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| {{#Wiki_filter:U -AUUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555August 16, 1993NRC INFORMATION NOTICE 93-67: BURSTING OF HIGH PRESSURE COOLANT INJECTIONSTEAM LINE RUPTURE DISCS INJURES PLANTPERSONNEL | | {{#Wiki_filter:U -AUUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555August 16, 1993NRC INFORMATION NOTICE 93-67: BURSTING OF HIGH PRESSURE COOLANT INJECTIONSTEAM LINE RUPTURE DISCS INJURES PLANTPERSONNEL |
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| 1. Figure 1, "Simplified Layout of Quad CitiesStation HPCI Turbine Exhaust Steam Line"2. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE.OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE 07/08/93 , 07/08/93 07/14/93 07/14/93OFC *C:DRS:R-III *SC:OEAB:DORS *C/OEAB/DORS *C:SPLB:DSSANAME GWright I RDennig AEChaffee CEMcCrackenDATE [ 07/14/93 1 07/15/93 07/15/93 ]07/16/93I__ _ iOFC*D:DSSA*C/OGCB:DORSD/DORS A^rNAME AThadani GMarcus BGrimes tDATE 07/24/93 07/29/93 0,S/\o/93 V[OFFICIAL RECORD COPY]DOCUMENT NAME: 93-67.IN | | 1. Figure 1, "Simplified Layout of Quad CitiesStation HPCI Turbine Exhaust Steam Line"2. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE.OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE 07/08/93 , 07/08/93 07/14/93 07/14/93OFC *C:DRS:R-III *SC:OEAB:DORS *C/OEAB/DORS *C:SPLB:DSSANAME GWright I RDennig AEChaffee CEMcCrackenDATE [ 07/14/93 1 07/15/93 07/15/93 ]07/16/93I__ _ iOFC*D:DSSA*C/OGCB:DORSD/DORS A^rNAME AThadani GMarcus BGrimes tDATE 07/24/93 07/29/93 0,S/\o/93 V[OFFICIAL RECORD COPY]DOCUMENT NAME: 93-67.IN |
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| \-IN 93-XXJuly XX, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Clark Vanderniet, RIII(708) 790-5594David(301)Skeen, NRR504-1174 | | \-IN 93-XXJuly XX, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Clark Vanderniet, RIII(708) 790-5594David(301)Skeen, NRR504-1174 |
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| ===Attachment:=== | | ===Attachment:=== |
| List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE07/08/9307/08/9307 114/9307/14/93L, _, I_,__ _ .., __ ...I_ I -*C:DRS:RIII S ODORS EAB:DORS C:SPLB:DSSA D:DSSAGWright R enn afaf' afee CEMcCracken ACThadani07/14/93 [ 3 07/j</93 07/ /93 07/ /93C:OGCB:DORSD:DORSGHMarcus BKGrimes07/ /93 07/ /930DOCUMENT NAME: QCHPCIIN.WEN | | List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE07/08/9307/08/9307 114/9307/14/93L, _, I_,__ _ .., __ ...I_ I -*C:DRS:RIII S ODORS EAB:DORS C:SPLB:DSSA D:DSSAGWright R enn afaf' afee CEMcCracken ACThadani07/14/93 [ 3 07/j</93 07/ /93 07/ /93C:OGCB:DORSD:DORSGHMarcus BKGrimes07/ /93 07/ /930DOCUMENT NAME: QCHPCIIN.WEN |
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| -E7/14/9312:53 ?03 787905538417463837P. 0',This infiyou havethe techRoactorIN 93-XXJuly xx. 1993 Irmation notice requires no specific action or written response. Itany questions about the information in this noticet please contactlcal contmct listed below or the appropriate Office of Nuclearr.gulmtion (NRR) project manager.Brian K. Grimes, DirectorDivision of sOrating RGOM SupportOffice of Nuclear Reactor RegulationTechnic~l contactsClark Vanderniet, R-II1(708) 790-5594Oavid Skeen NRR(301) 604-1174Attach4nt: List of Recently Issued NRC Information Notices/._ _ *,,1'SEL PR -.IUUb 6UNCUUMM6C,OFFIC D _ *TECH:,ED -I _ I RNAME _ JGnMain PI_. .,I -- '^A j"IR na jai4I 7/1k01.