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McGuire Nuclear Station Units 1 and 2, Technical Specification Bases 3-5-2.

McGuire Units 1 and 2 B 3.5.2-1 Revision No. 116 ECCS—Operating B 3.5.2 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) B 3.5.2 ECCS—Operating BASES BACKGROUND The function of the ECCS is to provide core cooling and negative reactivity to ensure that the reactor core is pro...

Clinton, Unit 1 - Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049.

~Exelton Generation®Order No. EA-12-049RS-1 5-320December 14, 2015U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-000 1Clinton Power Station, Unit 1Facility Operating License No. NPF-62NRC Docket No. 50-461Subject: Revised Final Integrated Pla...

"Application of Advanced Full Scope Simulators to Severe Accident Precursor Training," presented at 1993 simulation multiconference on 930329-0401 in Washington,DC.

- - - _ - - - - ---------------- _ ----- -. .APPLICATION OF ADVANCED FULL SCOPE SIMULATORSTO SEVERE ACCIDENT PRECURSOR TRAINING!R. J. Espinosa, S. E. Johnson,A. T. Shester, R. L. McBethABB Power Plant Controls1000 Prospect Hill RoadWindsor, Ct. 06095Presented at the 1993 Simul...

Application for amend to License DPF-62,revising Tech Spec 3/4.6.5, "Drywell Post-LOCA Vacuum Relief Valves."

k( , '.|yOEe<''i,,i.)rnil\ 9009130024 900831"";PDR ADOCK 05000461 \\ ,3.y p.~..PNVy. . , . . . . . .. .. .. .. . . .- . ..- . . . ..--.; . . , ;... . .. .... . .;. , .' DAS/alh-. Attachmentscc: Regional ~Adminstrator, Region III; US.NRCNRC Clinton-Licensing Project ManagerNRC ...

LER 93-014-01:on 930529,discoverd incomplete logic sys functional testing.Caused by test procedure deficiencies. Surveillance test program improved plan incorporated into improvement program.W/931217 ltr.

C.'James A.MtzP; trick ..Nuclear Power Pl:nt|=P.O. Box 41Lycoming. New York 13093315 342-3840,4 NewYorkPowers orry e. S ai m o n , ar.& Authoritysesieent uaoa9er,Deceber 17, 1993-JAFP-93-0673United States Nuclear Regulatory CommissionDocument Control DeskMail Station P1-137Was...

LER 84-006-00:on 840801,air cooling & purging sys galvanized ductwork & supports improperly coated to mitigate corrosion. Caused by insufficient controls due to ductwork painting designated nonsafety-related.W/840830 ltr.

e-U.S. NUCLEAJd RE!ULATJ.Y COMMISSIONNRC Form 386APOROVED oms No. 3130-4104*,I"'REs. si3iinLICENSEE EVENT REPORT (LER)PAGF ACILITY NAME (1)DOCKET NUMBER (2)North Anna Power Station Units 1 and 2 0 | S | 0 | 0 | 0 |3 |3 18 1 |OF|0 | 7TITLE (esApplication of Unqualified Protecti...

Application for amend to Licenses DPR-57 & NPF-5,revising Tech Specs re listed TMI Action Plan items,per Generic Ltr 83-36.

. , _ . _ _ _ _ _ _ _ _ _ _ _- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -..i |Ge:xqa rous Conv:,''') 333 he dmW AanueI' Atanta Gmg a 30308Timshorc 404 526 7020w ng Mam.snost O*cc Hu 45%. Av..ma Georgs 303C?Georgia Power" *'J. T. Beckham. Jr.vre neset and oeera renay...

FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 2.

.. . ,.. , 7 n n S 7 7°o (l I). tJ CONS'!'iWC1'lON ['iWCJ:l)UJWS j{j:AC1'Oi{ Slil E1.O ~i"\LL. SI.lP FOHN CO;-lS'J'RUCTr.o:," . . " '<.< :./. ; i':... ::.:···.~t~~t t1Il4 ' bciriding :.~;cerdhCBt;~ · ~l.il ; · '< . ' . . ~. '". ' . :. •... .. '-: .-: .... -;';B ' nd>b~'sfg~(l...

Calvert Cliffs, Unit 3, Revision 8 to the Combined License Application Part 5, Emergency Plan. Enclosure 1.

Calvert Cliffs Nuclear Power Plant Unit 3 Combined License Application Part 5: Emergency Plan This COLA Part is completely Site Specific Revision 8 March 2013 2007-2013 © UniStar Nuclear Service, LLC All rights reserved. COPYRIGHT PROTECTED CALVERT...

Applicant's Environmental Report Operating License Renewal Stage Braidwood Station, Units 1 and 2. Appendix F.

Appendix F Severe Accident Mitigation Alternatives Analysis Rev. 2 Braidwood Station Environmental Report This Page Intentionally Blank Braidwood Station Environmental Report Appendix F Severe Accident Mitigation Alternatives Analysis Rev. 2 Byron and Braidwood ...

Applicant's Environmental Report Operating License Renewal Stage, Byron Station, Units 1 and 2. Appendix F.

Appendix F Severe Accident Mitigation Alternatives Analysis Rev. 2 Byron Station Environmental Report This Page Intentionally Blank Byron Station Environmental Report Appendix F Severe Accident Mitigation Alternatives Analysis Rev. 2 Byron and Braidwood Statio...

MUAP-07010-NP-A, (R4), "Non-LOCA Methodology."

Non-LOCA Methodology MUAP-07010-NP-A (R4) Mitsubishi Heavy Industries, LTD. ...

APR1400-E-P-NR-13003-NP, Rev. 0, Appendix-C2, "Severe Accident Accident Analysis Report for Rapid Depressurization," Page C2-13 through End.

KEPCO & KHNP SEVERE ACCIDENT ANALYSIS APR1400-E-P-NR-13003-13KEPCO & KHNP C2-13 Figure 3-8 Containment Nodes at EL. 156’ – 0" Security Related Information- Withheld Under 10CFR2.390KEPCO...

Proposed Tech Specs,expanding spent fuel storage facilities.

TABLEOF CONTENTS (Continuec9Section Title ~Pa e3.03.53.63.73.83.93.103.113.123.133.103.153.163.170.00.10.20.30.00.50.60.7'0;80;9Engineer ing Safety Features.Safety Injection and RHR SystemsEmergency Containment Cooling SystemsEmergency Containment Filtering SystemComponent Coo...

2018/03/06 NRR E-mail Capture - FINAL REQUESTS FOR ADDITIONAL INFORMATION FOR THE SAFETY REVIEW OF THE RIVER BEND STATION LICENSE RENEWAL APPLICATION (CAC NO. MF9757) - SET 12

1NRR-DMPSPEm ResourceFrom: Wong, AlbertSent: Tuesday, March 06, 2018 9:10 AMTo: wmagui1@entergy.comCc: RidsNrrDmlr Resource; RidsNrrDmlrMrpb Resource; RidsNrrPMRiverBend Resource; RidsOgcMailCenter Resource; Wilson, George; Donoghue, Joseph; Sayoc, Emmanuel; Wong, Albert; Min,...

NuScale Power, LLC Response to NRC Request for Additional Information No. 436 (eRAI No. 9435) on the NuScale Design Certification Application.

RAIO-0618-60593NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comJune 25, 2018 Docket No. 52-048U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville ...

Technical Project to Investigate Release Mitigation Strategies.

BWR Mark I and Mark II Studies Evaluation of Strategies for Mitigating Radiological Releases in Severe Accidents: Assumptions, Models, Input, and Data 2 © 2012 Electric Power Research Institute, Inc. All rights reserved. Topics • EPRI’s use of MAAP and MAACS2 to evaluate strat...

Part 03 - Applicants Environmental Report - Standard Design Certification (Rev. 4.1) - Part 03 - Applicants Environmental Report - Standard Design Certification - Section 1.0 - Appendix B (Rev. 4.1)

NuScale Standard PlantDesign Certification ApplicationApplicant's Environmental Report - Standard Design CertificationPART 3Revision 4.1June 2020©2020, NuScale Power LLC. All Rights ReservedCOPYRIGHT NOTICEThis document bears a NuScale Power, LLC, copyright notice. No right to...

LER 93-008-00:on 930505,determined that B train of SBGT sys had been inoperable.Caused by procedure error.C/As included bringing missed surveillances up to date,revising procedures & counselling personnel.W/930603 ltr.

Georgia Power Company40 inverness Center Parkway ,1Post Ofhce Box 129s*.Birmingham, Alabama 35201 ,,Telephone 20s 877-7279|nGeorgia PowerJ. T. Beckham, Jr.%ce President NuclearHatch ProjectT* ' MYD t mm , semJune 3, 1993Docket No. 50-321 HL-3330005544U.S. Nuclear Regulatory Co...

LER 2020-001-00 for Sequoyah Nuclear Plant Unit 2, Ice Bed Inoperable Due to Exceeding Maximum Allowed Ice Bed Temperature

Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 September 16, 2020 10 CFR 50.73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Renewed Facili...

Susquehanna, Unit 2, Technical Requirements Manual

VL. L • J...:> I L. UL. U MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2020-16612 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 10/13/2020 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCU...

Surry, Units 1 & 2, Updated Final Safety Analysis Report, Revision 39, Chapter 11: Radioactive Wastes and Radiation Protection.

Revision 39—09/27/07 SPS UFSAR 11-i 11.1 GENERAL DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11.1-111.1 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...

Millstone, Unit 3, Response to Request for Additional Information Regarding Stretch Power Uprate License Amendment Request, Response to Question AADB-07-0107.

Dominion Nuclear Connecticut, Inc. .5000 Dominion Boulevard, Glen Allen, Virginia 23060 3 i'.."Web Address: www.dom.com January 18, 2008U. S. Nuclear Regulatory Commission Serial No.: 07-0846Attention: Document Control Desk NLOS/MAE: RDOne White Flint North Docket No.: 50-4231...

2008/01/07 Indian Point LR Hearing - Draft RAIs on Structures, Reactor Systems, and Scoping and Screening Methodology

From: Kimberly Green To: ,"MICHAEL D STROUD" Date: 1/7/2008 2:12:13 PM Subject: Draft RAIs on Structures, Reactor Systems, and Scoping and Screening Methodology cc: "Bo Pham" , Donna, Attached are draft requests for additional information related to the Indian ...

Response to Portion of NRC Request for Additional Information Letter No. 160 Related to ESBWR Design Certification Application, Classification of Structures, Systems and Components, RAI Number 3.2-34 S03.

HITACHI GE Hitachi Nuclear EnergyJames C. KinseyVice President, ESBWR LicensingPO Box 780 M/C A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 06-308 Docket No. 52-010Supplement 16April 11,2008U.S. Nuclear Regulatory CommissionDocument Control D...