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Proposed changes to Tech Specs,modifying requirements for reactor water level monitoring to be applicable only for duration of Cycle 10M outage.

__ _ __ __ _ __. _ __ _ _ _ - _ _ _ . _ . _ _ _ _ _ _ _ _ . _ _ _ __ _ __ ___ .__ _ . _,.....,, .TABLE 3.1.1 (CONT'0)v.These functions not required to be operable when the ADS is not required to be operable.!w.These functions must be operable only when irradiated fuel is in th...

Amend to OL application,consisting of Amend 66 to FSAR, revising Chapters 2,3,5,6 & 15.FSAR documentation of items transmitted by LM Mills 800613 ltr & responses to NRC questions encl.

-w ,.s- ' -+ 4 ~' .,.,._* - '.-. :2:p3,q,. ,- .,-v..,i'{ t_],. ',' , w1 j' ' 1 .' *(. ' s-**>s .-3.,n-;,_,,_ __ _''TENNECSEE VALLEY AUTHORITY'>~-', < <,' dHATrANOOGA TENNESSEE 374o1,".4 |, . ,' ,. .J'- P500A Chestnut [ Street Tower IIm.c- , , ;+,*'.* *.-.. . , ,j ,~ '*^', . ,I...

Comment on proposed rule 10CFR50 re acceptability of LWR performance for severe accidents;scope of consideration in safety regulations.Containment venting capability should be encouraged due to importance as strategy in severe accident.

. -. . .- - .-3[ g*f;,w~ ^Qq g a-'['j." * '1-: _- Entergy,w.m,,.r.u. .. ino, o_(6 7 F R W5 0)"-Operations. h.MOPbr.wii

REQUEST FOR PUBLICATION IN MONTHLY FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT NO. 88 TO FACILITY OPERATING LICENSE DPR-66.

December 31, 1984MEMORANDUM FOR: James R. Miller, Chief Distribution Operating Reactors Branch #3 Docket file Division of Licensing NRC PDR LPDR ORB#1 RDG FROM: Steven A. Varga, Chief CParrish Operating Reactors Branch #1 PTam Division of Licensing Sholly file PKreutzer SUBJEC...

Attachment 18 - Exemptions.

ExemptionsESBWRESBWR Pre-application MeetingOctober 12 and 13, 2004ESBWR Pre-application MeetingExemptionsABWR Exemptions• Operating Basis Earthquake (OBE)> App A Part 100 still includes OBE> ESBWR will likely request same exemption as ABWR from the OBE> Implementation of RTNS...

Forwards application for amend to License DPR-26,amending Tech Spec limiting conditions for operation for refueling water storage tank & spray additive tank & refueling water storage tank basis.

Stephen B. Brain Vice President 0Consolidated Edison Company of New York, Inc. Indran Point Station Broadway & Bleakley Avenue Buchanan, NY 10511 Telephone (914) 737-8116May 26, 1989Re: Indian Point Unit No. 2 Docket No. 50-247 Document Control Desk US Nuclear Regulatory Comm...

Responds to IE Bulletin 78-04 re survey & evaluation of EA-170-302 switches.No applicability at facility.

C~74A& 6h~ S'POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRCLE NEW YORK, N. Y. 10019 (212) 397-6200TRUSTEES 'REDERICK R. CLARK CHAIRMAN ;EORGE L. INGALLS VICE CHAIRMAN UICHARD M. FLYNN tOBERT I. MILLONZI VILLIAM F. LUDDYMarch 21, 1978 IPO-69GEORGE T. BERRY GENERAL MA...

Application for amend to license DPR-64,changing frequency of indicating instrument calibrs to accommodate operation w/ 24 month operating cycle,including rev to item 37 of Table 4.1-1 re testing requirements for core exit thermocouples.

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of ) POWER AUTHORITY OF THE STATE OF NEW YORK ) Docket No. 50-286 Indian Point 3 Nuclear Power Plant ) APPLICATION FOR AMENDMENT TO THE OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nu...

E-mail from Saba to Khanna et al., Request for Turkey Point Report on Delamination.

Kuritz, RobertFrom: Saba, Farideh 4 (.Sent: Monday, October 19, 2009 2:52 PMTo: Khanna, Meena; Farzam, Farhad; Manoly, Kamal; Kuntz, RobertCc: Boyce, Tom (NRR)Subject: FYI: Request for Turkey Point Report on DelaminationAttachments: Turkey Point Unit 3 Dome Delamination Report...

Email from F. Saba, NRR to J. Giitter, NRR et al., Crystal River Status.

/Orf, TracyFrom: Saba, FaridehSent: Friday, October 30, 2009 3:01 PMTo: Giitter, Joseph; Howe, Allen; Boyce, Tom (NRR)Cc: Orf, TracySubject: Crystal River StatusFrom PITA on 10/30109:SGRP Outage Activities: Day 34, 12.5 days behind schedule: No Mode. Both trains of spent fuel ...

CP-2012-06 Draft Written Exam Comments.

ES-401 CP-2012-06 Written Examination Review Worksheet Form ES-401-9 Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.] 1. Enter the level of knowledge (LOK) of each question as either (F)undamental...

River Bend Station, Unit 1, Revision 25 to the Updated Safety Analysis Report, Chapter 3, Tables 3.2-1 through 3.11-14.

TABLE 3.2-1 EQUIPMENT AND STRUCTURE CLASSIFICATION Quality(3) Tornado(4)Scope(6)Safety(1)Seismic(2)Assurance Protection of Design(7)Class Category Category Designation Location(5)Supply Detail NotesRevision 3 1 of 34 August 1990 I. Reactor System1. Reactor vessel 1 I ...

Seabrook, Revision 11 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2D. (Part 1 of 2).