%0J//Y//93I1UATI I uJ 1 b I W ._ II nF&-flIA I C:PBDS :ISS I ----.n J T TVcr P. rAn | | -E7/14/9312:53 ?03 787905538417463837P. 0',This infiyou havethe techRoactorIN 93-XXJuly xx. 1993 Irmation notice requires no specific action or written response. Itany questions about the information in this noticet please contactlcal contmct listed below or the appropriate Office of Nuclearr.gulmtion (NRR) project manager.Brian K. Grimes, DirectorDivision of sOrating RGOM SupportOffice of Nuclear Reactor RegulationTechnic~l contactsClark Vanderniet, R-II1(708) 790-5594Oavid Skeen NRR(301) 604-1174Attach4nt: List of Recently Issued NRC Information Notices/._ _ *,,1'SEL PR -.IUUb 6UNCUUMM6C,OFFIC D _ *TECH:,ED -I _ I RNAME _ JGnMain PI_. .,I -- '^A j"IR na jai4I 7/1k01.%0J//Y//93I1UATI I uJ 1 b I W ._ II nF&-flIA I C:PBDS :ISS I ----.n J T TVcr P. rAn |
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| * Motwrn r nAs WDgRI C.SPLB*DSSAD :DSSA_ICh ouf I 1NNI I I I;rn n I= -- 1 --.-. -T II 1Atn"^"4^"I ji 1%V, famrEIaCrackenACThadani _1OI-lqn 0, 7/ R/9M3..~07~11 9 93 07/ /93 -- 107/ /193 -IQl l 193 107/ /93--:_ _r _r.nnr 'f lRSD:DORSus BK rimes-.. ..- _ L4Y.IIuL)OCUME NA ML: QUMrLun.w~J'14 JUL 93 B: 5uLETd lN11 211HM DUN411 b0S T ,z ES:90 t 5os->X-L0LM1 b0S IQ£ J\1IN 93-XXJuly xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Clark(708)Vanderniet, R-III790-5594David Skeen, NRR(301) 504-1174 | | * Motwrn r nAs WDgRI C.SPLB*DSSAD :DSSA_ICh ouf I 1NNI I I I;rn n I= -- 1 --.-. -T II 1Atn"^"4^"I ji 1%V, famrEIaCrackenACThadani _1OI-lqn 0, 7/ R/9M3..~07~11 9 93 07/ /93 -- 107/ /193 -IQl l 193 107/ /93--:_ _r _r.nnr 'f lRSD:DORSus BK rimes-.. ..- _ L4Y.IIuL)OCUME NA ML: QUMrLun.w~J'14 JUL 93 B: 5uLETd lN11 211HM DUN411 b0S T ,z ES:90 t 5os->X-L0LM1 b0S IQ£ J\1IN 93-XXJuly xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Clark(708)Vanderniet, R-III790-5594David Skeen, NRR(301) 504-1174 |
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Bursting of High Pressure Coolant Injection Steam Line Rupture Discs Injures Plant PersonnelML031070135 |
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, 05000349, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/16/1993 |
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From: |
Grimes B K Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-93-067, NUDOCS 9308100248 |
Download: ML031070135 (14) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000349, 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 [[:05000349]] 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 [[:05000349]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
U -AUUNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATIONWASHINGTON, D.C. 20555August 16, 1993NRC INFORMATION NOTICE 93-67: BURSTING OF HIGH PRESSURE COOLANT INJECTIONSTEAM LINE RUPTURE DISCS INJURES PLANTPERSONNEL
Addressees
All holders of operating licenses or construction permits for nuclear powerreactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this informationnotice to remind addressees of the hazards associated with steam drivencoolant injection systems such as the high pressure coolant injection (HPCI)system and the reactor core isolation cooling (RCIC) system at BWRs and theauxiliary feedwater system at PWRs. It is expected that recipients willreview the information for applicability to their facilities and consideractions, as appropriate, to avoid similar problems. However, suggestions Xcontained in this information notice are not NRC requirements; therefore, nospecific action or written response is required.BackgroundThe purpose of HPCI steam exhaust rupture discs is to protect the HPCI turbinecasing and associated exhaust piping from an overpressure event if the normalexhaust path to the suppression pool becomes blocked. At Quad Cities Station,two 40.6-cm [16-inch] stainless steel discs are installed in series with a6.4-cm [2.5-inch] spacer between them to allow for a pressure sensorinstrumentation line. The pressure sensor, while serving no control function,actuates an alarm in the control room at 68.9 kPa [10 psig] to alert theoperators that the inner disc is leaking. The normal range of the HPCIexhaust steam pressure is 172 to 207 kPa [25 to 30 psig].- The HPCI highexhaust pressure turbine trip setpoint is 689 kPa [100 psig] and is sensed bypressure sensors located downstream from where the section of pipingcontaining the rupture discs branches off from the exhaust piping. Thesection of piping containing the rupture discs is mounted vertically over theturbine exhaust and vents directly to the HPCI room. Pressure greater than1034 kPa [150 psig] in the exhaust line will cause the inner disc to ruptureand impact the outer disc, releasing steam into the HPCI room.
Description of Circumstances
During a quarterly inservice test of the HPCI pump at the Commonwealth EdisonQuad Cities Station, Unit 1, on June 9, 1993, the exhaust steam line rupture9308100248F QrRi IN 93-67August 16, 1993 discs burst, releasing steam into the HPCI room, burning, and slightlycontaminating, five workers. The rupture discs burst within one second afterthe turbine was started. Fire doors between the Unit 1 and Unit 2 HPCI roomswere blown off their hinges into the Unit 2 HPCI room. Both sets of doubledoors that are part of the secondary containment boundary were also blownopen. The floor latch on the inner containment door was bent; the outer doorswere also slightly damaged, but were repaired, closed and sealed approximately35 minutes after the event. The steam release was terminated by automaticisolation of the steam supply line on high HPCI turbine area temperature about20 seconds into the event.DiscussionUpon investigating the event, the licensee determined that water hadaccumulated in the turbine casing because the drain system level switches forthe Unit 1 HPCI system had failed. In April 1992, the licensee performed areliability-centered maintenance study which recommended the level switches beincluded in the preventive maintenance program but the recommendation had notbeen acted on at the time of the event. The Unit 2 HPCI drain system levelswitches were also found to be inoperable.The slug of water created during the HPCI turbine roll passed from the turbinecasing to the vertical exhaust line and compressed the air in the 40.6 cm[16 inch] line containing the rupture discs. The resulting pressure pulsecaused the inner rupture disc to burst, which impacted the outer disc asdesigned and caused it to burst as well. The exhaust line pressure sensors,located in the horizontal 61 cm [24 inch] exhaust line that tees off from thevertical 40.6 cm [16 inch] rupture disc line, did not detect a high pressure(see Figure 1). The pressure switches were within tolerance and should haveimmediately isolated the steam supply upon sensing a high exhaust pressurebefore the rupture discs burst. The fact that a high exhaust line pressurewas not detected indicates two possible causes for the disc rupture. Eitherthe inner rupture disc was degraded and burst at lower-than-design pressure,or the pressure pulse actually exceeded the design pressure and caused thedisc to burst, relieving the exhaust line pressure before the downstreampressure sensors detected a high pressure condition.While inspection of the rupture discs did not reveal any degradation fromcorrosion or aging, the vendor, Black Sivalls & Bryson, Inc, stated that thediscs are warranted for one year of service under normal conditions. The HPCIand RCIC rupture discs at Quad Cities Station had been in service for 20 yearsand were not part of any scheduled inspection or preventive maintenanceprogram. When consulted about the event, the vendor advised against using thespare discs in the plant storeroom because they were purchased at the sametime as the failed discs. The licensee later replaced the failed discs withnew units. Before this event, the licensee recently replaced a HPCI rupturedisc during a refueling outage at the Dresden Station, a plant similar to QuadCities, after finding a crack in the disc during an inspection. The rupturediscs were inspected at the Dresden station as part of an enhancement to thepreventive maintenance program that was recommended by a reliability-centeredanalysi I IIN 93-67August 16, 1993 The steam injured five workers, four of whom were participating in the HPCIpump surveillance test. The fifth, and m6st severely. injured worker was ahealth physics technician in the room on routine rounds, who was not aware ofthe danger posed by the surveillance test. The test procedure contained nospecific guidance on room occupancy. Interviews with the workers revealedthat they had performed the surveillance in the past and were familiar withthe process. This familiarity may have led to a relaxed attitude towardpersonal safety. The workers stated that during previous surveillances theysometimes evacuated the room before rolling the turbine, or stood near thedoors to be ready to escape. The licensee made no routine announcement overthe plant paging system to alert plant personnel before the HPCI-turbinestart, and the workers were not prepared for the turbine to start.A lack of constant communication between the workersand the control room mayhave contributed to the personnel injuries. If a control room operator hadbeen in contact with the workers in the HPCI room during the turbine roll, theworkers would have been aware of the impending turbine start and, after start,the steam supply might have been manually-isolated or the turbine manuallytripped before the automatic isolation caused by the high area temperatureointhe HPCI room.When the Unit 1 HPCI rupture disc failure caused the fire doors to be blownoff their hinges and into the Unit 2 HPCI room, one of the doors impacted apipe hanger in the room and moved it 5.1 centimeters [2 inches]. If the steamrelease had resulted from a high energy line break from the inlet side of theHPCI steam line instead of the exhaust line, the damage to the Unit 2 HPCIsystem could have been more severe. While high energy line breaks have beenanalyzed for safety systems at all plants, the doors to rooms containing highenergy steam lines may not have been included in the analysis. For example,at Duane Arnold Energy Center, the licensee discovered that while the HPCI andRCIC rooms were qualified for pressures of 26.2 kPa [3.8 psig], the doorsbetween these rooms and the reactor building would yield at 6.9 kPa [1 psig].The licensee for the Quad Cities Station will implement a preventivemaintenance schedule for both the HPCI and RCIC rupture discs and the levelswitches. The licensee will review the surveillance test procedure andevaluate the missile hazard created by the fire doors. The licensee replacedthe rupture discs for the Unit 2 HPCI and RCIC systems with new ones after theevent at Unit 1 and is considering burst testing the removed discs todetermine if they are degrade IN 93-67August 16, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grim s, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Clark Vanderniet, RIII(708) 790-5594David Skeen, NRR(301) 504-1174
