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Forwards "Containment Structures Design Rept,Revision 2" incorporating GE load definition info & documenting design change to containment dome.

HoustonrcompanyElectric Tower.RQ Box 1700Houston. Texas 77001December 20, 1979AC-IIL- AE-382Mr. Ilarold R. Denton, DirectorOffice of Nuclear Reactor RegulationNuclear Regulatory CommissionWashington, D. C. 20555Dear Sir:Allens Creek Nuclear Generating StationUnit 1Docket No. 5...

Proposed Tech Specs re reactor encl secondary containment integrity.

CONTAINMENT SYSTEMS''3/4.6.5-SECONDARY CONTAINMENTREACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITYLIMITING CONDITION FOR OPERATION3.6.5.1.1 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY shall bemaintained.APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.ACTIONWithout REA...

Proposed tech specs 4.6.1.5 re containment systems air temp.

" • CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION ============================================================================== 3.6.1.5 Primary containment average air temperature shall not exceed 120°F. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With ...

"Secondary Containment Drawdown Analysis & LOCA Radiological Analysis."

ATTACHMENTNINE MILE POINT UNIT THOSECONDARY CONTAINMENT DRAHDONN ANALYSISANDLOCA RADIOLOGICAL ANALYSISAUGUST 1988j3+083102~05000~f.0gapS26PDRADOCPDCPI~~1.0 SECONDARY CONTAINMENT DRAW-DONN ANALYSIS1.1 IntroductionFollowing a postulated loss-of-coolant accident (LOCA), thesecond...

Forwards responses to NRC questions on containment H control sys from 960401 ltr & containment pH control from 960308 ltr.

__ __ _Westinghouse Energy Systems Box 355Electric CorporationPittsourgn Pennsywania is230-aassNSD-NRC-964810DCP/NRC0596Docket No.. STN-52-003August 30,1996Document Control DeskU.S. Nuclear Regulatory CommissionWashington, D.C. 20555ATTENTION:T.R. QUAYSUBJECT: RESPONSES TO NRC...

"Integrated Primary Containment Leakage Rate Test."

''e .,,w : . < > e..s . c ,i ,. ~ , e..:o,1,s..,y', A j,.'*3a , . |S ', . 'h"T T ,b ' c, .. - ..,,," i.;/, A -., s.. ReguJ,atory F.Ve . cy.1 ,,, ...',,m, . .s e --.' a *- !~ *rc',*,# , [. , b/,'7-gi, . , . . '--a 5s&.,ur Sh/NN3|~a,..''-, ,... g, .. . . . r ,.<' '{t' '_ . , , ....

AP1000 Containment Vessel External Pressure Analysis And Design.

AP1000 CONTAINMENT VESSEL EXTERNAL PRESSURE ANALYSIS AND DESIGN NRC REVIEW PACKAGE TABLE OF CONTENTS 1.0 BACKGROUND 2.0 PROPOSED CHANGES 3.0 PROPOSED DCD CHANGES AND JUSTIFICATION TABLE 4.0 NECESSARY DCD MARKUPS 5.0 CONTAINMENT VESSEL EXTER...

Salem, Unit No. 1, Technical Specifications, Consolidate the Containment Isolation Requirements by Moving the Requirements of TS 3/4 6.1.7, "Containment Ventilation System," to TS 3/4 6.3.1, "Containment Isolation Valves."

- 4 -(1) Maximum Power LevelPSEG Nuclear LLC is authorized to operate the facility at asteady state reactor core power level not in excess of 3459megawatts (one hundred percent of rated core power).(2) Technical SpecificationsThe Technical Specifications contained in Appendice...

IP 53053, "Containment Penetrations (Mechanical) Work Observations."

Issue Date: 01/27/84 - 1 - 53053 NRC INSPECTION MANUAL DQASIP INSPECTION PROCEDURE 53053 CONTAINMENT PENETRATIONS (MECHANICAL) WORK OBSERVATION PROGRAM APPLICABILITY: 2512 53053-01 INSPECTION OBJECTIVES 01.01 By direct observation and independent evaluation of w...

Draft of PWR Containment Sump Evaluation Methodology.

NUCLEAR ENERGY INSTITUTEAnthony R. PletrangeloSENIOR DIRECTOR RISK REGULATIONNUCLEAR GENERATIONOctober 31, 2003Mr. John N. HannonChief, Plant Systems BranchOffice of Nuclear Reactor RegulationMail Stop O11-AllU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001SUBJECT:...

License Amend Request 91-08 to Licenses DPR-80 & DPR-82, revising TS 1.8, "Containment Integrity," 3/4.6.1, "Containment Integrity" & 3/4.6.3, "Containment Isolation Valves," per guidance in Generic Ltr 91-08.

PGhE Letter No. DCL-91-311ENCLOSUREUNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONn t e atter o))PACIFIC GAS AND ELECTRIC COMPANY))Diablo Canyon Power Plant)Units 1 and 2))Docket No. 50-275Facility Operating LicenseNo. DPR-80Docket No. 50-323Facility Operating LicenseNo....

Forwards "Arkansas Nuclear One Unit 1 Reactor Containment Bldg 10-Yr Surveillance." No abnormal degradation of containment structure indicated.

_ _ - - --- ------- --{Y)L 8& .,,,. ,m'zPg068'40002'1MabLi^yL k,u,e -ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 LITTLE ROCK. AAKANSAS 72203 (501)371.4000 s .~.. . . p.May 30, 1984 -J ||]s. !..'. .V.I CD.'',Cu:; x. ::-1x31CAN058409Mr. John T. CollinsRegional Administrato...

Proposed tech specs re containment spray additive sys retirement.

< -.; .,|-!.e:CONTAINMENT SYSTEMS.iRECIRCULATION FLUID oH CONTROL (RFPC) SYSTEM-;LIMITING CONDITION FOR OPERATIONl!3.6.2.2 The RFPC System shall be OPERABLE with each of the two storage baskets (onewithin the confines of each of the two containment recirculation sumps) contain...

Forwards "Reactor Containment Bldg Integrated Leakage Rate."

.,„ACCELERATED DI UTION DEMONSTION"'SYSTEMREGULATORY INFORMATION DISTRIBUTXON SYSTEM (RXDS)~- -',~ ~ i~ ~ACCESSION NBR: 8910270032 DOC. DATE: 89/10/18 NOTARIZED: NOFACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit1,Rochester GAUTH.NAME AUTHOR AFFILIATIONMECREDY,R.C. Rocheste...

Oyster Creek Secondary Containment Capability Test.

Exelkn®Oyster Creek Generating Station www.exe]oncorp.comRoute 9 SouthP0 Box 388Forked River, NJ 08731Technical Specification 4.5.GOctober 20, 2010RA- 10-077U. S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555 - 0001Oyster Creek Nuclear Generating...

Attachment - Vogtle Unit 4 LAR-17-043 Containment Pressure Analysis.

ATTACHMENT TO LICENSE AMENDMENT NO. 146 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO. 52-026 Replace the following pages of the Facility Combined License No. NPF-92 with the attached revised pages. The revised pages are identified by amendment number and contain mar...

Proposed Tech Specs re containment isolation valves.

u*3. .. '4. ,;3. ... .=ENCLOSURE l'PROPOSED TECHNICAL SPECIFICATION CHANGE'SEQUOYAH NUCLEAR PLANT UNITS 1~AND;2,DOCKET-.NOS. 50-327 AND:50-328':-(TVA-SQN-TS-90 14), ~LIST-0F AFFECTED PAGES:-Unit:1 ', ,3/4 6-19-3/4 -6-20 -.Unit-2:3/4.6-19'' 3/4 6-20''-.>., ,b.1;4.* < pt...4 j' ...

Response to Gap Analysis Summary Report Containment Regulatory Issues.

March 24, 2016 Mr. Thomas Bergman Vice President, Regulatory Affairs NuScale Power, LLC 1100 Circle Boulevard, Suite 200 Corvallis, OR 97330 SUBJECT: RESPONSE TO GAP ANALYSIS SUMMARY REPORT CONTAINMENT REGULATORY ISSUES Dear Mr. Bergman: In a July 31, 2014, letter, ...

Proposed TS 3/4.6.1.7, "Containment Purge Ventilation Sys."

. .ATTACH _ MENT BP_BOPO_ SED _GHANGES_TOAPfENDIX AIECHNICALSP_ECIFICAIlONSEQBFACILITY OPERATING _LIGENSESNPF-3LNPF-66. NPF-72 AND NPF-77Revised Pages3/4 6-113/4 6-12B 3/4 6-2 *B 3/4 6-3|)|* No changes. Included for continuity.ZNLD/2605/4^9305190390 930513PDR ADDCK 05000454P P...

Letter Regards Changes to TS 3.9.4 Containment Building Penetrations.

North Atlantic Energy Service Corporation - North P.O. Box 300 28 Seabrook, NH 03874 l Atlantic (603) 474-9521 The Northeast Utilities System October 11, 2002 Docket No. 50-443 NYN-02089 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D...

Forwards secondary containment leak rate test results.Test satisfactorily performed on 830905,proving containment capable of maintaining less than -.25 inches water w/less than 12,000 containment failure mode of inleakage.

. . .._ _ _ _ _ _ _ _ - _ _ _ .I?.I'..<.TENNESSEE VALLEY AUTHORITY .--CHATTANOOGA, TENNESSEE 374ot400 Chestnut Street Tower II,|m DEC 7P 2 *DLSmber 2, .1983'U.S. Nuclear Regulatory CommissionRegion-IIATTN: James P. O'Reilly, Regional Administrator101 Marietta Street, Suite 290...

0522 - R504B - GE BWR4 Advanced Technology - 6.5 Diff Containment.

General Electric Advanced Technology Manual Chapter 6.5 Primary Containments Rev 1210 6.5-i USNRC HRTD TABLE OF CONTENTS 6.5 PRIMARY CONTAINMENTS ......................................................................... 6.5-1 6.5.1 Introduction .....

Sequoyah, Unit 2, Technical Specifications, Increased Containment Purge Hour Limit.

CONTAINMENT SYSTEMSCONTAINMENT VENTILATION SYSTEMLIMITING CONDITION FOR OPERATION3.6.1.9 One pair (one purge supply line and one purge exhaust line) of containment purge system linesmay be open; the containment purge supply and exhaust isolation valves in all other containment...

Y020130099 - Citizen Power Letter Regarding Beaver Valley Containment Liner Inspections.

CITIZEN POWERPublic Policy' Research Education and AdvocacyNovember 26, 2013Peter Bamford, Project ManagerOffice of Nuclear Reactor RegulationMail Stop: 08B3Washington, DC 20555-0001Dear Mr. Bamford:As you know, during the latest Beaver Valley Unit 1 refueling outage, a breach...

Rev 38 to OP 9C, "Containment Venting & Purging."

_ - - - . - - - - -sNUCLEARPOWERBUSINESS UNITOP 9COPERATING PROCEDURESMAJORRevision 38CONTAINMENT VENTING AND PURGING Januan' 31.1997DateRECORDDSS_COP!Es REQUIRED. USE PBFMin IAW NP I 24 AND DO liQI COMPLETE TICS BLOCKPRocEDue vEamED CURRENT AND CHECKED FOR TEMPORARY CHANGE 5 ...