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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| WASHINGTON, D.C. 20555 June 16, 1993 NRC INFORMATION
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| NOTICE 93-45: DEGRADATION | | WASHINGTON, D.C. 20555 June 16, 1993 NRC INFORMATION NOTICE 93-45: DEGRADATION OF SHUTDOWN COOLING |
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| ===OF SHUTDOWN COOLING SYSTEM PERFORMANCE===
| | SYSTEM PERFORMANCE |
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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. |
| | |
| 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
| | notice to alert addressees to degradation of shutdown cooling system |
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| notice to alert addressees
| | performance at the Oyster Creek Nuclear Generating Station resulting from |
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| to degradation
| | inadequate operating procedures. It is expected that recipients will review |
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| of shutdown cooling system performance
| | the information for applicability to their facilities and consider actions, as |
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| at the Oyster Creek Nuclear Generating
| | appropriate, to avoid similar problems. However, suggestions contained in |
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| Station resulting
| | this information notice are not NRC requirements; therefore, no specific |
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| from inadequate
| | action or written response is required. |
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| operating
| | ==Description of Circumstances== |
| | On January 23, 1993, the Oyster Creek Nuclear Generating Station was in day 57 of the 14R refueling outage. The plant was in a normal cold-shutdown |
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| procedures.
| | condition with the primary containment open and the reactor coolant system at |
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| It is expected that recipients
| | about 43' C [110* F]. One reactor recirculation loop was in service, one |
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| will review the information
| | recirculation loop was open, and the remaining three recirculation loops were |
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| for applicability
| | either idled or isolated. Two shutdown cooling loops were operating with a |
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| to their facilities
| | combined flow rate of 11,735 liters per minute 13,100 gpm]. |
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| and consider actions, as appropriate, to avoid similar problems.
| | In order to support the planned activities, the licensee elected to secure |
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| However, suggestions
| | operation of all recirculation pumps and lower reactor water level. This |
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| contained
| | configuration would allow completion, in parallel, of recirculation pump |
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| in this information
| | maintenance activities and main steam isolation valve local leak rate testing. |
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| notice are not NRC requirements;
| | When the operators lowered the reactor water level to approximately 419 cm |
| therefore, no specific action or written response is required.Description
| |
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| of Circumstances | | (165 inches] above the top of active fuel and secured the running. |
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| On January 23, 1993, the Oyster Creek Nuclear Generating
| | recirculation pump, the shutdown cooling water took the least resistance path |
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| Station was in day 57 of the 14R refueling
| | through the open recirculation loop, and the majority of flow bypassed the |
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| outage. The plant was in a normal cold-shutdown
| | core (see Attachment 1). During the time that the planned activities were in |
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| condition
| | progress, plant personnel did not realize that shutdown cooling system |
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| with the primary containment
| | performance was degraded, allowing unmonitored heatup of the reactor core. |
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| open and the reactor coolant system at about 43' C [110* F]. One reactor recirculation
| | On January 25, 1993, after completing the main steam isolation valve local |
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| loop was in service, one recirculation
| | leak rate testing, an operations engineer discovered that the reactor vessel |
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| loop was open, and the remaining
| | metal temperature was about 109C 1228F] at the mid-vessel point. Several |
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| three recirculation
| | 9306090036 PDI I.E No*[ct 3-. oj58 |
| | . . P 'v1\ |
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| loops were either idled or isolated.