Attachments:
1. Figure 1, "Simplified Layout of Quad CitiesStation HPCI Turbine Exhaust Steam Line"2. List of Recently Issued NRC Information Notices Cq~0crcOCd) h r-4 0\TOSUPPRESSIONPOOL1OUTER RUPTURE DISC _____CLOSABLE CHECKCHECK VALVE VALVE IINNER RUPTURE DISC[1 In]240.6 cm[16 in]VENT TOHPCI ROOMSTEAM INLET LINEFROM "B" MAINSTEAM LINELOCKEDOPENIIIIIRX BLDGIIII50.8 cm[20 In]61 cm[24 In]HPCI ROOM25 cm[10 In]D NOTES:1. PRESSURE SWITCH ACTUATES ALARM IN CONTROL ROOM WHEN PRESSURE BETWEEN THE INNER RUPTURE DISC AND OUTERRUPTURE DISC IS GREATER THAN 68.9 kPa [10 psig]. ALARM IS FOR INNER RUPTURE DISC LEAK DETECTION.2. REDUNDANT PRESSURE SWITCHES IN EXHAUST STEAM LINE TRIP THE HPCI TURBINE IF PRESSURE IS GREATER THAN 689 kPa [100 psig].3. RUPTURE DISC MAXIMUM DESIGN BURST PRESSURE IS 1034 kPa [150 psig].Figure 1 -Simplified Layout of Quad Cities Station HPCI Turbine Exhaust Steam Line Attachment 2IN 93-67August 16, 1993 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to93-6693-6593-6493-6393-6293-6193-6093-5993-58Switchover to Hot-LegInjection FollowingA Loss-of-CoolantAccident in Pres-surized Water ReactorsReactor Trips Causedby Breaker Testingwith Fault ProtectionBypassedPeriodic Testing andPreventive Maintenanceof Molded Case CircuitBreakersImproper Use of SolubleWeld Purge Dam MaterialThermal Stratificationof Water in BWR ReactorVesselsExcessive Reactor CoolantLeakage Following A SealFailure in A ReactorCoolant Pump or ReactorRecirculation PumpReporting Fuel Cycle andMaterials Events to theNRC Operations CenterUnexpected Opening ofBoth Doors in AnAirlockNonconservatism in Low-Temperature OverpressureProtection for Pressurized-Water Reactors08/16/9308/13/93-08/12/9308/11/9308/10/9308/09/9308/04/9307/26/9307/26/93All holders of OLs or CPsfor pressurized waterreactors.All 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.All holders of OLs or CPsfor boiling water reactors.All holders of OLs or CPsfor nuclear power reactors.All fuel cycle and materialslicensees.All holders of OLs or CPsfor nuclear power reactors.All holders of OLs or CPsfor pressurized-waterreactors.OL = Operating LicenseCP = Construction Permit l--IN 93-67August 16, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.orig /s/'d by CIGrimes/forBrian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Clark Vanderniet, RIII(708) 790-5594David Skeen, NRR(301) 504-1174
Attachments:
1. Figure 1, "Simplified Layout of Quad CitiesStation HPCI Turbine Exhaust Steam Line"2. List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE.OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE 07/08/93 , 07/08/93 07/14/93 07/14/93OFC *C:DRS:R-III *SC:OEAB:DORS *C/OEAB/DORS *C:SPLB:DSSANAME GWright I RDennig AEChaffee CEMcCrackenDATE [ 07/14/93 1 07/15/93 07/15/93 ]07/16/93I__ _ iOFC*D:DSSA*C/OGCB:DORSD/DORS A^rNAME AThadani GMarcus BGrimes tDATE 07/24/93 07/29/93 0,S/\o/93 V[OFFICIAL RECORD COPY]DOCUMENT NAME: 93-67.IN
\-IN 93-XXJuly XX, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts: Clark Vanderniet, RIII(708) 790-5594David(301)Skeen, NRR504-1174
Attachment:
List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCE.*D:DSSAAThadani07/24/93OFC *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE J 07/08/93 07/08/93 07/14/93 07/14/93OFC *C:DRS:R-III *SC:OEAB:DORS *C/OEAB/DORS *C:SPLB:DSSANAME GWright RDennig AEChaffee CEMcCrackenDATE J 07/14/93 07/15/93 107/15/93 J07/16/93.Y.OFCC/OGCB:DORSD/DORSNAME GMarcus ifM BGrimes TDATE 07/.9/93 07/ /93[OFFICIAL RECORD COPY]DOCUMENT NAME: IN93 XX.QC1 IN 93-XXJuly 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:Clark Vanderniet, R-III(708) 790-5594David Skeen, NRR(301) 504-1174
