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Wolf Creek Revision to Technical Specification 3.9.4, "Containment Penetrations."

WE *LF CREEK 'NUCLEAR OPERATING CORPORATION Richard A. Muench Vice President Technical Services 'AUG 7 2001 ET 01-0021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station: P1-137 Washington, D. C. 20555 Subject: Docket No. 50-482: Revision to Technical...

NuScale Design-Specific Review Standard Section 6.2.6, Containment Leakage Testing.

ADAMS Accession No. ML15356A388 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD for NuScale SMR DESIGN 6.2.6 CONTAINMENT LEAKAGE TESTING REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of NuScale SMR containment integrity. Seco...

"Reactor Containment Bldg Integrated Leakage Rate Test," final rept.

..li!WATERFORD STEAM ELECTRIC STATIONUNIT NO. 3TAFT, LOUISIANADOCKET NUMBER 50-382REACTOR CCNTAINMENT BUILDINGINTEGRATED LEAKAGE RATE TESTFINAL REPORTPrepared for:LOUISIANA POWER & LICHT COMPANY.Prepared by:YWH RubinEbasco Staff EngineerJ.UhCReviewed by:Joint Test GroupLouisia...

8.2 Thermal Stresses Containment Spray FSAR Section 5 87, Draft.

8.2 Thermal Stresses due toContainment SprayDescription:The containment spray event of October, 1992 resulted in an injection of about 9400 gallons of borated water into the reactor building (RB)atmosphere. The event resulted in a change to the average containment temperature....

Presentation Slides on Shield Building /Containment Delamination.

'2/23/2012SHIELD BUILDING / CONTAINMENTDELAMINATION:DAVIS-BESSE & CRYSTAL RIVERBRYCE LEHMAN - NRR/DLRJIM NEURAUTER - REGION III/DRSDANIEL RICH - REGION II/DRP1Agenda" Davis-Besse Condition & Licensee's Position" NRC's Position on Davis-Besse" Impact on License Renewal" Status ...

Revised Tech Specs 3/4.6.1.6 re containment structural integrity.

- . _ _ _ _ _ _ _.; ..-1,,.!-CONTAINMENT SYSTEMSCONTAINMENT STRUCTURAL INTEGRITYLIMITING CONDITION FOR OPERATION3.6.1.6 The structural integrity of the containment shall be maintained at alevel consistent with the acceptance criteria in Specification 4.6.1.6.APPLICABILITY: Mod...

Crystal River, Unit 3, Containment Delamination Update.

Crystal River Unit #3Cti tDl i ti Udt Containment Delamination UpdateNovember 20th2009Agenda• Introduction• Plant Overview• CR3 Containment Design Features• SGR Opening Sequence & Identification of Delamination Delamination• Investigative Approach• Condition Assessment• Root C...

Amend 94 to License DPR-3,changing Tech Specs by adding containment isolation valves for containment breathing air sys.

.l)YANKEE ATOMIC ELECTRIC COMPANYDOCKET NO. 50-029YANKEE NUCLEAR POWER STATIONAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 94License No. DPR-31.The Nuclear Regulatory Comission (the Comission) has found that:A.The application for amendment by Yankee Atomic Electric Com...

Technical Specification Change Request For ANO-2 Containment Cooling System

Entergy Operations, Inc. 1448&R. 333 -Li UL I'Russellville, AR 72801 Tel 501-858-4888 Craig Anderson Vice President Operations ANO June 29, 2000 2CAN060003 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station OP 1-17 Washington, DC 20555 Subject: Arkansas Nu...

Proposed Tech Spec re reliability of ECCS & containment integrity.

NPF-10/15-353 ATTACHMENT "A" EXISTING SPECIFICATIONS UNIT 2 91070.3 PIDR ")- 1064 p ADOCK 05000361 PEREMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - Tav GREATER THAN OR UAL TO 350OF LIMITING CONOITION FOR OPERATION 3.-2 Two independent Emergency Core Cooling System (...

North Anna, Units 1 & 2, License Amendments 116 & 99, Adding Additional Surveillance Requirements for Butterfly-Type Containment Isolation Valves in Containment Purge Lines.

May 8, 1989Docket Nos.. 50-338 and 50-339 Mr. W. R. Cartwright Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd. Glen Allen, Virginia 23060 Dear Mr. Cartwright:DISTRIBUTION See attache sheetSUBJECT: NORTH ANNA UNITS 1 AND 2 - ISSUANCE OF AMENDME...

0968 - R107P - AP1000 Intro to Diffs - 05.1 - Containment Text.

USNRC HRTD 5.1-i Rev 0111 TABLE OF CONTENTS 5.1 CONTAINMENT STRUCTURE ................................................................. 5.1-1 5.1.1 Introduction ............................................................................................ 5.1-1 5.1.2 Contain...

Discussion of Changes ITS 3.6.3, Containment Isolation Valves.

DISCUSSION OF CHANGES ITS 3.6.3, CONTAINMENT ISOLATION VALVES A.10 CTS 4.6.3.1. .a requires testing of each containment isolation valve that is a weight or spring loaded check valve testable during unit operation every 92 days. The ITS does not contain this Surveillance. This ...

Proposed Tech Spec changes for primary containment leakage testing.

'1'.Ii!ENCLOSURE 1[!BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 1PROPOSED TECHNICAL SPECIFICATION CHANGESPRIMARY CONTAINMENT LEAKAGE TESTING ,REFERENCE NO. 83TSB32@310060066 831003''DR ADOCK 05000324PDR~*.CONTAINMENT SYSTEMSPRIMARY CONTAINMENT LEAKAGELIMITING CONDITION FOR OPERAT...