| | IN 93-45 June 16, 1993 C [212 F] were not |
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| Two shutdown cooling loops were operating
| | Technical Specifications prerequisites for exceeding 100. integrity. |
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| with a combined flow rate of 11,735 liters per minute 13,100 gpm].In order to support the planned activities, the licensee elected to secure operation
| | met, including the requirement to establish primary containment |
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| of all recirculation
| | measures to reduce reactor coolant |
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| pumps and lower reactor water level. This configuration
| | After discovery, operators took immediate two operating |
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| would allow completion, in parallel, of recirculation
| | system water temperature by first maximizing flow in the |
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| pump maintenance
| | cooling loop in |
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| activities
| | shutdown cooling loops and then placing a third shutdown to approximately |
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| and main steam isolation
| | service. Additionally, the reactor water level was raised a recirculation pump was |
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| valve local leak rate testing.When the operators
| | 508 cm [200 inches] above the top of active fuel and |
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| lowered the reactor water level to approximately
| | started. |
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| 419 cm (165 inches] above the top of active fuel and secured the running.recirculation
| | conditions |
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| pump, the shutdown cooling water took the least resistance
| | The immediate cause of the event was determined to be plant cooling operating |
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| path through the open recirculation
| | established by a temporary procedure change to the shutdown |
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| loop, and the majority of flow bypassed the core (see Attachment
| | through the reactor |
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| 1). During the time that the planned activities
| | procedure that failed to provide sufficient forced flow procedure change had |
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| were in progress, plant personnel
| | core to prevent thermal stratification. The temporary |
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| did not realize that shutdown cooling system performance
| | pumps |
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| was degraded, allowing unmonitored
| | been implemented to allow shutdown operations with all recirculationlevel at which |
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| heatup of the reactor core.On January 25, 1993, after completing
| | secured and the nominal reactor water level less than the (approximately 470 cm |
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| the main steam isolation | | spillover from the core region to the annulus is assured |
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| valve local leak rate testing, an operations
| | been developed |
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| engineer discovered
| | [185 inches] above the top of active fuel). The change had a requirement (stated |
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| that the reactor vessel metal temperature
| | from a draft engineering evaluation, but did not includeshutdown cooling flow |
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| was about 109C 1228F] at the mid-vessel
| | in the body of the evaluation) to maintain a specified shutdown cooling |
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| point. Several 9306090036 PDI I.E No*[ct 3-. oj58 P ..'v1\
| | of 22,712 liters per minute [6,000 gpm]. Instead, the usual which, due |
| IN 93-45 June 16, 1993 Technical
| |
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| Specifications
| | flow of about 11,735 liters per minute [3,100 gpm] was maintainedheatup. |
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| prerequisites
| | to the specified configuration, allowed the inadvertent reactor |
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| for exceeding
| | and NRC |
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| 100. C [212 F] were not met, including
| | Further details can be found in Licensee Event Report 50-219/93-002 Augmented Inspection Team Inspection Report No. 50-219/93-80. |
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| the requirement
| | Discussion |
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| to establish
| |
| | |
| primary containment
| |
| | |
| integrity.
| |
| | |
| After discovery, operators
| |
| | |
| took immediate
| |
| | |
| measures to reduce reactor coolant system water temperature
| |
| | |
| by first maximizing
| |
| | |
| flow in the two operating shutdown cooling loops and then placing a third shutdown cooling loop in service. Additionally, the reactor water level was raised to approximately
| |
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| 508 cm [200 inches] above the top of active fuel and a recirculation
| | change |
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| pump was started.The immediate
| | This event at Oyster Creek indicated that the temporary procedure review process did |
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| cause of the event was determined
| | represented a significant procedure revision and that the |
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| to be plant conditions
| | was implemented. The |
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| established
| | not identify deficiencies in the procedure before it engineering |
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| by a temporary
| | temporary procedure change had been developed from a draft in operation would |
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| procedure
| | evaluation which concluded that two shutdown cooling loops |
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| change to the shutdown cooling operating procedure
| | of the |
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| that failed to provide sufficient
| | adequately cool the core. An additional assumption in the body at its |
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| forced flow through the reactor core to prevent thermal stratification.
| | evaluation was that each loop of shutdown cooling would be operating |
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| The temporary
| | gpm], for a total flow |
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| procedure
| | design flow rate of 11,356 liters per minute [3,000 would be |
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| change had been implemented
| | rate of 22,712 liters per minute [6,000 gpm]. This flow rate |
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| to allow shutdown operations
| | at the |
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| with all recirculation
| | adequate to induce spillover from the core region to the annulus that implemented |
| | |
| pumps secured and the nominal reactor water level less than the level at which spillover
| |
| | |
| from the core region to the annulus is assured (approximately | |
| | |
| 470 cm[185 inches] above the top of active fuel). The change had been developed from a draft engineering
| |
| | |
| evaluation, but did not include a requirement (stated in the body of the evaluation)
| |
| to maintain a specified
| |
| | |
| shutdown cooling flow of 22,712 liters per minute [6,000 gpm]. Instead, the usual shutdown cooling flow of about 11,735 liters per minute [3,100 gpm] was maintained
| |
| | |
| which, due to the specified
| |
| | |
| configuration, allowed the inadvertent
| |
| | |
| reactor heatup.Further details can be found in Licensee Event Report 50-219/93-002 and NRC Augmented
| |
| | |
| Inspection
| |
| | |
| Team Inspection
| |
| | |
| Report No. 50-219/93-80.
| |
| | |
| Discussion
| |
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| |
|
| This event at Oyster Creek indicated
| | reduced nominal water level. The temporary procedure change |
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| that the temporary
| | flow rate of 22,712 the engineering evaluation did not require a minimum the |
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| procedure
| | operators following |
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| change represented
| | liters per minute [6,000 gpm]. As a result, the loops in |
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| a significant
| | deficient temporary procedure change placed two shutdown cooling |
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| procedure
| | cooling water to the |
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| revision and that the review process did not identify deficiencies
| | operation, but did not provide sufficient shutdown addition, the |
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| in the procedure
| | reactor core to maintain reactor vessel temperatures. In for monitoring |
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| before it was implemented.
| | temporary procedure change contained no provision or guidance |
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| The temporary
| | heat was being adequately removed |
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| procedure
| | available instruments to ensure that decay |
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| change had been developed
| | from the reactor core. |
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| from a draft engineering
| | the |
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| evaluation
| | As part of the licensee corrective actions, the licensee reviewedchanges and |
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| which concluded
| | effectiveness of its safety review process concerning temporary |
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| that two shutdown cooling loops in operation
| | who |
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| would adequately
| | provided training on the subject of this event to all site personnel |
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| cool the core. An additional
| | perform technical and safety reviews. |
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| |
|
| assumption
| | IN 93-45 June 16, 1993 This information notice requires no specific action or written response. If |
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| |
|
| in the body of the evaluation | | you have any questions about the information in this notice, please contact |
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| |
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| was that each loop of shutdown cooling would be operating
| | one of the technical contacts listed below or the appropriate Offic of |
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| |
|
| at its design flow rate of 11,356 liters per minute [3,000 gpm], for a total flow rate of 22,712 liters per minute [6,000 gpm]. This flow rate would be adequate to induce spillover
| | Nuclear Reactor Regulation (NRR) project manager. |
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| |
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| from the core region to the annulus at the reduced nominal water level. The temporary
| | Brian K. Grimes, Director |
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| procedure
| | Division of Operating Reactor |
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| |
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| change that implemented
| | Support |
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| the engineering
| | Office of Nuclear Reactor Regulation |
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| |
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| evaluation
| | Technical contacts: James S. Stewart, RI |
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| |
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| did not require a minimum flow rate of 22,712 liters per minute [6,000 gpm]. As a result, the operators
| | (215) 337-5240 |
| | Peter C. Wen, NRR |
|
| |
|
| following
| | (301) 504-2832 Attachments: |
| | 1. Figure 1, *Oyster Creek Shutdown Cooling System |
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| |
|
| the deficient
| | Flow With Open Recirculation Loop" |
| | 2. List of Recently Issued NRC Information Notices |
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| |
|
| temporary
| | K. / I'l I |
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| |
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| procedure
| | Attachment 1 |
| | 1iK 93-45 June 16, 1993 Steam Flow *- |
| | 4- Open Recirculation |
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| |
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| change placed two shutdown cooling loops in operation, but did not provide sufficient
| | TORecirculation Loop |
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| shutdown cooling water to the reactor core to maintain reactor vessel temperatures.
| | # ~Loop |
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| In addition, the temporary
| | Shutdown Cooling |
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| procedure
| | System |
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| change contained
| | (3 Cooling Loops) |
| | Figure 1 Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop |
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| no provision
| | I |
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| |
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| or guidance for monitoring
| | Attachment 2 IN 93-45 June 16, 1993 LIST OF RECENTLY ISSUED |
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| |
|
| available
| | NRC INFORMATION NOTICES |
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| |
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| instruments
| | Information Date of |
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| |
|
| to ensure that decay heat was being adequately | | Notice No. Subject Issuance Issued to |
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| |
|
| removed from the reactor core.As part of the licensee corrective
| | 93-44 Operational Challenges 06/15/93 All holders of OLs or CPs |
|
| |
|
| actions, the licensee reviewed the effectiveness
| | During A Dual-Unit for nuclear power reactors. |
|
| |
|
| of its safety review process concerning
| | Transient |
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| |
|
| temporary
| | 93-43 Use of Inappropriate 06/10/93 All holders of OLs or CPs |
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| |
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| changes and provided training on the subject of this event to all site personnel
| | Lubrication Oils in for nuclear power reactors. |
|
| |
|
| who perform technical
| | Safety-Related Applications |
|
| |
|
| and safety reviews.
| | 93-42 Failure of Anti-Rotation 06/09/93 All holders of OLs or CPs |
|
| |
|
| IN 93-45 June 16, 1993 This information
| | Keys in Motor-Operated for nuclear power reactors. |
|
| |
|
| notice requires no specific action or written response.