SEABROOI( UPDATED FSAR APPENDIX 2D GEOLOGIC BEDROCK LOGS OF BORING IN THE SITE AREA The information contained in this appendix was not revised, but has been extracted from the original FSAR and is provided for historical information. APPENDIX 2D LIST OF BORINGS DONE FOR SEABRO...

Forwards revised detailed calculations re operability of containment vent & purge valves under DBA conditions & correcting data for spring torque vs valve opening angles. Changes discussed during 850128 meeting in Bethesda,MD.

1V123 Main Street: /.' White Fiains, NewYork 10601''.914 681.6800!,.#> NewYorkPbwer="-:& : Authority50e*%=:"*"'!May.3, 1985||JPN-85-40Director of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C.20555*' Attention:Mr. Domenic B/ Vassallo, ChiefOperati...

Calvert Cliffs Final - Section C Operating Exam (Folder 3).

Page 1 of 21 Appendix D Scenario Outline Form ES-D-1 Event Malf. No. Event Type* Event Scenario No.: 1 Facility: Calvert Cliffs 1 81 2 Scenario No.: 1 Op-Test No.: 2008 Examiners: Operators: Turnover: Unit 1 was MOC at 100% for previous 6 months 2 hours ago power was reduced t...

Forwards plant-specific responses to Bulletins & Orders Task Force 790713 long-term questions.Responses will be incorporated in suppl to NEDO-24708, "Addl Info Required for NRC Staff Generic Rept on BWRs."

*._LONG ISLAND LIGHTING COM PANYT... : fLC'O C*faggsfgsfgSHOREHAM NUCLEAR POWER STATIONP.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792, _ . . _ _ _ _ _ _ ,November 21, 1979 SNRC-450Mr. Denwood Ross, DirectorBulletins and OrdersU. S. Nuclear Regulatory CommissionWash...

Safety evaluation approving continued implementation of SPDS required per NUREG-0737,Suppl 1.Addl info requested re human factors review of SPDS & isolation devices used to interface SPDS w/plant.

____ _ __________________ - - - _ - _ _e,UNITS 3 STATS 3| { NUCLEAR REGULATORY COMMISSION,|5WASHING T ON. O. C. 206SS\\.....*\?i,SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION'|PURI CALHOUN STATION UNIT IlmmA PUstTt7DgrinmmmT(MMJE I NO. 50-2H5SAFETY FXWXRrTTIMIT...

Refers to 980501 ltr which provided initial draft rev of industry maint rule guidance document (NUMARC 93-01) aimed at accommodating PRM on 10CFR50.65.Documentation developed for NRC consideration in proceeding w/rulemaking.

- _ _ _ - _ _ _ - - _ - - -,.b1QEINUCLEAR INERGY IN5il1UTE$NWo!th?N$c*." *NUCLEAR GENERATION DNISIONJuly 1,1998Mr. Samuel J. Collins1DirectorjOffice of Nuclear Regulatory RegulationU. S. Nuclear Regulatory CommissionWashington, D. C. 20555-0001!|SUBJECT:Revised Draft of NUMARC...

Fermi 2, License Renewal Application, Page 3.3-2 through Appendix C, Page C-13.

Fermi 2License Renewal ApplicationTechnical Information* Table 3.3.2-5 Emergency Equipment Cooling Water System-Summary of AgingManagement Evaluation* Table 3.3.2-6 Compressed Air Systems-Summary of Aging Management Evaluation" Table 3.3.2-7 Fire Protection - Water System-Summ...

2012 Dresden Nuclear Power Station Initial License Examination Post Written Exam Comments and Resolutions.

DRESDEN 2012-301 NRC WRITTEN EXAM POST EXAM COMMENTS AND RESOLUTIONS I. Question #7 The high pressure sensing line for the core plate D/P instrumentation has a fitting leak of 10 gpm at the transmitter. An ATWS event occurs and SBLC is started. Which of the following desc...

Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Rev. 24, Chapter 14 - Figure 14.3-1 though Figure 14.3-129.

494.ea1-0ChaMOI Sel)n9 QGap 444.400 - ..------1-..... - . - . - . -... - . - . - . -... ~ [BO] ~ ~ft§] Sections (IUS") l5iJ ~ ~ 4:25. 156- '""T"" """"""'=:!===;F"""=i?=="""===r=--t" DC '.!'.le ....,... DC• DC -r 359.321- ·-·~-- .. ·-···-·-·~···--· ............ , ... _ .... . :...

Draft & Final Retake Exam Outlines.

5/21/01 1:25:38 PM Page 1 of 12 NUREG-1021, Revision 8ES-401 BWR RO Examination Outline Form ES-401-2Facility: Cooper Date of Exam: ?/?/01 Exam Level: ROK/A Category PointsTier GroupK1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*PointTotal1 1 2 2 3 3 2 132 2 5 4 3 ...

Commission has issued Amendment Nos. 72 and 70 to Facility Operation Licenses Nos DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units Nos. 2 and 3.

RIGULAIQ0Y D01,KIT ntEUI NSIC TNovak JWetmo NRL PDR ORB#4 Rdg Rlngram BJones L PDR NRR Rdg DVerrelli BSchar TERA-2 - HDenton IE-4 Dockets Nos,6503-277 DEisenhut ACRS-16 and 50-278 RPurple OELDjuisllnSKl RTedesco GLainasMr. Edward G. Bauer, Jr. L, Vice President and General Cou...

Sequoyah, Units 1 & 2, Notice of Consideration, Relates to Application to Amend the Technical Specification 3.7.5.c to Allow an Increase in the Average Essential Raw Cooling Water Supply Header Temperature.

August 22, 1995'-Mr. Oliver D. Kingsley, Jr. President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUBJECT: SEQUOYAH NUCLEAR PLANT, UNITS I AND 2 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDM...