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Provides addl info to resolve discrepancy re design & testing of containment vacuum relief instrument sensing lines penetrating primary containment.

,_ __ _ _ . _. . . . . . _ _ _!-'.&ntergy ~Egggca>r,'tiaa=.i e-.Operationsx= m t^ 700c0i 'T6 504-739-6650W3F1-97-0046A4.05PRMarch 17,1997U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555Subject: Waterford 3 SESDocket No. 50-382License No. NPF-...

FRN - Combustible Gas Control in Containment

[7590-01-P]NUCLEAR REGULATORY COMMISSION10 CFR Parts 50 and 52RIN 3150 - AG76Combustible Gas Control in Containment AGENCY: Nuclear Regulatory Commission.ACTION: Final rule.SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its regulations forcombustible gas control...

Draft Tech Specs re containment sys primary containment leakage.Related info encl.

. . ._ ~- .,q.--.-,*Ig,CONTAINMENT SYSTEMS gPRIMARY CONTAINMENT LEAKAGEi, LIMITING CONDITION FOR OPERATION,.'3.6.1.2 Primarycontainmentleakageratesshallbe}imitedto:,An overall integrated leakage rate of less than or equal to L,,;a.-0.635 percent by weight of the containment ai...

"Experimental Evaluation of Reactor Containment Sump."

_ _ _ _ - _ _ _ _ _ - _ - _ _ _w7.n. v,c,w wn- .: ,.., s ..x. ..e. - ~,- _ .,s,+ . .,e,.-<. > n-tj y . s _.Lr+cp,,.rs. .o<. > ,... , - ._. . c. 'm . . .- m,4, .1 5,a'0[ k Q "6,# 5 4' i** i' 7e es- _ _ _an,] J-. __'' 8^'" '-''s i .W*f,7y , 'i,4 ;, fiabym,w' %.g . ' s... .-: --w...

Proposed Tech Specs governing containment leakage testing.

gegula$ Docket Qlg'1'..LICENSE AME?DtENT REQUEST LATED JANUARY 31, 1976EXHIBIT BN bI*.";.,agM . l.rg'q $ jall:of the proposed Technical Specification changes:l ' ihis exhibit consists of the following pages reviced or added to incorporate*, s .. w ,_ c. #, m' 't !',,k > '' .s ...

Hatch, Technical Specifications Revision to Secondary Containment Access Door Surveillance.

Lewis Sumner Southern Nuclear Vice President Operating Company, Inc. Hatch Project Support 40 Inverness Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 Fax 205.992.0341 SOUTHERN COMPANY December 2, 2002 Energy to Serve Your Wor1dM Docket Nos. 50-321 H...

"Structural Analysis of Containment Vessel (Conrad Rept)."

• ATTACHMENT 4 PSE&G CALCULATION SS0-0791 STRUCTURAL ANALYSIS OF CONTAINMENT VESSEL (CONRAD REPORT) PAGES 225, 241, AND 243 THRU 270 _ ... · ..... .. ;;; ...... • MOOP FORCE (KIP/ FT) EJ..[V ... NAOIA.t. STll[S!i IJt.Sr) VERTICAL STF?E!S (K!!"'l ,. CIR CU MF ERE PITIA !,, Ill ...

Revision to Technical Specification 3.6.3, "Containment Isolation Valves".

WI~LF CREEK'NUCLEAR OPERATING CORPORATIONDonna JacobsVice President Operations and Plant Manager-JUL 2 3 2004WO 04-0030U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555References: 1) Letter ET 02-0030, dated August 16, 2002, from G. B. Fader,WC...

LER 86-039-00:on 860812,containment air release & addition sys automatically isolated due to containment gaseous radiation levels exceeding containment gas monitor trip setpoint.Caused by conservative setpoint.W/861002 ltr.

wt'U.S. NUCLEAR !.EGULATORY CC-seRC Pere MeAppMOVE2 OMO NO. 3iess!104***''7'*'''""LICENSEE EVENT REPORT (LER)FACILITY NAAAE (IlDOCKET NURAeER (2)PAGE433Catawba Nuclear Station, Unit 20 | 5 | 010 | 0141114 1|OF|013TITLE (4)Three Containment Isolations Due To Conservative Trip S...