| | Valves Manufactured by |
|
| |
|
| If you have any questions
| | Velan |
|
| |
|
| about the information
| | 93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs |
|
| |
|
| in this notice, please contact one of the technical
| | Test Results for Thermal for nuclear power reactors. |
|
| |
|
| contacts listed below or the appropriate
| | Ceramics Kaowool, 3M |
|
| |
|
| Offic of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | Company FS-195 and |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | 3M Company Interam E-50 |
| Technical
| | Barrier Systems |
|
| |
|
| contacts:
| | 93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs |
| James S. Stewart, RI (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
| |
| 1. Figure 1, *Oyster Creek Shutdown Cooling System Flow With Open Recirculation
| |
|
| |
|
| Loop" 2. List of Recently Issued NRC Information
| | Results for Thermal for nuclear power reactors. |
|
| |
|
| Notices
| | Ceramics FP-60 Fire |
|
| |
|
| K. /I'l I Steam Flow *-4-TO Recirculation
| | Barrier Material |
|
| |
|
| # ~Loop Shutdown Cooling System (3 Cooling Loops)Figure 1 Attachment
| | ,93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs |
|
| |
|
| 1 1iK 93-45 June 16, 1993 Open Recirculation
| | Power Reactor Biolog- for nuclear power reactors. |
|
| |
|
| Loop Oyster Creek Shutdown Cooling System Flow With Open Recirculation
| | ical Shields |
|
| |
|
| Loop
| | 93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs |
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| |
|
| I Attachment
| | Engineered Safety for nuclear power reactors. |
|
| |
|
| 2 IN 93-45 June 16, 1993 LIST OF RECENTLY ISSUED NRC INFORMATION
| | Features Actuation |
|
| |
|
| NOTICES Information
| | System |
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| |
|
| Date of Notice No. Subject Issuance Issued to 93-44 93-43 93-42 Operational
| | 93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs |
|
| |
|
| Challenges
| | minate Properties In- for nuclear power reactors. |
|
| |
|
| During A Dual-Unit Transient Use of Inappropriate
| | stalled in Limitorque |
|
| |
|
| Lubrication
| | Valve Operator Housing |
|
| |
|
| Oils in Safety-Related
| | Covers |
|
| |
|
| ===Applications===
| | 0L - Operating License |
| Failure of Anti-Rotation
| |
|
| |
|
| Keys in Motor-Operated
| | CP - Construction Permit |
|
| |
|
| Valves Manufactured
| | IN 93-45 June 16, 1993 This information notice requires no specific action or written response. If |
|
| |
|
| by Velan 06/15/93 06/10/93 06/09/93 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.93-41 One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Barrier Systems 05/28/93 All holders for nuclear of OLs or CPs power reactors.93-40 ,93-39 93-38 Fire Endurance
| | you have any questions about the information in this notice, please contact |
|
| |
|
| Test Results for Thermal Ceramics FP-60 Fire Barrier Material Radiation
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| Beams from Power Reactor Biolog-ical Shields Inadequate
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| Testing of Engineered
| | Original !1gnd by |
|
| |
|
| Safety Features Actuation System 05/26/93 05/25/93 05/24/93 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders for nuclear of OLs or CPs power reactors.93-37 Eyebolts with Indeter-minate Properties
| | Brian K. Gdmeg |
|
| |
|
| In-stalled in Limitorque
| | Brian K. Grimes, Director |
|
| |
|
| Valve Operator Housing Covers 05/19/93 All holders of OLs or CPs for nuclear power reactors.0L -Operating
| | Division of Operating Reactor Support |
|
| |
|
| License CP -Construction
| | Office of Nuclear Reactor Regulation |
|
| |
|
| Permit
| | Technical contacts: James S. Stewart, RI |
|
| |
|
| IN 93-45 June 16, 1993 This information
| | (215) 337-5240 |
| | Peter C. Wen, NRR |
|
| |
|
| notice requires no specific action or written response.
