The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

"Assessment of Hydraulic Performance of WNP-1 Containment Recirculation Sumps (Hydraulic Evaluation of Design of Containment Recirculation Sumps) & (Hydraulic Model Study of Containment Recirculation Sumps)."

[[ASSESSMENT OF THE HYDRAULIC PERFORMANCE OF THEf WNP-1 CONTAINMENT RECIRCULATION SUMPS[[ HYDRAULIC EVALUATION OF THE DESIGN OFLCONTAINMENT RECIRCULATION SUMPSby'Mahadevan PadmanabhanHYDRAULIC MODEL STUDY OF CONTAINMENTRECIRCULATION SUMPSbyf William W. DurginLJohn F. NoreikaWA...

Salem, Units 1 and 2, Revision to Request for Changes to Technical Specifications Containment Systems - Containment Cooling System.

PSEG Nuclear LLCP.O. Box 236, Hancocks Bridge, New Jersey 08038-0236'AUG 1 1 2005LR-N05-0377LCR S03-07 0 S G"Nuclear LLCU. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001REVISION TO REQUEST FOR CHANGES TO TECHNICAL SPECIFICATIONSCONTAINMENT...

"Rept on Containment Safety at Vermont Yankee."

. . .. .IREPORT ONCONTAINMENT SAFETYAT VERMONT YANKEE'April 29,1988l1I||1Vermont Yankee Nuclear Power Corporation%{$$"'$800!$$0Sfff1.- - .. .INTRODUCTION!This report gives a comprehensive review of the status ofcontainment safety at the Vermont Yankee nuclear power plant inVer...

Proposed Tech Specs 3/4.6.1.2 & 3/4.6.3,addressing containment leakage & containment isolation valves, respectively.

g . P,_A ., ,. . _ __ --- .my^y . j }| :t.9s$ ;l.-,,,;i?'TA3,4TjC ..,,|\'-= Attachment 11 to WM 88-0080MPage- 1 cfN3/ .f'fMarch 28,19'( ( k'>'(, )% \q,jCONTA_INMENT WSTEMS --.i < or equal toL,, 0.20% by weignt of the containmer:)3.$ir per 34 hours at P ,i ,3 psig, orj3,f4<'

Responds to 781129 ltr re containment purge issue.Forwards C-E ECCS performance evaluation,assessment of radiological release from containment & discussion of containment purge isolation instrumentation & control circuit designs.

REGULATORY I RMATION DISTRIBUTION SYS1 (BIDS)ACCESSION NBR e 7912200408 DOC~ DATE i 79/12/13 NOTARIZED: YESF'ACIC;So-335St. Luc/e Planti Unit ii Florida Power L'Light Co.,AOTH; NAME'AU'THORAFFILIATIONUHAIGgR ~ ED Flo.iidaPower"L Light Co,REC IP, NAME RECIPIENT AFFILIATION*Of f...

Discusses AEC participation in Markviken II containment test program.Unanticipated phenomenological events noted:pressure oscillations in vent pipes to supression pool & containment subcompartments & unexpected containment temp responses.

''- -_ _. -nbde'l . .fE2 "4UNITED STATESbATOMIC ENERGY COMMISSION ,wasuinarou.o.c. zos4s ,?j""n *August 16,1974'-J.;- |, Dr. H. Kouts, Director; Division of Reactor Safety Research-.;:ilAEC PARTICIPATION IN THE MARVIKEN II CONTAINMENT TEST PROGRAMThe Marviken I containment tes...

Proposed Tech Specs modifying containment isolation barriers.

__ _ _ _ _ _ _ _ _ _ _ _ _ _?.. .!..,i|3/4.6 CONTAINMENT SYSTEM _S_3/4.6.1 PRIMARY CONTAINMENTCONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.APPLICABILITY: MODES 1, 2, 3 and 4ACTION:Without primary CONTAINMENT INT...

Proposed Tech Specs re primary containment isolation & primary containment leakage test penetrations.

, , ,..4., _, . ,g>7 , a, ,,w _, < , ,7;7,*fp .; ;) , n. ; c. 'J -'s..,v- s 35, t . , y h ,!.o,L.;h_ , J',o(v: .: *;; . . . G*,"1 > ,^i;;. :> ,*>y. 'l l,, . ,~ ,'F-hc j,('''/ i s.. ,'i {',':i< 4 ;*... . ,'.},2 . i..1'Is ..y , . , ' 5,' >,., . . ,f hd.:- -,.ATTAca nt 1.! p--c.,...

Proposed tech specs re containment sys.

- .. - -- _- - --I'.LAR 95-0017Page 9|1INDEILIMITING CONDITIONS FOR OPERATION AND SURVII11ANCE REQUIREMEN13I PACISECTIONi23/4.6 CONTAINMENT SYSTEMS3/4.6.1 FRIMARY CONTAINMElffIcontainment Integrity . . . . . . . . . . . . . . .3/4 6-1tContainment Leakage . . . . . . . . . . . ...

"Reactor Containment Bldg Integrated Leak Rate Test."

H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST NOVEMBER 1984 CAROLINA POWER & LIGHT COMPANY Prepared by: Reviewed by: ILRT Engineer Approved by: _ _ _ _ _ _ _ _ Gilbert /Commonwealth 8502010408 850128 PDR ADOCK 05000261 P ...

Tech Specs 3/4.6.3 for containment sys.

'. CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment.isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With one or ...

Proposed Tech Specs re containment purge sys.

_ _ - 'N C - A l/07CONTAlNMENT SYSTEMSCONTAINMENT PURCE SYSTEMLIMITING CONDITION FOR OPERATION3. 6.1. 9The containment purge system supp'y and exhaust isolation valvesshall be OPERABLE and either the 20 inch or the 6 inch purge system may be inoperation; however, the 20 inch p...

Proposed Tech Specs re containment isolation valves.

.,|. , .,Docket No. 50-423812985..Attachment 1-.,Proposed Revision to Technical SpecificationsContainment Isolation Valves:,i4f,;i.:September 1988$$$"$Dockb[P- - . . _ . _ _ . _ _ . . . . . _ ,*:,. .INDEXLIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSSECTIONfAG...

LER 85-018-00:on 850525,valve 1RV-429 in containment ventilation cooling water sys outside containment found open,allowing flow path between auxiliary bldg & upper containment through inside containment valve.W/850708 ltr.

r~,afmc Form 305U S NUCLEM4 L E1;UL1 TORY COMM80 BION~431 AP* ROVED OMG NO 3:50 4 104*" ' ' " ' ' ' ' ' " ' 'LICENSEE EVENT REPORT (LERIDOCKET NUMSER (2)PAGE GFACILITY NAME HDMcGuire Nuclear Station - Unit 1 o |510 to |0 | 3 6|9 i|os|04 1 1n at i.IContainment Integrity Violate...

St. Lucie, Unit 2 - Proposed License Amendment Regarding Containment Equipment Door and Containment Airlock Doors Open During Core Alterations.

Florida Power & Light Company, 6501 South Ocean Drive, Jensen Beach, FL 34957 0 June 22, 2001 FPL L-2001-083 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment Cont...

"Containment Bldg Structural Integrity Test."

•\ '\ :'..--\ \r,· ~ . \ .... ~. ', ' .. ·- '. • • L_____ ' ·. CONSUMERS POWER COMPANY PALISADES PLANT CONTAINMENT .BUILDING STRUCTURAL INTEGRITY TEST BECHTEL COMPANY JOB 5935 . November 1970 -'::::l -._ .... -.-_ _, -,.J .. :., .. • ATTACHMENT CONTAINMENT BUILDING STRUCTURAL ...

Proposed tech specs 3/4.6.1, "Containment Integrity," clarifying when verification of primary containment integrity may be performed by administrative means.

• • 3/4.6 CONTAINMENT SYSTEMS ~ 3J4.6.l PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION ============================================================================= 3.6.l.l Primary CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: MODES l, 2...