Submits clarification re instrumentation installation for NUREG-0737,Items II.F.1.4, "Containment Pressure Monitor" & II.F.1.6, "Containment Hydrogen Monitor."

--.oMR%,j |, 0 $ 'i %gdYIV.[D$/~|~~ ~- A :g>ye,p: :pcr +qLyey?iVgfpMPowerC 0m POn a 7 ionOctober 18,1982#3F-1082-17File: 3-0-26Mr. John F. Stolz, ChiefOperating Reactors Branch #4Division of LicensingU.S. Nuclear Regulatory CommissionWashington, DC 20555S' bject: Crystal River...

Transmittal of PWR Containment Sump Evaluation Methodology.

N U C L E A R EN ERGY INSTI T UTE Anthony R. Pietrangelo SENIOR DIRECTOR, RISK REGULATION NUCLEAR GENERATION May 28, 2004 Mr. John N. Hannon Chief, Plant Systems Branch Office of Nuclear Reactor Regulation Mail Stop O11-A11 U.S. Nuclear Regulatory Commission Washington,...

Provides justification for min containment pressure used to initiate containment isolation for facility,per NRC 801231 request re NUREG-0737.Present containment isolation setpoint is adequate & no reduction in setpoint is warranted.

.4oOoNtHrrHI!A!ir trrII. FRIES3.:LC.'o|MC27~[OOroNcoNNECTICUT 06101*;| :C||* : .;'," "~:2%) M9nL t a r;"""|1:|'|: ' '77'February 27, 1981-x@'Docket No. 50-336gghfpA01328 ;Director of Nuclear Reactor RegulationAttn: Mr. Robert A. Clark, Chiefo40fOperating Reactors Branch #3M,

FC Final Containment Structural TIA.

January 28, 2014 MEMORANDUM TO: Kriss M. Kennedy, Director Division of Reactor Projects Region IV FROM: Sher Bahadur, Deputy Director /RA/ Division of Policy and Rulemaking Office of Nuclear Reactor Regulation SUBJECT: FINAL RESPONSE TO TASK INTERFACE AGREEMENT 2...

NuScale Design-Specific Review Standard Section 6.2.1.1.A, Containment.

ADAMS Accession No. ML15355A544 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD for NuScale SMR DESIGN 6.2.1.1.A CONTAINMENT REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of containment integrity Secondary - None I. ARE...

Special rept:on 880914,performance strength test of removed containment tendon wire failed to meet accepted criteria. Containment structural integrity restored by verifying that containment has required level of integrity.

._ _ _ _ _ _ .- - -~,$W''Commtnwoolth EdloonJ * *'g'-- Rural Route #1, Box 220 -LaSalle County Nuclear Station-,p Marsellius,Ilknois 61341Telephone 815/357 6761September 28, 1988Mr. A. Bert DavisRegional Administratore!' Region III'!U.S. Nuclear Regulatory Commission199 Roosev...

Proposed tech specs 3/4.6.1.2, "Containment Leakage."

ATTACHMENT 2 TECHNICAL SPECIFICATION PAGE WITH PEN AND INK CHANGES LICENSE AMENDMENT APPLICATION ONE-TIME EXTENSION OF SURVEILLANCE REQUIREMENT INTERVAL SALEM GENERATING STATION UNIT NO. 1 FACILITY OPERATING LICENSE DPR-70 LR-N95056 DOCKET NO. 50-272 LCR 95-06 The following Te...

LER 92-002-00:on 920430,containment pressure channel "C" sensing line for containment pressure instrument PT-07-2C process line in containment capped.Caused by personnel error.Cap on channel "C" removed.W/920527 ltr.

ACCELERATEDDISTRIBUTIONDEMONS~TION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9206020321 DOC.DATE: 92/05/27 NOTARIZED: NOFACIL:50-389 St. Lucie Plant, Unit2, Florida Power & Light Co.AUTH.NAME, AUTHOR AFFILIATIONSIENKIEWICZ,S. Florida Power & Light Co...

Proposed rev to TS 3/4.6 to remove list of containment isolation valves,revising allowed outage time for CCW motor operated containment isolation valves & allowing use of containment penetration check valves as isolation devices.

;riATTACHMENT 1TECHNICAL SPECIFICATION CHANGES(MARKED UP).>f9507060087 950626PDR ADOCK 05000483P PDRp;R "' TN'l)INDEX.LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS*9PAGESECTIONEMERGENCY CORE COOLING SYSTEMS (Continued)'3/4 5-103/4.5.5REFUELING WATER STORAGETA...

"Passive Containment Cooling Condenser Equipment Requirements Specification."

. .. _ , .~ _ . - . _r h.6Progetto identifcattvoocoact m noS B W 5 2 8 O T N I X N O 1.5 0 0:-"SBWRCt ente Comm.EmmentePagna Di0 * *?po ao.emune py peps of.'l_,,j2 N 2 5 3 3 0 |D'N U I N C ISNTip0 00C..C.l. ns.AN89ahAag C SC A.f str cr00 !ce'ttificat'vC CCmDCPente+ODC fype Cl ...

Proposed tech specs 3/4.6 re containment systems.

e .,s,..Attachment 1I.I1|.PDR_.!'!3/4.6 CONTAINMENT SYSTEMSji 3/4.6.1 PRIMARY CONTAINMENT!,i CONTAINMENT INTEGRITYj| LIMITING CONDITION FOR OPERATION|I3.6.1.1Primary CONTAINMENT INTEGRITY shall be maintained.iAPPLICABILITY: MODES 1, 2, 3, and 4. W * ( Foor NorE- A-TMc MD)fij A...

0519 - R304P - Westinghouse Technology 5.3, 5.4, 5.5, 5.6, Containment Systems.

Containment & Containment Systems ySection 5.3-5.6Section 5.3 Objectives1. State the purpose of the containment.2. Briefly describe the function of the following:a.Containment linerb.Primary shield wallc.Secondary shield walld.Refueling canale.Containment sumpsf. Containment r...

Proposed tech specs deleting containment internal pressure & correcting typographical errors.

ATTACHMENT I TO IPN-95-067CHANGE TO TECHNICAL SPECIFICATION BASIS REGARDING CONTAINMENT PRESSURE NEW YORK POWER AUTHORITY INDIAN POINT 3 NUCLEAR POWER PLANT DOCKET NO. 50-286 DPR-64 9506200165 950615 PDR ADOCK 05000286 p PDRRegarding internal pressure limitations, the containm...

TSTF-409, "Containment Spray System Completion Time Extension"

(CEOG-151, Rev. 1) TSTF-409Industry/TSTF Standard Technical Specification Change TravelerContainment Spray System Completion Time ExtensionClassification: 1) Technical ChangePriority: 2)MediumNUREGs Affected: 1430 E 1431 v1 1432 E 1433 C 1434Description:The Completion Time for...

Forwards "Reactor Containment Bldg Integrated Leak Test."

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9101240144 DOC.DATE: 91/01/16 NOTARIZED: NO DOCKET # FACIL:50-270 Oconee Nuclear Station, Unit 2, Duke Power Co. 05000270 AUTH.NAME AUTHOR AFFILIATION TUCKMAN,M.S. Duk...

"Containment Integrity at Surry Nuclear Power Station."

- .. _ _ _ . . .__1. .., . , - _ . _ _ . , . . ,- _ ' ' " ''-,&A + ' .1.,.-f--. . .-. g . .' -.fc 4 W.goT:nlf' , * . -... . ...a~--. . - .. . .g_. _. . ., .. W.a ..,. .. .'.' M N J. N 6 % % W*)'.OW.a"'M J.*4, 3 CONTAINMENT INTEGRITY?h!%T19|lR!QNI9?)W$ RREAR .f.w.. OWE..R.. J4 ...