
| | *OEAB:DORS |
|
| |
|
| notice.Stone) have been notice and they have Peter Wen, 5/10/94 IN 94-xx May xx, 1994 This information
| | RBenedict |
|
| |
|
| notice requires no specific action or written response.
| | *DRP:RII |
| | |
| If you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact the technical
| |
| | |
| contact listed below or the appropriate
| |
| | |
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| |
| | |
| ===Reactor Support Office of Nuclear Reactor Regulation===
| |
| Technical
| |
| | |
| Contacts: R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, R11 (615) 842-8001 Attachment:
| |
| List of Recently Issued NRC Information
| |
| | |
| ===Notices See previous concurrence===
| |
| OFFICE l *OEAB:DORS
| |
| | |
| *DRP:RII *OGCB:DORS | |
| | |
| l *SC/DRP:RII
| |
| | |
| *TECH ED NAME } RBenedict
| |
|
| |
|
| SMShaeffer | | SMShaeffer |
|
| |
|
| PCWen MLesser MFMejac DATE 1 05/04/94 1_05/05/94
| | *OGCB:DORS |
| 1 05/05/94 _ 05/05/94 1 05/05/94*AC/SRXB:DSSA
| |
| | |
| *AD/DSSA j *C/OEAB:DORS
| |
| | |
| AC/OGCB:DORS
| |
| | |
| D/DORS TECollins
| |
| | |
| MVirgilio
| |
| | |
| AChaffee AJKugler i(: BKGrimes 05/06/94 = 05/09/94 05/09/94 5/1V94 / /94 DOCUMENT NAME: SEQGASIN.RV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J.informed of the development
| |
| | |
| of this information
| |
| | |
| reviewed the draft information
| |
| | |
| notice.Stone) have been notice and they have Peter Wen, 5/10/94 IN 94-xx May xx, 1994 This information
| |
| | |
| notice requires no specific action or writttten
| |
| | |
| response.you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact the technical
| |
| | |
| contact listed below or the appropriate
| |
| | |
| Office of Nuclear Reactor Regulation (NRR) project manager.If Brian K. Grimes, Director Division of Operating
| |
| | |
| ===Reactor Support Office of Nuclear Reactor Regulation===
| |
| Technical
| |
| | |
| Contacts: R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, RII (615) 842-8001 Attachment:
| |
| List of Recently Issued NRC Information
| |
| | |
| Notices OFFICE IOEABDOR5 DRP:RIIpcyJ
| |
| | |
| OGCB_ _ _ SC/DRP:RI
| |
| | |
| TECH ED NAME Benedict 'MShaeffer
| |
| | |
| PCWen Lesser DATE </A/94 5 /5/94 5 / 94/94 5//94 5 / 5/94 AC/SRXB:DSSA , AD/DSSA j C/OEAB:DORS
| |
| | |
| AC/OGCB:DORS
| |
| | |
| D/DORS TEColli MVirgil ' A2 fe AJKugler BKGrimes_____94 /$\/94 /947/94 94 / /94 UULUMtN I NAML: x 01 I J//q btbAbI1 N.KV1 jp'A4Mi: THE R& FR FoY(AH (-. LAMRPE) Azb 6MPA (j. )ROeia^ SoF'E Deospwt oF Ttts um. waIce ARD'NW ME .F) T"E JPV O D0e bWf ^ .&4-vhiw S/o/oA4.
| |
| | |
| IN 94-36 May 24, 1994 This information
| |
|
| |
|
| notice requires no specific action or written response.
