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LER 88-002-00:on 880203,containment ventilation isolation on high containment radioactivity signals occurred.Caused by inadequate procedural guidance re containment pressure reduction.Procedure being revised.W/880203 ltr.

-g,esev . % m ...vu ro., < - =-.,.o o.s. ,,. e,e.*UCENSEE EVENT REPORT (LER)"''*"8'8'**.!f aciLITV anAmet ttiCast anseen q) raer .3Troian Nuclear Plant0|5|0|0|0|y[4|41 |OF| 0l 3" '"Containment Ventilation Isolation on High Containment RadioactivitySignals Due to inadequate Pro...

Enclosure 4 Containment Performance RLSO.

- 1 - ENCLOSURE 4 BWR MARK I AND MARK II CONTAINMENT PERFORMANCE DURING SEVERE ACCIDENTS - 2 - Contents 1.0 Introduction ........................................................................................................................ 3 2...

Application for amend to License NPF-3 consisting of Tech Spec changes implementing containment normal sump & containment wide range level schedule,containment pressure schedule & RCS high point vents.

r._ .,*.APPLICATION FOR AMENDMENTTOFACILITY OPERATING LICENSE NO. NPF-3,FORDAVIS-BESSE NUCLEAR POWER STATIONUNIT NO. 1Enclosed are forty-three (43) copies of the requested changes to theDavis Besse Nuc1 car Power Station Unit No. 1 Facility Operating LicenseNo. NPF-3, together...

Proposed Tech Spec Sections 1.31 re primary containment integrity,3/4.6.1 re primary containment & 3/4.6.3 re primary containment isolation valves.

_-_______- _ __ _-*.,, .,ATTA N ANIMIARA NORAWK POUBR CORN *ATIONLICWitt NO. NPF-490073T NO. 50-410ff.9JRDatd. Ch40&tR._19 th.t_Itshniea1 SDicifIcation3- Replace existing pages x1, x11, xiii, 1-6, 3/4 3-15, 3/4 6-1, 3/4 6-2,3/4 B G, 3/4 6-4, 3/4 6-21, 3/4 6-22, 3/4 6-23, 3/4 7...

"Containment Vessel Structural Integrity Test."

REPORT ON CONSOLIDATED EDISON'S INDIAN POINT UNIT NO. 3CONTAINMENT VESSEL STRUCTURAL INTEGRITY TEST FOR WEDCO CORPORATION 00d6engineersC 8110240390 750221 PDR ADOCK 0500026 P PDRREPORT ON CONSOLIDATED EDISON' S INDIAN POINT UJNIT NO. 3 CONTAINMENT VESSEL STRUCTURAL INTEGRITY T...

Forwards "Reactor Containment Bldg Integrated Leakage Rate Test," & "Containment Isolation Valve Replacement Program Rept."

Aicace A.FitAP: trickkutleer Power Plantto Box 41O .saming. N3w York 13093315 342 38404ewYorkPbwerth0IIgWillbm Femander llResident ManagerOctooer 11, 1990JAFP 90-0742U.S. Nuclear Regulatory CommissionMail Station P1-137Washington, D.C. 20555Attention:Document Control DeskSUBJE...

Traversing Incore Probe (TIP) Containment Isolation Ball Valve Open Without Automatic Containment Isolation Capability

James A. FitzPatrick Nuclear Power Plant 268 Lake Road P.O. Box 41 Lycoming, New York 13093 315-342-3840 l NewYorkPower Michael J. Colomb SAuthority Site Executive Officer February 29, 2000 JAFP-00-0047 United States Nuclear Regulatory Commission Attn: Document Control Desk Ma...

Proposed Tech Specs,reflecting deletion of isolation times for specific high pressure injection & containment spray containment isolation valves & redundant listing for Containment Isolation Valves DH87 & DH88.

_ .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _..$f5![Oh!)[)$Si ' j!2 i-f.B!$t i'c .:,,: L-191J3 . , .CONTAINMENT SYSTEMS{* {.0 b:w:.>-cjNr -p ,, pT-4ry;,;gU'\-sE N E'h IY- u :[$NEd,bCONTAINMENT COOLING SYSTEMLIMITING CONDITION FOR OPERATION3.6.2.2 At least two independent containment c...

Forwards test results of secondary containment LRT per procedure 8.7.3, "Secondary Containment Leak Rate Test."

_~*App::ndix Jor*G,,Boston Edeon,Pilgrim Nuclear Power StationRocky Hill Road'Plymouth, Massachusetts 02360-5599,!IMay 20,1997|BECo Ltr. 97-052 !l.U.S. Nuclear Regulatory CommissionAttention: Document Control Desk)Washington, DC 20555Docket No. 50-293|ILicense No. DPR-35,Secon...

Interpretation of Substantially Complete Containment.

OE F 325Je, (1244) Gvrmnu nited .State-s GovernmentDepartment of EnergymemorandumDATE July 8, 1988REPLY TOATN OF: RW-222SUBJECT: Interpretation of Substantially Complete ContainmentTo Program Review GroupAttn: Steve Brocoum, ChairmanAttached is the proposed revision to Section...

Application for amend to License NPF-7 changing completion dates for implementing license conditions re containment pressure,containment hydrogen concentration,containment radiation & noble gas effluent.(ref NUREG-0737)

. _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _____ ___ __ ____ ___ __ ._ __ _ _ _ . ._ _ _ _ _>', , ,e.-VnmonunA Ex.ncranC AND Powsm COMPANYR1cuxown, VimonwsA sant,1i;ii R.H.LsAmmunevie e. ...r June 14,=1982N :ctuam oarsaarao eMr. Harold R. Denton,...

Forwards clarificaion of 810928 response to Containment Sys Branch questions re containment spray sys.

REGULAtTORY INFORMATION DISTRISUT ON SYSTEM (RIDS)ACCESSIOV! NBR:811FACILi:STN 50 528STN-50-529STN 50 530AUTrll,NAME.V A N 9 R U lViTIKr~ E"~REC IP ~VAMEITEDESCOgR,Li,0130386" DOC ~ DATKi: 81/09/30 NOTARI2ED: YESPalo Verde Nuclear Stati one Un-it ir Ar izona PubliPalo Verde Nu...

"Vermont Yankee Containment Safety Study."

- ' * ^ '.,,a ( .,. - -. # w**~ '- s...- - _ _ _ .-, ___ _ -,- + e", .,"V ,,,,#-.4.'y;_.W % ,f^, .o' ' _'"}'~ 'Zy' v %-- '+ - ,| n'h -. 'n'.'o,-v:-'''|' $*,p'. * - , 'r .),e. .y -' 4 {;3_ ~ ~ -. ?;; ;~ - , -, - - n' * - - '"f>.=Q 7.s.,*<,'' - I <--6,j \' .3* # y [ . , . , ' . ...

Forwards response to IE Bulletin 80-24, "Prevention of Damage Due to Water Leakage Inside Containment." Describes containment fan cooling sys,only open cooling water sys inside containment.

~----·· --Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production Mr. Boyce H. Grier, Director Office Of Inspection and Enforcement U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King ...

Proposed tech specs 3.6.1 re containment,3.6.2 re containment air locks,3.6.3 re containment isolation valves & 5.7 re procedures,programs & manuals.

I ..-- --~ ... .. ... -.SURVEILLANCE REQUIREMENTSSURVEILLANCE FREQUENCYSR 3.6.1.1 Perform required visual examinations and -----NOTE------leakage rate testing except for containment SR 3.0.2 is notair lock testing, in accordance with applicable10 CFR 50, Appendix j, a modified...

Proposed Tech Specs re containment spray subsystem, containment spray sys & total sys uncollected leakage.

e ATTACHMENT 1 Proposed Technical Specifications Change I ' Discussion The Nuclear Regulatory Commission (NRC). requested information from Virginia Electric and Power Company concerning offsite doses after a Loss-Of-Coolant Accident (LOCA) by letter, dated July 9, 1976. Additi...

CONTAINMENT INTEGRITY RESEARCH PROGRAM PLAN.

-.-.-.NUR EG-1264_ _ _ ._.__Containnlent IntegrityResearchProgram PlanU.S. Nuclear RegulatoryCommissionOffice of Nuclear Regulatory Researchy ''o,,,o! - '|-ci.x,;e,,,,,-8709160104 870831PDRNUREGPDR1264 R_ - _ _ _ _ _ _ _ _ _. _ _ _. _ _ _ _ - _ _ _ - _ -'". . _ _.NOTICEAvailab...

Forwards application for amend to License NPF-3,revising TS Definition 1.8, "Containment Integrity," TS 3/4.6.1.1, "Containment Integrity & Bases," TS 3/4.6.1.2, "Containment Leakage" & TS 3/4.6.1.3, "Containment Air Locks."

. . _ _ . . _ ._ _ _ _ _ _ _ _ ___ _ _ . . - _ _ _ _ . _ -_. ,fcg w' ra m o a= ENERGY._ Donsid C. Shelton 300 Madison Avenue' Vee Presdent Nuclear .Toledo, OH 436520001DaveBesse(419)249 2300Docket Number 50-346License Number NPF-3Serial Number 1971May 1, 1992--United States ~ ...

"Structural Integrity Test of Containment."

REPORT ON STRUCTURAL INTEGRITY TEST OF CONTAINMENT UNIT NO. 2 SALEM NUCLEAR - NOTICE -THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE . DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE. RETURN.ED TO THE RECORDS FACILITY BRANCH 01...

LER 12-002-00 for Fort Calhoun Regarding Inadequate Qualifications for Containment Penetrations Renders Containment Inoperable.

r~e ----~~------DPPD ---Omaha Public Power District 444 South 16111 Street Mall Omaha, NE 68102-2247 LIC-12-0043 May 1, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285 Subject: Licensee Event Report 20...

Forwards response to NRC 791217 request for addl info re containment purge & venting sys.Discusses primary containment atmosphere control piping penetrations & leak rate testing of containment purge & vent valves.

.rCnI VERMONT Y AN K EE NUCLEAR POWER CORPOR ATION*C'V43SEvErJTY SEVEN GROVE STREETB.3.2.1kVY 80-24RUTI.AND, VEID10NT 05701REPLY TOENGINEERING OFFICETURFt TE Ro ADW EST DO RO. M ASS AC HU SE T T S C 15 L 19 TELEPHONE 617-366 9019United States Nuclear Regulatory CommissionWashi...

Forwards rept on containment access mgt & containment purge activities during Cycle 1 operation at plant.Rept satisfies SER Section 6.4.2.3 re containment purge data collection.

ppm =-~ , 7( .- ' - -- - - - - - - - - - - - - - - - - - ~ - -- - - - - - - - - -. . . - ..g .a, . .>'m , ;g gjpm ys.; .; * : , ;;i,m.,H,..m,,. r ..',. 'i.'q 3 at',',. ,,., . GULF, i STATESUTILITIES COMPANY.1m|J ,:1>October, 30, 1987-RBG- 26880 y^~File Nos. G9.5, G9.23! i's:;....

Tech Spec re containment sys.

.. . . . . - - . . ..'.17. '.'..~[ICONTAINMENT SYSTEMSINTERNAL PRESSURE'LIMITING CONDITION FOR OPERATION!3.6.1.5 Primary containment internal pressure shall be maintained between-qw and+0. 2 PSIG.APPLICABILITY: MODES 1, 2, 3 and 4.ACTION:With the containment internal pressure ...

THE PROBABILITY OF CONTAINMENT FAILURE BY DIRECT CONTAINMENT HEATING IN SURRY.

•• NUREG/CR-6109 SAND93-2078 The Probability of Containment Failure by Direct Containment Heating in Surry • Prepared by M. M. Pilch, M. D. Allen/SNL B.W. Spencer/ANL K. D. Bergeron/SNL K. S. Quick, D. L. KnudsonnNEL E. L. Tudios, D. W. Starnps/SNL Sandia National Laboratories...

Discusses agreements reached at 830113 meeting re containment purge sys,SER Outstanding Issue 10a,concerning containment continuous vent & purge sys.Proposal for redesign of containment ventilation sys included.

\oeU-0592/LLINDIS POWER 00MPANY'73739_g3g93_3yy_5500 SOUTH 27TH STiicET, DECATUR, ILUNOIS 62525January 17, 1983Director of Nuclear Reactor RegulationAttention: Mr. A. Schwencer, ChiefLicensing Branch No. 2Division of LicensingU. S. Nuclear Regulatory CommissionWashington, D.C....