Forwards containment vessel integrated rate test rept. Containment vessel assessed as functionally adequate.W/o encl.

NRCp;nu 195u.s. Nucta An natutAreny cowwissGN ooCEST NuM!E n$0 3 n12-27-76 ehfASSIGNED AD: V4.s s e & ( u e) AmmTr w n an.BRANCH CMT'v? 0 +0/ t (<4) . 1tnAsn r trTev.i ----PROJECT MANAGERr En < /4. - WS'''''3PROJECT MANAGER:|---LIC. ASST. :A#ffo n .MMLIC. ASST. :-'-',_. i',h ....

Proposed Tech Specs re containment isolation valves.

,• REVISED PAGES - UNIT NO. 1. {/) ):ii t"i ~ I c:: VALVE NUMBER :z: H 1-:1 A • PHASE 11A11 ISOLATION ..... 1. 1 PR 17* 2. 1 m 18* 3. 1 NT 25* 4. . 1 WR 80* 5. 1 CV 3 6. 1 CV 4 7. 1 CV 5 8. 1 CV 7 9. 1 CV 68## 10. 1 CV 6911 11. 1 CV 284 w 12. 1 CV 116 ' 13 • 1 cc 215 .. ..,, O...

"Reactor Containment Bldg Integrated Leak Rate Test."

REACTOR CONTAINMENT-BUILDING" INTEGRATED LEAK RATE TEST JULY, 1985 DUANE ARNOLD ENERGY CENTER DOCKET 50-331 OPERATING LICENSE DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY8511190331 851114 PDR ADOCK 05000331 P PDRMIATORY DOCKET FILE COPYREACTOR CONTAINMENT INTEGRATED LEAK RATE ...

Proposed tech specs re secondary containment.

--,|r.Docket No. 50-423rB15215i:i|!Attachment 1Millstone Nuclear Power Station, Unit No. 3Proposed Revision to Technical SpecificationsSecondary ContainmentMarked-up PagesJune 19959506190044 950609PDR ADOCK 05000423P PDR- - -- . - - - . - - . - . .-. ==- . -i|-|12/08/93^2EEINF...

RELIABILITY ASSESSMENT OF CONTAINMENT TANGENTIAL SHEAR FAILURE.

. . ...REG /CR-4366L-NUREG-51913RELIABILITY ASSESSMENTOF CONTAINMENT TANGENTIAL SHEAR FAILURES. Pepper H. Hwang, and J. Pires:Date Pubilshed - January 1986,STRUCTURAL ANALYSIS OlVISIONDEPARTMENT OF NUCLEAR ENERGY, BROOKHAVEN NATIONAL LABORATORYUPTON, NEW YORK 11973--_{)} hSInt...

"Primary Reactor Containment Structural Integrity Test."

SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION PRIMARY REACTOR CONTAINMENT STRUCTURAL INTEGRITY TEST (SO1k3 9(DSAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 CONTAINMENT STRUCTURAL INTEGRITY TEST FINAL REPORT PREPARED BY BECHTEL POWER CORPORATION FEBRUA...

Responds to Generic Ltr 89-16 re Mark I containment hardened vent.Procedures in place & operators trained to vent containment if needed to maintain containment integrity.

. - , -*e :*\.,*.OPU Neeleet CorporationOne Upper Pond Road,erPar 61ppany. New Jersey 07054201 316 7000iTELEX 136 482 ;Writer's Direct Dial Number:JOctober 30, 19895000-89-1832>|U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555|'Gentlemen{Subj...

Callaway Plant - Proposed Revision to Technical Specification 3.9.4, "Containment Penetrations," 3.3.6, "Containment Purge Isolation Instrumentation" and 3.3.7, "CREVS Actuation Instrumentation."

PO Box 620 Fulton, MO 65251December 6, 2001U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.C. 20555-0001Ge WAmeren UliULNRC- 04574ntlemen:DOCKET NUMBER 50-483 CALLAWAY PLANT UNION ELECTRIC COMPANY PROPOSED REVISION TO TECHNICAL ...