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Susquehanna, Unit 1 & 2, Revision to Technical Requirements Manual.

Feb. 03, 2014Page1 of 3MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2014-4612USER INFORMATION:GERLACH*ROSEY M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSEY M 02/03/2014LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL C...

2014 Prairie Island Nuclear Generating Plant Initial License Examination Proposed Written Examination - Senior Reactor Operator.

2014 NRC INITIAL LICENSE WRITTEN EXAMSENIOR REACTOR OPERATOR76. P8170L-002 136/015/017 AA2.10/3.7/3.7/3H/YES/P8100/1C3 AOP2/T.S. 3.4.5/2014 ILT NRC S76Given the following conditions: - Unit 1 is in Mode 3, HOT STANDBY. - 11 and 12 RCPs are running. - The RCP ...

Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8.

EnclosureAttachment 8PG&E Letter DCL-1 5-069ATTACHMENT 8Diablo Canyon Power PlantUpdated Final Safety Analysis Report Markup(For Information Only)DCPP UNITS 1 & 2 FSAR UPDATEreleases of radioactive materials to the atmosphere and (2) coping with radiologicalemergencies.2.3.1.4...

Forwards Rev 1 to "Steam Generator Repair Rept for Donald C Cook Nuclear Plant Unit 2."

~.42ACCESSION NBR:FAC IL: 50-31 6AUTH. NANEALEXICHiN. P.REC IP. NAI'LEDENTON> H. R.REGULATORY FORMATION DISTRIBUTION SY N < R IDS),870403021 5 DOC. DATE: 87/03/30 NOTARIZED: NO DOCKETDonald C. Cook Nuclear Pouer Planti Unit 2i Indiana 50500031'UTHORAFFILIATIONIndiana h Nichiga...

Responds to NRC 971126 ltr re violations noted in insp on 970804-0907.Corrective actions:RWST level taps have been moved from discharge line to dedicated instrument area that is not subject to flow effects.

CATEGORY 1REGULAT 5 INFORMATION DISTRIBUTIO YSTEM (RIDS)ACCESSION NBR:9802120299 DOC.DATE: 98/01/30 NOTARIZED:~NO DOCKETFACXL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 0500031550-316. Donald C. Cook Nuclear'Power Plant, Unit 2, Indiana M 05000316AUTH.NAME AU...

Proposed tech specs revised pages re overpressure protection.

ATTACHMENT I Consumers Power Company Pa 1 i sades Pl ant Docket 50-255 PROPOSED PORV TECHNICAL SPECIFICATIONS Revised Pages 15 Pages ,,---- --- --- ----' 9402160232940262 -- :----~DR ADOCK 05000255 PDR PALISADES PLANT FACILITY OPERATING LICENSE DPR-20 APPENDIX A TECHNICAL SPEC...

APR1400-Z-A-NR-14019-NP, Rev. 2, "CCF Coping Analysis".

CCF Coping Analysis APR1400-Z-A-NR-14019-NP, Rev.2 KEPCO & KHNP Non-Proprietary CCF Coping Analysis Revision 2 Non-Proprietary January 2018 Copyright ⓒ 2018 Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd All Rights Reserved CCF Coping Analysis ...

Forwards "Design Assessment Rept," Vol 2,Revision 6.

*+MlSREGULATOR ORMA'TION DISTRIBUTION'(RIDS)AOCE'SSION NBR:8204080375 DOC ~ DATE: 82/00/07 NOTARIZED: NOFACIL:50-387 'Susquehanna Steam Electric Stations Unit 1~ Rennsylva50-388 Susquehanna Steam Electric -Stationi Unit 2i PennsylvaAUTH INANEAUTHOR AFFILIATIONCURTIS' ~N ~ Penn...

Proposed - mPower Design-Specific Review Standard Section 8.4, Revision 0, Station Blackout.

Proposed - For Interim Use and Comment ADAMS Accession No. ML12269A015 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD FOR mPOWERTM iPWR DESIGN 8.4 STATION BLACKOUT REVIEW RESPONSIBILITIES Primary - Organization responsible for the electrical engi...

Toshiba Design Control Document Rev. 1 - Tier 1 - Chapter 02 - Certified Design for ABWR Systems - Section 02.04 - Core Cooling Systems

Core Cooling Systems 2.4-1RS-5146900 Rev. 1Design Control Document/Tier 1 ABWR2.4 Core Cooling Systems2.4.1 Residual Heat Removal SystemDesign DescriptionThe Residual Heat Removal (RHR) System has three separate divisions. The major functions of the RHR System are:(1) Contai...

Nine Mile Point Unit 2 - Final Written Examination with Answer Key (401-5 Format) (Folder 2).

Examination Outline Cross-reference: Level RO SRO Tier # 2 Group # 1 KIA # 400000 K1.01 Importance Rating 3.2 Knowledge of the physical connections and I or cause-effect relationships between CCWS and the following: Service water system Proposed Question: RO Question # 1 The ...

2012/03/22 STP COL - 3-27-2012 STP 3&4 Fukushima Presentation Final DRAFT

1PMSTPCOL PEmailsFrom: Chappell, Coley [ccchappell@STPEGS.COM]Sent: Thursday, March 22, 2012 12:42 PMTo: Wunder, GeorgeSubject: 3-27-2012 STP 3&4 Fukushima Presentation Final DRAFTAttachments: 3-27-2012 STP 3&4 Fukushima Presentation Final DRAFT.pdfGeorge, Attached is a draf...

ANO2-2012-08 DRAFT Outlines.

Revision 0ES-301 Administrative Topics Outline Form ES-301-1Facility: Arkansas Nuclear One Unit 2 Date of Examination: 08/27/2012Examination Level: RO X SRO Operating Test Number: 2012-1Administrative Topic(see Note)TypeCode*Describe activity to be performedA1. ...

Vogtle, Units 1 and 2, License Amendment Request to Revise Technical Specifications to Implement NEI 06-09, Revision 0, "Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications (RMTS) Guidelines."

Mark J. Ajluni. P.E. Southern Nuclear Nuclear Licensing Director Operating Company. Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 SOUTHERN'\' September 13, 2012 COMPANY Docket Nos.: 50-424 NL-12-1344 50-425...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 11 - Radioactive Waste Management - Section 11.3 Gaseous Waste Management Systems

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 4 Page 11.3-111.3 Gaseous Waste Management SystemsFission product gases and radiolytic decomposition gases (including xenon and krypton) are generated in the reactor, dissolve in the reactor coolant, and are transported t...

FOIA/PA-2011-0118, FOIA/PA-2011-0119 & FOIA/PA-2011-0120 - Resp 139 - Partial - Group Letter CY. Part 1 of 3.

pll3( 2.3 3 2Group CY(Records WithheldIn Part)From: Skeen, DavidSent: Saturday, April 30, 2011 10:56 AMTo: Jaczko, Gregory; Casto, Chuck; HOO HocCc: Virgilio, Martin; Borchardt, Bill; Doane, Margaret; Reynolds, Steven; Wittick, Brian;Young, FrancisSubject RE: Steering committe...

FOIA/PA-2011-0118/ FOIA/PA-2011-0119 FOIA/PA-2011-0120 - Resp 44 - Partial - Group AAA, Part 2 of 2.

IDENTIFICATION AND ASSESSMENT OF BWR IN-VESSELSEVERE ACCIDENT MITIGATION STRATEGIESStephen A. HodgeT. S. KressJ. C. ClcvclandM. PetekOak Ridge National LaboratoryOak Ridge, Tennessee 37831The submitted manuscript has been authored bya contractor of the U.S. Govcrnment undercon...

FOIA/PA-2011-0118/FOIA/PA-2011-0119/FOIA-2011-0120 - Resp 134 - Partial, Group CS. Part 2 of 4.

Can you take care of this for me?Angela CogginsPolicy DirectorOffice of Chairman Gregory B JaczkoUS Nuclear Regulatory Commissionanqela. coqqins(..nrc.Qov/301-415-1828From: Hinson, CharlesTo: Coggins, AngelaCc: Roach, EdwardSent: Mon Mar 28 18:48:21 2011Subject: TLD dosimeter...

Edwin I. Hatch, Units 1 & 2, Southern Nuclear Operating Company's Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events....

B. L. "Pete" Ivey Southern Nuclear Vice President Operating Company, Inc. Regulatory Affairs 40 Inverness Center Parkway Post Office Box 1295 Birm ingham, AL 35242 Tel 205.992.7619 Fax 205.992.521 7 February 27, 2013 Docket Nos.: 50-321 NL-13-0214 50-366 U. S. Nuclear Regulat...

AREVA Design Control Document Rev. 3 - Tier 2 Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Appendix 19A

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 3 Page 19A-119A Event Trees for Core Damage Sequences Initiated During Power OperationAppendix 19A presents the event trees that delineate the core-damage sequences for internal events initiated during power operation. T...

Minutes of the ACRS Subcommittee on the AP1000 Reactor, August 16, 2011, Rockville, Maryland.

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 – 0001 October 21, 2011 MEMORANDUM TO: ACRS Members FROM: Weidong Wang, Senior Staff Engineer /RA/ Technical Support Branch, ACRS SUBJECT: CERTIFICATION ...

Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 12 to Updated Final Safety Analysis Report, Chapter 03, Design of Structures, Components, Equipment, and Systems.

DRESDEN — UFSAR Rev. 8June 20093.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMSTABLE OF CONTENTSPage3-i3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1-13.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-13.1.1 Compliance with Draft De...

Dresden Nuclear Power Station, Units 2 & 3, Technical Specification Bases.

Dresden Nuclear Power Station Technical Specification Bases (TS Bases) June 2017 Dresden Nuclear Power Station, Unit 2 and 3 Renewed Facility Operating License Nos. (Renewed) DPR-19 (Unit 2) and DPR-25 (Unit 3) NRC Docket Nos. STN 50-237 (Unit 2) and 50-249 (Unit 3) Dresden 2 ...

Forwards Open Item Rept Forms 8021-8061,issued since last semimonthly rept.

npm~QREGULATORY 'ORMATION DISTRIBUTION S M (RIDS)tACCESSIN NBR: 8211170365 DOC ~ DATE: 82/11/12 NOTARIZED: NO DOCKETFACIL:50-275 Diablo Canyon Nuclear Power Plantg Unit ir Pacific Ga 05000275AUTHBYNAMEAUTHOR AFFILIATIONKRECHTINGq J~E~Stone L webster Engineering Corp,RECIP,NAME...

V.C. Summer, Units 2 and 3 - LAR 17-14: Request for License Amendment and Exemption: Addition of Steam Generator System (SGS) Thermal Relief Valves.

< scE&G@ A SCANA COMPANY ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3 Combined License Nos. NPF-93 and NPF-94 Docket Nos. 52-027 & 52-028 April R. Rice Manager N...