Attachment:
List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain l PWen CVandernietDATE07/08/9307/08/9307/14/9307/14/931'I*C:DRS:RIII *SC:OEAB:DORS *C:OEAB:DORS C:SPLBAS* D: DSS 3q %GWright RDenning AChaffee CEMcCracken ACThadani07/14/93 [07/15/93 07/15/93 -07/2/f93 07/2A/93C:OGCB:DORSD: DORSGHMarcus BKGrimes07/ /93 07/ /93DOCUMENT NAME: QCHPCIIN.WENC 5 G-4J -z--l -2'J 4 3-- -k k- 9 C J-
IN 93-XXJuly 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:Clark(708)Vanderniet, R-III790-5594David Skeen, NRR(301) 504-1174
Attachment:
List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEOFFICE *OEAB:DORS *TECH:ED *OGCB:DORS *DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE07/08/9307/08/9307 114/9307/14/93L, _, I_,__ _ .., __ ...I_ I -*C:DRS:RIII S ODORS EAB:DORS C:SPLB:DSSA D:DSSAGWright R enn afaf' afee CEMcCracken ACThadani07/14/93 [ 3 07/j</93 07/ /93 07/ /93C:OGCB:DORSD:DORSGHMarcus BKGrimes07/ /93 07/ /930DOCUMENT NAME: QCHPCIIN.WEN
-E7/14/9312:53 ?03 787905538417463837P. 0',This infiyou havethe techRoactorIN 93-XXJuly xx. 1993 Irmation notice requires no specific action or written response. Itany questions about the information in this noticet please contactlcal contmct listed below or the appropriate Office of Nuclearr.gulmtion (NRR) project manager.Brian K. Grimes, DirectorDivision of sOrating RGOM SupportOffice of Nuclear Reactor RegulationTechnic~l contactsClark Vanderniet, R-II1(708) 790-5594Oavid Skeen NRR(301) 604-1174Attach4nt: List of Recently Issued NRC Information Notices/._ _ *,,1'SEL PR -.IUUb 6UNCUUMM6C,OFFIC D _ *TECH:,ED -I _ I RNAME _ JGnMain PI_. .,I -- '^A j"IR na jai4I 7/1k01.%0J//Y//93I1UATI I uJ 1 b I W ._ II nF&-flIA I C:PBDS :ISS I ----.n J T TVcr P. rAn
- Motwrn r nAs WDgRI C.SPLB*DSSAD :DSSA_ICh ouf I 1NNI I I I;rn n I= -- 1 --.-. -T II 1Atn"^"4^"I ji 1%V, famrEIaCrackenACThadani _1OI-lqn 0, 7/ R/9M3..~07~11 9 93 07/ /93 -- 107/ /193 -IQl l 193 107/ /93--:_ _r _r.nnr 'f lRSD:DORSus BK rimes-.. ..- _ L4Y.IIuL)OCUME NA ML: QUMrLun.w~J'14 JUL 93 B: 5uLETd lN11 211HM DUN411 b0S T ,z ES:90 t 5os->X-L0LM1 b0S IQ£ J\1IN 93-XXJuly xx, 1993 This information notice requires no specific action or written response. Ifyou have any questions about the information in this notice, please contactthe technical contact listed below or the appropriate Office of NuclearReactor Regulation (NRR) project manager.Brian K. Grimes, DirectorDivision of Operating Reactor SupportOffice of Nuclear Reactor RegulationTechnical contacts:Clark(708)Vanderniet, R-III790-5594David Skeen, NRR(301) 504-1174
Attachment:
List of Recently Issued NRC Information Notices*SEE PREVIOUS CONCURRENCEIOFFICE *OEAB:DORS *TECH:ED _ _GC i'O W DRS:R-IIINAME DSkeen JMain PWen CVandernietDATE07/08/9307/08/9307/ W/9307/ /93C:DRS:RIII SC:OEAB:DORS C:OEAB:DORS C:SPLB:DSSA D:DSSAGWright RDenning AChaffee CEMcCracken ACThadani07/ /93 J07/ /93 07/ /93 07/ /93 07/ /93..IC:OGCB:DORSD:DORSGHMarcus BKGrimes07/ /93 07/ /93DOCUMENT NAME: QCHPCIIN.WEN I' >OFC OEAB:DORS SC/OEAB:DORS PUB:ADM C/OEAB:DORSNAME DSkeen o RDennig Tech Ed T7av LY AChaffee[DATE 17/g/93 / /93 7/P /93 / /93OFC OGCB:DORS C/DRS/R-III DRS/R-IIINAME PWen GWright CVandernietDATE / /93 / /93 / /93OFC TECH BRANCH CHF TECH BR C/OGCB:DORS D/DORSNAME l GMarcus l BGrimesDATE / /93 / /93 / /93 1 / /93 l[OFFICIAL RECORD COPY]DOCUMENT NAME: IN93 XX.QC1
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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)
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