|
|
(3 intermediate revisions by the same user not shown) |
Line 3: |
Line 3: |
| | issue date = 06/16/1993 | | | issue date = 06/16/1993 |
| | title = Degradation of Shutdown Cooling System Performance | | | title = Degradation of Shutdown Cooling System Performance |
| | author name = Grimes B K | | | author name = Grimes B |
| | author affiliation = NRC/NRR | | | author affiliation = NRC/NRR |
| | addressee name = | | | addressee name = |
Line 14: |
Line 14: |
| | page count = 9 | | | page count = 9 |
| }} | | }} |
| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555June 16, 1993NRC INFORMATION NOTICE 93-45: DEGRADATION OF SHUTDOWN COOLINGSYSTEM PERFORMANCE | | {{#Wiki_filter: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== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear powerreactors. | | All holders of operating licenses or construction permits for nuclear power |
| | |
| | reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to alert addressees to degradation of shutdown cooling systemperformance at the Oyster Creek Nuclear Generating Station resulting frominadequate operating procedures. It is expected that recipients will reviewthe information for applicability to their facilities and consider actions, asappropriate, to avoid similar problems. However, suggestions contained inthis information notice are not NRC requirements; therefore, no specificaction or written response is required. | | 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== | | ==Description of Circumstances== |
| On January 23, 1993, the Oyster Creek Nuclear Generating Station was in day 57of the 14R refueling outage. The plant was in a normal cold-shutdowncondition with the primary containment open and the reactor coolant system atabout 43' C [110* F]. One reactor recirculation loop was in service, onerecirculation loop was open, and the remaining three recirculation loops wereeither idled or isolated. Two shutdown cooling loops were operating with acombined flow rate of 11,735 liters per minute 13,100 gpm].In order to support the planned activities, the licensee elected to secureoperation of all recirculation pumps and lower reactor water level. Thisconfiguration would allow completion, in parallel, of recirculation pumpmaintenance 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 paththrough the open recirculation loop, and the majority of flow bypassed thecore (see Attachment 1). During the time that the planned activities were inprogress, plant personnel did not realize that shutdown cooling systemperformance was degraded, allowing unmonitored heatup of the reactor core.On January 25, 1993, after completing the main steam isolation valve localleak rate testing, an operations engineer discovered that the reactor vesselmetal temperature was about 109C 1228F] at the mid-vessel point. Several9306090036 PDI I.E No*[ct 3-. oj58P ..'v1\ | | 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 |
| IN 93-45June 16, 1993 Technical Specifications prerequisites for exceeding 100. C [212 F] were notmet, including the requirement to establish primary containment integrity.After discovery, operators took immediate measures to reduce reactor coolantsystem water temperature by first maximizing flow in the two operatingshutdown cooling loops and then placing a third shutdown cooling loop inservice. Additionally, the reactor water level was raised to approximately508 cm [200 inches] above the top of active fuel and a recirculation pump wasstarted.The immediate cause of the event was determined to be plant conditionsestablished by a temporary procedure change to the shutdown cooling operatingprocedure that failed to provide sufficient forced flow through the reactorcore to prevent thermal stratification. The temporary procedure change hadbeen implemented to allow shutdown operations with all recirculation pumpssecured and the nominal reactor water level less than the level at whichspillover from the core region to the annulus is assured (approximately 470 cm[185 inches] above the top of