| | (301) 504-283], |
| | Attachments: 6 |
| | 1. Figure 1, "Oyster Creek Shutdown Cooling System |
|
| |
|
| If you have any questions
| | Flow With Open Recirculation Loop' |
| | 2. List of Recently Issued NRC Information Notices |
|
| |
|
| about the information
| | *rFF pRmVrnus CONCURRFNCF |
|
| |
|
| in this notice, please contact one of the technical
| | OFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RI |
|
| |
|
| contacts listed below or the appropriate
| | NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Original !1gnd by Brian K. Gdmeg Brian K. Grimes, Director Division of Operating
| | DATE 04/29/93 05/03/93 03/19/93 03/19/A3 .03/19/93 |
| | _______- _ . |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | *Tech Ed. I *C:OGCB:DORS-- *D:DSSA:NRR |
| Technical
| |
|
| |
|
| contacts: James S. Stewart, RI (215) 337-5240 Peter C. Wen, NRR (301) 504-283], Attachments:
| | RSanders IGHMarcus ACThadani |
| 6 1. Figure 1, "Oyster Creek Shutdown Cooling System Flow With Open Recirculation
| |
|
| |
|
| Loop'2. List of Recently Issued NRC Information
| | 04/29/93 05/10 05/24/93 |
| | **SEE MEMO FROM M.. HODGES TO B.K. GRIMES |
|
| |
|
| Notices*rFF pRmVrnus CONCURRFNCF
| | = |
| | . |
|
| |
|
| OFFICE *OGCB:DORS
| | DOCUMENT NAME: 93-45.IN |
|
| |
|
| *DRS:RI **SC:DRS:RI
| | DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT |
|
| |
|
| **BC:DRS:RI
| | Team Leader (J. Beall) were consulted during |
|
| |
|
| **D:DRS:RI
| | the development of this IN. |
|
| |
|
| NAME PCWen/vsb
| | IN 93-XX |
|
| |
|
| JSStewart
| | May xx, 1993 This information notice requires no specific action or written response. If |
|
| |
|
| PKEapen JPDurr MWHodges DATE 04/29/93 05/03/93 03/19/93 03/19/A3 .03/19/93_______- _ .*Tech Ed. I *C:OGCB:DORS--
| | you have any questions about the information in this notice, please contact |
| *D:DSSA:NRR
| |
|
| |
|
| RSanders I GHMarcus ACThadani 04/29/93 05/10 05/24/93.=DOCUMENT NAME: 93-45.IN**SEE MEMO FROM M.. HODGES TO B.K. GRIMES DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT Team Leader (J. Beall) were consulted
| | one of the technical contacts listed below or the appropriate Office of |
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| |
|
| during the development
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| of this IN.
| | Brian K. Grimes, Director |
|
| |
|
| IN 93-XX May xx, 1993 This information
| | Division of Operating Reactor Support |
|
| |
|
| notice requires no specific action or written response.
| | Office of Nuclear Reactor Regulation |
|
| |
|
| If you have any questions
| | Technical contacts: James S. Stewart, Region I |
|
| |
|
| about the information
| | (215) 337-5240 |
| | Peter C. Wen, NRR |
|
| |
|
| in this notice, please contact one of the technical
| | (301) 504-2832 Attachments: |
| | 1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop |
|
| |
|
| contacts listed below or the appropriate
| | 2. List of Recently Issued NRC Information Notices |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | *SEE PREVIOUS CONCURRENCE |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | OFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RI |
| Technical
| |
|
| |
|
| contacts: James S. Stewart, Region I (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
| | NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges |
| 1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation
| |
|
| |
|
| Loop 2. List of Recently Issued NRC Information
| | DATE l04/29/93 l05/03/93 I 03/19/93 l 03/19/93 l03/19/93 |
| | *Tech Ed. *C:OGCB:DORS D:DORS:NRR |
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| Notices*SEE PREVIOUS CONCURRENCE
| | IRSanders GHMarcus BKGrimes |
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| OFFICE *OGCB:DORS
| | 04/29/93 _ 05/10/93 ;05/ /93 4 xk) |
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| *DRS:RI **SC:DRS:RI
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| **BC:DRS:RI | | UULUIMNI NAMI: UIIrMUN .PW) **SEE MEMO FROM M.W. HODGES TO B.K. GRIMES |
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| **D:DRS:RI
| | DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT |
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| NAME PCWen/vsb
| | Team Leader (J. Beall) were consulted during |
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| JSStewart
| | the development of this IN. |
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| PKEapen JPDurr MWHodges DATE l04/29/93 l05/03/93 I 03/19/93 l 03/19/93 l03/19/93*Tech Ed.*C:OGCB:DORS
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| I RSanders GHMarcus 04/29/93 _ 05/10/93 ;onf~~~l ----1F o I~tsPIm BKGrimes UULUIMNI NAMI: UIIrMUN .PW)05/ /93 4 xk)**SEE MEMO FROM M.W. HODGES TO B.K. GRIMES DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT Team Leader (J. Beall) were consulted
| | IN 93-XX |
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| during the development
| | May xx, 1993 This information notice requires no specific action or written response. If |
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| of this IN.530 ACiwAt #f A);mli v-AV'I/tllos
| | you have any questions about the information in this notice, please contact |
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| IN 93-XX May xx, 1993 This information
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| notice requires no specific action or written response.