| | PCWen |
| | |
| If you have any questions
| |
| | |
| about the information
| |
| | |
| in this notice, please contact one of the technical
| |
| | |
| contacts listed below or the appropriate
| |
| | |
| Office of Nuclear Reactor Regulation (NRR) project manager.orig /s/'d by BKGrimes Brian K. Grimes, Director Division of Operating
| |
| | |
| ===Reactor Support Office of Nuclear Reactor Regulation===
| |
| Technical
| |
| | |
| contacts: R. Benedict, NRR (301) 504-1157 S. M. Shaeffer, R11 (615) 842-8001 Attachment:
| |
| List of Recently Issued NRC Information
| |
| | |
| Notices*See Previous concurrence
| |
| | |
| E OFFICE *OEAB:DORS
| |
| | |
| *DRP:RII *OGCB:DORS
| |
|
| |
|
| *SC/DRP:RII | | *SC/DRP:RII |
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| *TECH ED NAME RBenedict
| | MLesser |
| | |
| SMShaeffer
| |
| | |
| PCWen MLesser MFMejac DATE j05/04/94
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| 05/05/94 05/05/94 05/05/94 05/05/94l*AC/SRXB:DSSA
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| *AD/DSSA 5*C/OEAB:DORS | | *TECH ED |
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| *AC/OGCB:DO
| | MFMejac |
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| RS*TECollins | | DATE j05/04/94 05/05/94 05/05/94 05/05/94 05/05/94 l*AC/SRXB:DSSA *AD/DSSA 5*C/OEAB:DORS *AC/OGCB:DO RS* |
| | TECollins MVirgilio AChaffee IvAJKugler _s |
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| |
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| MVirgilio
| | 05/06/94 05/09/94 i 05/09/94 05/12/4 05//f/94 UuUMtrII NAMt: vq-io. IN |
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|
| AChaffee AJKugler Iv _s 05/06/94 05/09/94 i 05/09/94 05/12/4 05//f/94 UuUMtrII NAM t: vq-io. IN NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J.informed of the development
| | NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been |
|
| |
|
| of this information | | informed of the development of this information notice and they have |
|
| |
|
| reviewed the draft information | | reviewed the draft information notice. |
|
| |
|
| notice.Stone) have been notice and they have Peter Wen, 5/10/94}}
| | Peter Wen, 5/10/94}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Undetected Accumulation of Gas in Reactor Coolant SystemML031060539 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
05/24/1994 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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-nr IN-94-036, NUDOCS 9405190137 |
Download: ML031060539 (10) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
P/-3Y
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 24, 1994 NRC INFORMATION NOTICE 94-36: UNDETECTED ACCUMULATION OF GAS IN REACTOR
COOLANT SYSTEM
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to problems that could result from unrecognized
evolution and accumulation of gas in reactor coolant system high points. It
is expected that recipients will review this information for applicability to
their facilities and consider actions, as appropriate, to avoid similar
problems. However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action or written response is
required.
Description of Circumstances
Sequoyah Unit I had been shut down in March 1993. In early September 1993, after the unit had been refueled, the reactor vessel was reassembled and the
reactor coolant system was degassed, filled, and vented. The reactor coolant
system was then depressurized to atmospheric pressure. One pressurizer power- operated relief valve (PORV) was open and the reactor coolant system average
temperature was being maintained at approximately 49C [120'F]. Nitrogen
cover gas was being supplied to the volume control tank at approximately
239 kPa [20 psig] and reactor coolant was being circulated by the charging
system and the residual heat removal (RHR) system. The reactor vessel level
indication system (RVLIS) was functional for a significant portion of the
event. Before this event, instrument maintenance stickers were placed on the
RVLIS indicators for other maintenance work. Although the RVLIS information
was available, the operators were not monitoring this information because it
was not procedurally required to be used in shutdown modes of operation.
Reactor coolant system inventory was being monitored using pressurizer cold
calibration level indications.
On December 17, 1993, the operators began to pressurize the containment to
191 kPa [13 psig] in order to perform a containment integrated leak rate test.
As containment pressure increased, the operators noticed a decrease in
pressurizer water level and, over a period of time, added approximately 31,400
liters [8,300 gallons] of water to maintain the pressurizer level. Licensee
personnel evaluated this situation and recognized that gas was accumulating in
the reactor coolant system. However, they failed to recognize the magnitude
9405190137 po\ fit JEote qq-f3tn 9t1S EsoI
'I'
- ..~-IN94-36 May 24, 1994 or cause of the problem. Three days later, as the containment was being
depressurized upon completion of the containment leak test, the operators
noted that approximately the same amount of water had to be removed from the
reactor coolant system to maintain the level. On December 21, 1993, on the
basis of operators' observations of the changing coolant system Inventory
during the containment leak test, the reactor vessel head was vented. It was
subsequently vented several times to maintain appropriate reactor vessel
inventory based on RYLIS information. The reactor vessel gas voiding
conditions went undetected from early September 1993, when the reactor coolant
system was verified to be filled, until December 21, 1993, when the reactor
head was vented.
The gas evolution resulted from the temperature in the volume control tank
being much lower than that normally expected. (This lower temperature was due
to unusually low component cooling water temperatures and to a maintenance
problem with a cooling water valve that resulted in the reduction of the heat
sink temperature in the letdown heat exchanger.) The lower temperatures
increased the solubility of gas in the volume control tank water so that more
gas was dissolved in the water. This gas evolved when the water was
transferred to the reactor coolant system by the charging system and heated up
in the reactor vessel.
Further details concerning this event are in NRC Inspection Report No. 50-327;
50-328/94-04.