active fuel). The change had been developedfrom a draft engineering evaluation, but did not include a requirement (statedin the body of the evaluation) to maintain a specified shutdown cooling flowof 22,712 liters per minute [6,000 gpm]. Instead, the usual shutdown coolingflow of about 11,735 liters per minute [3,100 gpm] was maintained which, dueto the specified configuration, allowed the inadvertent reactor heatup.Further details can be found in Licensee Event Report 50-219/93-002 and NRCAugmented Inspection Team Inspection Report No. 50-219/93-80.DiscussionThis event at Oyster Creek indicated that the temporary procedure changerepresented a significant procedure revision and that the review process didnot identify deficiencies in the procedure before it was implemented. Thetemporary procedure change had been developed from a draft engineeringevaluation which concluded that two shutdown cooling loops in operation wouldadequately cool the core. An additional assumption in the body of theevaluation was that each loop of shutdown cooling would be operating at itsdesign flow rate of 11,356 liters per minute [3,000 gpm], for a total flowrate of 22,712 liters per minute [6,000 gpm]. This flow rate would beadequate to induce spillover from the core region to the annulus at thereduced nominal water level. The temporary procedure change that implementedthe engineering evaluation did not require a minimum flow rate of 22,712liters per minute [6,000 gpm]. As a result, the operators following thedeficient temporary procedure change placed two shutdown cooling loops inoperation, but did not provide sufficient shutdown cooling water to thereactor core to maintain reactor vessel temperatures. In addition, thetemporary procedure change contained no provision or guidance for monitoringavailable instruments to ensure that decay heat was being adequately removedfrom the reactor core.As part of the licensee corrective actions, the licensee reviewed theeffectiveness of its safety review process concerning temporary changes andprovided training on the subject of this event to all site personnel whoperform technical and safety review IN 93-45June 16, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Offic ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating ReactorSupportOffice of Nuclear Reactor RegulationTechnical contacts: James S. Stewart, RI(215) 337-5240Peter C. Wen, NRR(301) 504-2832 | | |
| | 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 |
| | |
| | *rFF pRmVrnus CONCURRFNCF |
| | |
| | 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 |
| | |
| | *SEE PREVIOUS CONCURRENCE |
| | |
| | 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 |
|
| |
|
| ===Attachments:===
| | NAME PCWen/vsb JSStewart PKEapen JPDurr MWHodges |
| 1. Figure 1, *Oyster Creek Shutdown Cooling SystemFlow With Open Recirculation Loop"2. List of Recently Issued NRC Information Notices K. /I'l ISteam Flow *-4-TO Recirculation# ~LoopShutdown CoolingSystem(3 Cooling Loops)Figure 1Attachment 11iK 93-45June 16, 1993 Open RecirculationLoopOyster Creek Shutdown Cooling System Flow With Open Recirculation Loop IAttachment 2IN 93-45June 16, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-4493-4393-42Operational ChallengesDuring A Dual-UnitTransientUse of InappropriateLubrication Oils inSafety-Related ApplicationsFailure of Anti-RotationKeys in Motor-OperatedValves Manufactured byVelan06/15/9306/10/9306/09/93All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.93-41One Hour Fire EnduranceTest Results for ThermalCeramics Kaowool, 3MCompany FS-195 and3M Company Interam E-50Barrier Systems05/28/93All holdersfor nuclearof OLs or CPspower reactors.93-40,93-3993-38Fire Endurance TestResults for ThermalCeramics FP-60 FireBarrier MaterialRadiation Beams fromPower Reactor Biolog-ical ShieldsInadequate Testing ofEngineered SafetyFeatures ActuationSystem05/26/9305/25/9305/24/93All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor nuclear power reactors.All holdersfor nuclearof OLs or CPspower reactors.93-37Eyebolts with Indeter-minate Properties In-stalled in LimitorqueValve Operator HousingCovers05/19/93All holders of OLs or CPsfor nuclear power reactors.0L -Operating LicenseCP -Construction Permit IN 93-45June 16, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Original !1gnd byBrian K. GdmegBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:James S. Stewart, RI(215) 337-5240Peter C. Wen, NRR(301) 504-283],
| |
|
| |
|
| ===Attachments:===
| | DATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93 Tech Ed. C:OGCB:DORS D: DORS:NRRI |
| 61. Figure 1, "Oyster Creek Shutdown Cooling SystemFlow With Open Recirculation Loop'2. List of Recently Issued NRC Information Notices*rFF pRmVrnus CONCURRFNCFOFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RINAME PCWen/vsb JSStewart PKEapen JPDurr MWHodgesDATE 04/29/93 05/03/93 03/19/93 03/19/A3 .03/19/93_______- _ .*Tech Ed. I *C:OGCB:DORS--*D:DSSA:NRRRSanders I GHMarcus ACThadani04/29/93 05/10 05/24/93.=DOCUMENT NAME: 93-45.IN**SEE MEMO FROM M.. HODGES TO B.K. GRIMESDATED 3/19/93PM (A. Dromerick), EAB (J. Carter) and AITTeam Leader (J. Beall) were consulted duringthe development of this I IN 93-XXMay xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:James S. Stewart, Region I(215) 337-5240Peter C. Wen, NRR(301) 504-2832
| |
|
| |
|
| ===Attachments:===
| | flU"AJA& GHMarcus BKGrimes |
| 1. Oyster Creek Shutdown Cooling System Flow With Open Recirculation Loop2. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OGCB:DORS *DRS:RI **SC:DRS:RI **BC:DRS:RI **D:DRS:RINAME PCWen/vsb JSStewart PKEapen JPDurr MWHodgesDATE l04/29/93 l05/03/93 I 03/19/93 l 03/19/93 l03/19/93*Tech Ed.*C:OGCB:DORSD:DORS:NRRI RSanders GHMarcus04/29/93 _ 05/10/93 ;onf~~~l ----1F o I~tsPImBKGrimesUULUIMNI NAMI: UIIrMUN .PW)05/ /93 4xk)**SEE MEMO FROM M.W. HODGES TO B.K. GRIMESDATED 3/19/93PM (A. Dromerick), EAB (J. Carter) and AITTeam Leader (J. Beall) were consulted duringthe development of this IN.530ACiwAt #f A);mli v-AV'I/tllos IN 93-XXMay xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:James S. Stewart, Region I(215) 337-5240Peter C. Wen, NRR(301) 504-2832
| |
|
| |
|
| ===Attachments:===
| | ON/.11/93 05/ /93 05/ /93 |
| 1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation LoopList of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE .OFFICE *OGCB:DORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RINAME PCWen/vsb 4SStewart PKEapen JPDurr MWHodgesDATE 04/29/93 05/3,0 Cal P/1/93 0/ l/93I__ 1_/93_J*Tech Ed.C:OGCB:DORSD:DORS:NRR4xx %E memoFizz MYS 144RSanders GHMarcus Ci~l BKGrimes04/29/93 05/ 1q993 1 05/ /9344 1/1 A/ 3DOUUMENT NAME: OCTPCIN.PWPA (A 'rolnerlk&) , 1 (. Covte). tAlT Team Leader (J. &3eA.A) LxQe cuAJX4AAlxrzrl t. 4JeLt"e'4 .tk& z4 BJ IN 93-XXMay xx, 1993Page 2 ofThis information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactone of the technical contacts listed below or the appropriate Office ofNuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:James S. Stewart, Region I(215) 337-5240Peter(301)C. Wen, NRR504-2832
| | %^rrlT scur -rnT -ab |
|
| |
|
| ===Attachments:===
| | UUUMt Ii NAMt: ULIrMLIN.fW}} |
| 1.2.Oyster Creek Shutdown Cooling System Flow With Open Recirculation LoopList of Recently Issued NRC Information NoticesOFFICE OBORS DRS:RI SC:DRS:RI BC:DRS:RI D:DRS:RINAME PCWen/vsb JSStewart PKEapen JPDurr MWHodgesDATE _/aq/93_ 05/ /93 05/ /93 05/ /93 105/ /93Tech Ed.C:OGCB:DORSD: DORS:NR RIflU"AJA& GHMarcus BKGrimesON/.11/93 05/ /93 05/ /93%^rrlT scur -rnT -abUUUMt Ii NAMt: ULIrMLIN.fW}}
| |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Degradation of Shutdown Cooling System PerformanceML031070480 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
---|
Issue date: |
06/16/1993 |
---|
From: |
Grimes B Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
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 |
---|
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
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
|
---|
|
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 |
---|