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| If you have any questions
| | Brian K. Grimes, Director |
|
| |
|
| about the information
| | Division of Operating Reactor Support |
|
| |
|
| in this notice, please contact one of the technical
| | Office of Nuclear Reactor Regulation |
|
| |
|
| contacts listed below or the appropriate | | Technical contacts: James S. Stewart, Region I |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | (215) 337-5240 |
| | Peter C. Wen, NRR |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | (301) 504-2832 Attachments: |
| Technical
| | 1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop |
|
| |
|
| contacts: James S. Stewart, Region I (215) 337-5240 Peter C. Wen, NRR (301) 504-2832 Attachments:
| | 2. List of Recently Issued NRC Information Notices |
| 1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation
| |
|
| |
|
| Loop List of Recently Issued NRC Information
| | *SEE PREVIOUS CONCURRENCE . |
|
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| Notices*SEE PREVIOUS CONCURRENCE
| | OFFICE *OGCB:DORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RI |
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| .OFFICE *OGCB:DORS
| | NAME PCWen/vsb 4SStewart PKEapen JPDurr MWHodges |
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| DRS:RI SC:DRS:RI
| | DATE 04/29/93 05/3,0 Cal P/1/93 0/ l/9 3 I__ 1_/93_J |
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| D:DRS:RI NAME PCWen/vsb
| | Fizz 144 RSanders GHMarcus Ci~l BKGrimes 44 1/1 A/3 |
| | 04/29/93 05/ 1q993 105/ /93 DOUUMENT NAME: OCTPCIN.PW PA (A 'rolnerlk&) , 1 (. Covte). t |
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| 4SStewart
| | AlT Team Leader (J. &3eA.A) LxQe cuAJX4A |
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| PKEapen JPDurr MWHodges DATE 04/29/93 05/3,0 Cal P/1/93 0/ l/9 3 I__ 1_/93_J*Tech Ed.C:OGCB:DORS
| | Alxrzrl t. 4JeLt"e'4 . tk& z4BJ |
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| D:DORS:NRR
| | IN 93-XX |
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| 4xx %E memo Fizz MYS 144 RSanders GHMarcus Ci~l BKGrimes 04/29/93 05/ 1q 9 93 1 05/ /93 44 1/1 A/ 3 DOUUMENT NAME: OCTPCIN.PW
| | May xx, 1993 Page 2 of |
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| PA (A 'rolnerlk&) , 1 (. Covte). t AlT Team Leader (J. &3eA.A) LxQe cuAJX4A Alxrzrl t. 4JeLt"e'4
| | This information notice requires no specific action or written response. If |
| .tk& z4 BJ
| |
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| IN 93-XX May xx, 1993 Page 2 of This information
| | you have any questions about the information in this notice, please contact |
|
| |
|
| notice requires no specific action or written response.
| | one of the technical contacts listed below or the appropriate Office of |
|
| |
|
| If you have any questions
| | Nuclear Reactor Regulation (NRR) project manager. |
|
| |
|
| about the information
| | Brian K. Grimes, Director |
|
| |
|
| in this notice, please contact one of the technical
| | Division of Operating Reactor Support |
|
| |
|
| contacts listed below or the appropriate
| | Office of Nuclear Reactor Regulation |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | Technical contacts: James S. Stewart, Region I |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | (215) 337-5240 |
| Technical
| | Peter C. Wen, NRR |
|
| |
|
| contacts: James S. Stewart, Region I (215) 337-5240 Peter (301)C. Wen, NRR 504-2832 Attachments:
| | (301) 504-2832 Attachments: |
| 1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation | | 1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop |
|
| |
|
| Loop List of Recently Issued NRC Information
| | 2. List of Recently Issued NRC Information Notices |
|
| |
|
| Notices OFFICE OBORS DRS:RI SC:DRS:RI
| | OFFICE OBORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RI |
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|
| BC:DRS:RI
| | NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges |
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| D:DRS:RI NAME PCWen/vsb | | DATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93 Tech Ed. C:OGCB:DORS D: DORS:NRRI |
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| JSStewart
| | flU"AJA& GHMarcus BKGrimes |
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| PKEapen JPDurr MWHodges DATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93 Tech Ed.C:OGCB:DORS
| | ON/.11/93 05/ /93 05/ /93 |
| | %^rrlT scur -rnT -ab |
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| D: DORS:NR RI flU"AJA& GHMarcus BKGrimes ON/.11/93
| | UUUMt Ii NAMt: ULIrMLIN.fW}} |
| 05/ /93 05/ /93%^rrlT scur -rnT -ab UUUMt Ii NAMt: ULIrMLIN.fW}}
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| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Degradation of Shutdown Cooling System PerformanceML031070480 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
06/16/1993 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-93-045, NUDOCS 9306090036 |
Download: ML031070480 (9) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 16, 1993 NRC INFORMATION NOTICE 93-45: DEGRADATION OF SHUTDOWN COOLING
SYSTEM PERFORMANCE
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 degradation of shutdown cooling system
performance at the Oyster Creek Nuclear Generating Station resulting from
inadequate operating procedures. It is expected that recipients will review
the 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
On January 23, 1993, the Oyster Creek Nuclear Generating Station was in day 57 of the 14R refueling outage. The plant was in a normal cold-shutdown
condition with the primary containment open and the reactor coolant system at
about 43' C [110* F]. One reactor recirculation loop was in service, one
recirculation loop was open, and the remaining three recirculation loops were
either idled or isolated. Two shutdown cooling loops were operating with a
combined flow rate of 11,735 liters per minute 13,100 gpm].
In order to support the planned activities, the licensee elected to secure
operation of all recirculation pumps and lower reactor water level. This
configuration would allow completion, in parallel, of recirculation pump
maintenance activities and main steam isolation valve local leak rate testing.
When the operators lowered the reactor water level to approximately 419 cm
(165 inches] above the top of active fuel and secured the running.
recirculation pump, the shutdown cooling water took the least resistance path
through the open recirculation loop, and the majority of flow bypassed the
core (see Attachment 1). During the time that the planned activities were in
progress, plant personnel did not realize that shutdown cooling system
performance was degraded, allowing unmonitored heatup of the reactor core.
On January 25, 1993, after completing the main steam isolation valve local
leak rate testing, an operations engineer discovered that the reactor vessel
metal temperature was about 109C 1228F] at the mid-vessel point. Several
9306090036 PDI I.E No*[ct 3-. oj58
. . P 'v1\
IN 93-45 June 16, 1993 C [212 F] were not
Technical Specifications prerequisites for exceeding 100. integrity.
met, including the requirement to establish primary containment
measures to reduce reactor coolant
After discovery, operators took immediate two operating
system water temperature by first maximizing flow in the
cooling loop in
shutdown cooling loops and then placing a third shutdown to approximately
service. Additionally, the reactor water level was raised a recirculation pump was
508 cm [200 inches] above the top of active fuel and
started.
conditions
The immediate cause of the event was determined to be plant cooling operating
established by a temporary procedure change to the shutdown
through the reactor
procedure that failed to provide sufficient forced flow procedure change had
core to prevent thermal stratification. The temporary
pumps
been implemented to allow shutdown operations with all recirculationlevel at which
secured and the nominal reactor water level less than the (approximately 470 cm
spillover from the core region to the annulus is assured
been developed
[185 inches] above the top of active fuel). The change had a requirement (stated
from a draft engineering evaluation, but did not includeshutdown cooling flow
in the body of the evaluation) to maintain a specified shutdown cooling
of 22,712 liters per minute [6,000 gpm]. Instead, the usual which, due
flow of about 11,735 liters per minute [3,100 gpm] was maintainedheatup.
to the specified configuration, allowed the inadvertent reactor
and NRC
Further details can be found in Licensee Event Report 50-219/93-002 Augmented Inspection Team Inspection Report No. 50-219/93-80.
Discussion
change
This event at Oyster Creek indicated that the temporary procedure review process did
represented a significant procedure revision and that the
was implemented. The
not identify deficiencies in the procedure before it engineering
temporary procedure change had been developed from a draft in operation would
evaluation which concluded that two shutdown cooling loops
of the
adequately cool the core. An additional assumption in the body at its
evaluation was that each loop of shutdown cooling would be operating
gpm], for a total flow
design flow rate of 11,356 liters per minute [3,000 would be
rate of 22,712 liters per minute [6,000 gpm]. This flow rate
at the
adequate to induce spillover from the core region to the annulus that implemented
reduced nominal water level. The temporary procedure change
flow rate of 22,712 the engineering evaluation did not require a minimum the
operators following
liters per minute [6,000 gpm]. As a result, the loops in
deficient temporary procedure change placed two shutdown cooling
cooling water to the
operation, but did not provide sufficient shutdown addition, the
reactor core to maintain reactor vessel temperatures. In for monitoring
temporary procedure change contained no provision or guidance
heat was being adequately removed
available instruments to ensure that decay
from the reactor core.
the
As part of the licensee corrective actions, the licensee reviewedchanges and
effectiveness of its safety review process concerning temporary
who
provided training on the subject of this event to all site personnel
perform technical and safety reviews.
IN 93-45 June 16, 1993 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 Offic of
Nuclear Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor
Support
Office of Nuclear Reactor Regulation
Technical contacts: James S. Stewart, RI
(215) 337-5240
Peter C. Wen, NRR
(301) 504-2832 Attachments:
1. Figure 1, *Oyster Creek Shutdown Cooling System
Flow With Open Recirculation Loop"
2. List of Recently Issued NRC Information Notices
K. / I'l I
Attachment 1
1iK 93-45 June 16, 1993 Steam Flow *-
4- Open Recirculation
TORecirculation Loop
- ~Loop
Shutdown Cooling
System
(3 Cooling Loops)
Figure 1 Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop
I
Attachment 2 IN 93-45 June 16, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-44 Operational Challenges 06/15/93 All holders of OLs or CPs
During A Dual-Unit for nuclear power reactors.
Transient
93-43 Use of Inappropriate 06/10/93 All holders of OLs or CPs
Lubrication Oils in for nuclear power reactors.
Safety-Related Applications
93-42 Failure of Anti-Rotation 06/09/93 All holders of OLs or CPs
Keys in Motor-Operated for nuclear power reactors.
Valves Manufactured by
Velan
93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs
Test Results for Thermal for nuclear power reactors.
Ceramics Kaowool, 3M
Company FS-195 and
3M Company Interam E-50
Barrier Systems
93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs
Results for Thermal for nuclear power reactors.
Ceramics FP-60 Fire
Barrier Material
,93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs
Power Reactor Biolog- for nuclear power reactors.
ical Shields
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs
Engineered Safety for nuclear power reactors.
Features Actuation
System
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
minate Properties In- for nuclear power reactors.
stalled in Limitorque
Valve Operator Housing
Covers
0L - Operating License
CP - Construction Permit
IN 93-45 June 16, 1993 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.
Original !1gnd by
Brian K. Gdmeg
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: James S. Stewart, RI
(215) 337-5240
Peter C. Wen, NRR
(301) 504-283],
Attachments: 6
1. Figure 1, "Oyster Creek Shutdown Cooling System
Flow With Open Recirculation Loop'
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RI
NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges
DATE 04/29/93 05/03/93 03/19/93 03/19/A3 .03/19/93
_______- _ .
- Tech Ed. I *C:OGCB:DORS-- *D:DSSA:NRR
RSanders IGHMarcus ACThadani
04/29/93 05/10 05/24/93
- SEE MEMO FROM M.. HODGES TO B.K. GRIMES
=
.
DOCUMENT NAME: 93-45.IN
DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT
Team Leader (J. Beall) were consulted during
the development of this IN.
IN 93-XX
May xx, 1993 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: James S. Stewart, Region I
(215) 337-5240
Peter C. Wen, NRR
(301) 504-2832 Attachments:
1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop
2. List of Recently Issued NRC Information Notices
OFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RI
NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges
DATE l04/29/93 l05/03/93 I 03/19/93 l 03/19/93 l03/19/93
- Tech Ed. *C:OGCB:DORS D:DORS:NRR
IRSanders GHMarcus BKGrimes
04/29/93 _ 05/10/93 ;05/ /93 4 xk)
onf~~~l oI~tsPIm
- - - - 1F
UULUIMNI NAMI: UIIrMUN .PW) **SEE MEMO FROM M.W. HODGES TO B.K. GRIMES
DATED 3/19/93 PM (A. Dromerick), EAB (J. Carter) and AIT
Team Leader (J. Beall) were consulted during
the development of this IN.
530
AV 'I/tllos
ACiwAt #
fA);mli v-
IN 93-XX
May xx, 1993 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: James S. Stewart, Region I
(215) 337-5240
Peter C. Wen, NRR
(301) 504-2832 Attachments:
1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop
2. List of Recently Issued NRC Information Notices
- SEE PREVIOUS CONCURRENCE .
OFFICE *OGCB:DORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RI
NAME PCWen/vsb 4SStewart PKEapen JPDurr MWHodges
DATE 04/29/93 05/3,0 Cal P/1/93 0/ l/9 3 I__ 1_/93_J
- Tech Ed. C:OGCB:DORS D:DORS:NRR 4xx %E memo MYS
Fizz 144 RSanders GHMarcus Ci~l BKGrimes 44 1/1 A/3
04/29/93 05/ 1q993 105/ /93 DOUUMENT NAME: OCTPCIN.PW PA (A 'rolnerlk&) , 1 (. Covte). t
AlT Team Leader (J. &3eA.A) LxQe cuAJX4A
Alxrzrl t. 4JeLt"e'4 . tk& z4BJ
IN 93-XX
May xx, 1993 Page 2 of
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: James S. Stewart, Region I
(215) 337-5240
Peter C. Wen, NRR
(301) 504-2832 Attachments:
1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop
2. List of Recently Issued NRC Information Notices
OFFICE OBORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RI
NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges
DATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93 Tech Ed. C:OGCB:DORS D: DORS:NRRI
flU"AJA& GHMarcus BKGrimes
ON/.11/93 05/ /93 05/ /93
%^rrlT scur -rnT -ab
UUUMt Ii NAMt: ULIrMLIN.fW
|
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|
list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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