Discussion
The licensee completed a final evaluation in January 1994 and determined that
during this event the reactor vessel water level had decreased to slightly
below the top of the hot leg, and that the steam generator tubes were nearly
empty. The reactor coolant system inventory was being monitored solely on the
basis of pressurizer level, which was not indicative of the reactor vessel and
steam generator levels. Calculations by the licensee indicated that an
equilibrium had been reached during the event so that the water level was
approximately 1.6 meters [5.25 feet] above the top of the core. Any
additional gas evolved in the reactor vessel would be expected to be vented
through the hot leg and surge line to the pressurizer and out through the open
pressurizer PORV.
The reactor water level at which equilibrium was established at Sequoyah was
sufficiently high so as not to interfere with reactor coolant flow through the
RHR cooling system. However, at other plants, the equilibrium level, which is
related to pressurizer surge line geometry and RHR suction line location, might be such that a similar event could interfere with shutdown cooling.
Another potential safety concern is related to the capability of the steam
generators to transfer heat from the reactor coolant to secondary coolant. In
the equilibrium condition at Sequoyah, the steam generator tubes were almost
empty during at least a portion of the duration of this event. During this
IN 94-36
--JMay 24, 1994 period, the steam generators were assumed to be available as an alternate
means for shutdown cooling. It is not clear that cooling through the steam
generators could have been established, if needed, especially because the
plant operators were unaware that the tubes were empty.
Several factors involving licensee performance contributed to the delay in the
identification and evaluation of this event. They included (1) lack of
consideration on the part of licensee personnel with respect to compression of
gas in the system caused by containment pressure transmitted to the reactor
coolant system water through the open pressurizer PORV; (2) misunderstanding
by the operators about the operability of RVLIS; (3) failure to stop the
containment leak test when water level changes were first noted so that the
situation could have been adequately evaluated; (4) an apparent lack of
thorough evaluation of previously published information on similar events.
The event discussed in this information notice highlights the potential for
gas evolution and accumulation in the reactor coolant system in locations and
quantities that may not be evident to operators. Changes in temperature and
pressure can have significant effects on the solubility of gas in water, especially at or near atmospheric pressure conditions. During cold shutdown, this phenomenon can permit significant quantities of cover gas to be dissolved
in lower-temperature, higher-pressure volumes such as the volume control tank
and to evolve into a large gas bubble in the reactor vessel (a lower-pressure, higher-temperature area). This phenomenon can occur without a sudden change
in pressurizer level, which is the indicator normally used by the operators to
monitor water inventory. Use of available instrumentation in shutdown modes
to monitor reactor vessel water level can provide detection of unexpected
system conditions when reduced vessel inventory is not planned as well as in
reduced inventory evolutions.
On April 12, 1994, a similar gas accumulation event was identified at the
Salem Generating Station (Unit 1) shortly after it entered Mode 5 (cold
shutdown) operation. Although this occurrence did not involve amounts of gas
accumulation as large as in the Sequoyah event, many similarities existed
regarding both the process of gas formation and the lack of operator awareness
of the abnormal condition. In both events, reactor vessel level information
was or could have been made available for prompt identification of the
problem.
Related Generic Communications
System Raw Water Sources," discusses similar solubility
considerations related to air pockets in piping at the McGuire
Nuclear Station.
Coolant," discusses undetected loss of reactor coolant inventory
at North Anna Unit 1 resulting from inadequate use of available
indications and failure to perform mass inventory balances.
- \ >
<_IN 94-36 May 24, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Of ice of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, RII
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
I At,.thment
IN 94-36 May 24, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
91-81, Switchyard Problems that 05/19/94 All holders of OLs or CPs
Supp. 1 Contribute to Loss of for nuclear power reactors.
Offsite Power
94-35 NIOSH Respirator User 05/16/94 All holders of OLs or CPs
Notices, "Inadvertent for nuclear power reactors, Separation of the Mask- and all licensed fuel
Mounted Regulator (MMR) facilities.
from the Facepiece on the
Mine Safety Appliances (MSA)
Company MMR Self-Contained
Breathing Apparatus (SCBA)
and Status Update
94-34 Thermo-Lag 330-660 05/13/94 All holders of OLs or CPs
Flexi-Blanket Ampacity for nuclear power reactors.
Derating Concerns
94-33 Capacitor Failures in 05/09/94 All holders of OLs or CPs
Westinghouse Eagle 21 for nuclear power reactors.
Plant Protection Systems
93-53, Effect of Hurricane 04/29/94 All holders of OLs or CPs
Supp. 1 Andrew on Turkey Point for nuclear power reactors.
Nuclear Generating
Station and Lessons Learned
94-32 Revised Seismic Hazard 04/29/94 All holders of OLs or CPs
Estimates for nuclear power reactors.
94-31 Potential Failure of 04/14/94 All holders of OLs or CPs
Wilco, Lexan-Type HN-4-L for nuclear power reactors.
Fire Hose Nozzles
90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs
Supp. 1 of Reactor Coolant Pump for pressurized water
Bolts reactors.
94-30 Leaking Shutdown Cooling 04/12/94 All holders of OLs or CPs
Isolation Valves at for nuclear power reactors.
Cooper Nuclear Station
OL - Operating License
CP - Construction Permit
IN 94-xx
May xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, R11
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
concurrence
-_. _ .
--- - 1 _._
OFFICE *OEAB:DORS *DRP:RII *OGCB:DORS *SC/DRP:RII *TECH ED
NAME RBenedict SMShaeffer PCWen MLesser MFMejac
lDATE 05/04/L94 05/05/94 05/05/94 05/05/94 05/05/94
[*AC/SRXB:DSSA *AD/DSSA *C/OEAB:DORS *AC/OGCB:DORS D/DORS
TECollins MVirgilio AChaffee AJKugler BKGrimes
05/06/94 05/09/94 05/09/94 05.12/94 / /94 DOCUMENT NAME: SLQGAbIN.KV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been
informed of the development of this information notice and they have
reviewed the draft information notice.
Peter Wen, 5/10/94
IN 94-xx
May xx, 1994 This information notice requires no specific action or written response.
you have any questions about the information in this notice, please contactIf
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, RI!
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
OFFICE *OEAB:DORS *DRP:RII *OGCB:DORS *SC/DRP:RII *TECH ED
NAME RBenedict SMShaeffer PCWen MLesser MFMejac
DATE 05/04/94 05/05/94 05/05/94 05/05/94 05/05/94
- AC/SRXB:DSSA *AD/DSSA *C/OEAB:DORS *AC/OGCB:DORS D/DORS
TECollins 8EXI MVirgilio I AChaffee AJKugler BKGrimes
05/06/94 1 05/09/94 05/09/94 05/12/94 / /94 nnlflMFNT IAMr. eCnveCTitn .* niti
.-- -- I ia11 I EAdIL* .JLA(Un4.1 r A
NOTE: The PMs for Sequoyah (D.LaBarge) and Salem (J.Stone) have been
informed of the development of this information notice and they have
reviewed the draft information notice.
Peter Wen, 5/10/94
IN 94-xx
May xx, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, R11
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
See previous concurrence
OFFICE l *OEAB:DORS *DRP:RII *OGCB:DORS l *SC/DRP:RII *TECH ED
NAME } RBenedict SMShaeffer PCWen MLesser MFMejac
DATE 1 05/04/94 1_05/05/94 1 05/05/94 _ 05/05/94 1 05/05/94
- AC/SRXB:DSSA *AD/DSSA j *C/OEAB:DORS AC/OGCB:DORS D/DORS
TECollins MVirgilio AChaffee AJKugler i(: BKGrimes
05/06/94 = 05/09/94 05/09/94 5/1V94 / /94 DOCUMENT NAME: SEQGASIN.RV1 NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been
informed of the development of this information notice and they have
reviewed the draft information notice.
Peter Wen, 5/10/94
IN 94-xx
May xx, 1994 This information notice requires no specific action or writttten response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, RII
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
OFFICE IOEABDOR5 DRP:RIIpcyJ OGCB__ _ SC/DRP:RI TECH ED
NAME Benedict 'MShaeffer PCWen Lesser
DATE </A/94 5 /5/94 5 / 94/94 5//94 5 / 5/94 AC/SRXB:DSSA , AD/DSSA jC/OEAB:DORS AC/OGCB:DORS D/DORS
TEColli MVirgil ' A2 fe AJKugler BKGrimes
_____94
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IN 94-36 May 24, 1994 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
orig /s/'d by BKGrimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: R. Benedict, NRR
(301) 504-1157 S. M. Shaeffer, R11
(615) 842-8001 Attachment:
List of Recently Issued NRC Information Notices
E
OFFICE
NAME
RBenedict
SMShaeffer
PCWen
MLesser
MFMejac
DATE j05/04/94 05/05/94 05/05/94 05/05/94 05/05/94 l*AC/SRXB:DSSA *AD/DSSA 5*C/OEAB:DORS *AC/OGCB:DO RS*
TECollins MVirgilio AChaffee IvAJKugler _s
05/06/94 05/09/94 i 05/09/94 05/12/4 05//f/94 UuUMtrII NAMt: vq-io. IN
NOTE: The PMs for Sequoyah (D. LaBarge) and Salem (J. Stone) have been
informed of the development of this information notice and they have
reviewed the draft information notice.
Peter Wen, 5/10/94
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed trip)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994)
... further results |
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