Proposed Tech Spec Surveillance 4.6.1.2 re containment leakage rates.

.*..ATTACllMENT 2PROPOSED CllANCE TOTECl!NICAL SPECIFICATIONSURVEILLANCE 4.6.1. 2,A1/011 N209103070024 910226PDRADOCK 05000498PPDR __ _ _ _ _ _ _ _ _ _ _ _ _ _- _ _ - _ ____ _ _ _ - _ _-'e.i i AdiUIE~Tl-ST-HL AE 3703PAGE30F- 1.C0%iAINMENT SYSTEMS( COWAINMENT LEAKAGE ''..LMllE_...

Proposed tech specs 3.6.1.1 through 3.6.1.3 re containment sys.

-31i .- ,*Definitions'1.1--!,1.1': DefinitionsL (continued)':' EMERGENCY CORE C00 LING' The ECCS RESPONSE TIME shall 'be that time interval.:SYSTEM (ECCS) RESPONSE~from when-the monitored parameter exceeds.its ECCSlTIMEinitiation setpoint at.the channel sensor until'the ECCS e...

Limerick Unit 1, License Amendment 8 re Secondary Containment Integrity.

March 10, 1988Docket No.: 50-352 Mr. Edward G. Bauer, Jr. Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Dear Mr. Bauer:DISTRIBUTION: Docket File NRC PDR Local PDR PDI-2 Rdg File SVarga BBoger WButler RClar...

Forwards response to 860428 request for info re automatic isolation of containment purge & vent valves on high containment radiation signal.Procedures for venting containment have separate sections for drywell & torus.

Georgia ibwer Company333 Piedmont AvenueAtlanta, Georgia 30308 .k sphone 404 526 6526Mailing Address:Fbst Office Box 4545At|anta, Georgta 30302Georgia PowerL T. Gucwa#4 *U Nt'\"UC F "Manager Nuclear Safetyand LicensingiSL-883 !l2785NJune 26, 1986Director of Nuclear Reactor Reg...

Forwards application for amend to License NPF-14,changing Tech Specs to add several new containment isolation valves to Table 3.6.3-1, "Primary Containment Isolation Valves" to support upcoming mods re containment radiation monitors.

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEMREGULATORY- INFORMATXON DXSTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9004250141 . DOC.DATE: 90/04/17 NOTARIZED: YESFACIL:50-387 Susquehanna Steam Electric Station, Unit,1, PennsylvaAUTH.NAME AUTHOR AFFILIATIONKEISER,H.W. Pennsylvania Pow...

Forwards response to RAI re cement erosion under containment foundation.

__ _. _ _ . . . . _ . _ _ -_ - . _ - _ . _ _ _ __ . _.... g g gy gv vp.y e ., siaison,Shippingport, PA 15077-0004oE E INamm November 7,1996rax$$$$$:$$$u ea OlvisionU. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555-0001Subject: Beaver Valle...

Updates status & confirms 910610 telcon notification re completion of installation of containment high radiation signal on containment vent line for Unit 2.Containment vent path established per Reg Guide 1.97 & TMI Item II.E.4.2.

3 ,. s*.BALTIMOREGAS AND*ELECTRICCHARLES CENTER * P.0, BOX 1475 * BALTIMORE, MARYLAND 21203 1475Gronot C CntctViet Pac siotN1Nucitan Cwt mov[200aco-44ssJune 14,1991U. S. Nuclear Regulatory CommissionWashington, DC 20555ATTENTION: Document Control DeskSUBJECT: Calvert Cliffs Nu...

"Reactor Containment Bldg Integrated Leak Test."

,*tance criteria for Type B and Type C tests are contained inParagrapi 4. 7. A. 2 (f) . The allowable leatage rates are:a)Double gasketal sealstotal leakage34.4 scfh (10t Lto)9 41 psigb)Testable penetrationsand isolation valves103.2 scfh total (30t Lto)except main stemi17.2 se...

009_05 CONTAINMENT SYSTEM AND OTHER SPECIAL STRUCTURES

TMI-1 UFSARCHAPTER 05 5-i REV. 21, APRIL 2012CHAPTER 5 – CONTAINMENT SYSTEM AND OTHER SPECIAL STRUCTURESTABLE OF CONTENTSSECTION TITLE5.0 CONTAINMENT SYSTEM AND OTHER SPECIAL STRUCTURES5.1 STRUCTURAL DESIGN CLASSIFICATION5.1.1 CLASSES OF STRUCTURES AND SYSTEMS FOR SEISMIC DESI...

"Reactor Containment Bldg Integrated Leak Rate Test Summary Technical Rept."

ARIZONA PUBLIC SERVICE COMPANYPALO VERDE NUCLEAR GENERATING STATIONUNIT NO. 1REACTOR CONTAINMENT BUILDINGINTEGRATED LEAR RATE TESTSUMMARY TECHNICAL;REPORTPREPARED BYWILLIAMD. ROMANARIZONA PUBLIC SERVICE COMPANYOPERATIONS ENGINEERING SECTIONJuly 15, 1986--SSOVSSOi99a6bias 'DR/D...

Section 4, Containment - Versa-Pac Rev 4 August, 2010.

Century Versa-Pac SAR Rev. 4 Page 4-i August 9, 2010 SECTION FOUR CONTAINMENT TABLE OF CONTENTS 4 CONTAINMENT………………………………………………………………..4-1 4.1 Description of the Containment System .......................................................... 4-1 4.2 Containment under Norma...