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Response to Request for Additional Information Related to Request to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination.

NMCCommitted to Nuclear ExcellecPalisades Nuclear PlantOperated by Nuclear Management Company, LLCOctober 11, 2005 10 CFR 50.55aU.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Palisades Nuclear PlantDocket 50-255License No. DPR-20Response to Re...

Final As-Administered Scenarios for the Monticello Initial Examination - February 2007.

QF-1030-19 Rev. 5 (05/12/05) Retention: Life of policy + 10yrs. Retain in: Training Program File Page 1 of 24 Appendix D Scenario Outline Form ES-D-1 Facility: ____MNGP__________ Scenario No.: NRC-01 Op-Test No.: MNGP-07Examiners: ____________________________ Operator...

IR 05000373-07-007 (DRS); 05000374-07-007 (DRS); on 4/23/2007 - 5/04/2007 and 5/14/2007 - 5/18/2007, LaSalle County Station, Units 1 and 2; Evaluation of Changes, Tests, or Experiments (10 CFR 50.59), and Permanent Plant Modifications.

June 4, 2007Mr. Christopher M. CranePresident and Chief Nuclear OfficerExelon NuclearExelon Generation Company, LLC4300 Winfield RoadWarrenville, IL 60555SUBJECT: LASALLE COUNTY STATION, UNITS 1 AND 2NRC EVALUATION OF CHANGES, TESTS, OR EXPERIMENTS, ANDPERMANENT PLANT MODIFICA...

Westinghouse AP1000 Design Control Document Rev. 16 - Tier 2 Chapter 11 … Radioactive Waste Management … Section 11.2 Liquid Waste Management Systems

11. Radioactive Waste Management AP1000 Design Control Document Tier 2 Material 11.2-1 Revision 16 11.2 Liquid Waste Management Systems The liquid waste management systems include the systems that may be used to process and dispose of liquids containing radioactive materi...

RO/SRO Initial Examination and Answer Keys - March 2009.

2009 Fermi 2 NRC SRO License Exam QUESTION 1 With the plant operating at 100% power, the following indications exist: • 7D14, GEN SERV H2O HEADER PRESSURE HIGH/LOW alarms • 4D64 GENERATOR H2 COOLERS INLET/OUTLET GAS TEMP HIGH / LOW TEMP HIGH alarms. • Main Generator H2 Coole...

NUREG/CR-5275, "FLAME Facility The Effect of Obstacles and Transverse Venting on Flame Acceleration and Transition to Detonation for Hydrogen-Air Mixtures at Large Scale."

NUREG/CR-5275SAND85-1264R3FLAME FacilityThe Effect of Obstacles and Transverse Venting onFlame Acceleration and Transition to Detonation forHydrogen-Air Mixtures at Large ScaleManuscript Completed: March 1989Date Published: April 1989Prepared byM. P. Sherman, S. R. Tieszen, W....

Draft RAIs for GL2004-02.

1 DRAFT REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2004-02 CORRECTIVE ACTIONS SEABROOK STATION, UNIT NO.1 DOCKET NO. 50-443 By letters dated February 28, 2008 and August 4, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML08...

South Texas Project, Units 3 and 4, Response to Request for Additional Information Letters 148 and 151 Related to Combined License Application Part 2, Tier 2, Subsections 3.2.1 and 3.5.1.5, Respectively.

Nuclear Operating CompanySouth Texas Project Electric Generating Station 4000 Avenue F - Suite A Bay City, Texas 77414 A VVA,-August 6, 2009U7-C-STP-NRC-090096U. S. Nuclear Regulatory CommissionAttention: Document Control DeskOne White Flint North11555 Rockville PikeRockville ...

Ft. Calhoun Unit 1 - Request for Additional Information Related to Extension Date for Corrective Actions re: GL 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors".

January 19, 2006Mr. R. T. RidenoureVice President - Chief Nuclear Officer Omaha Public Power DistrictFort Calhoun Station FC-2-4 Adm.Post Office Box 550Fort Calhoun, NE 68023-0550SUBJECT: FORT CALHOUN STATION, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION RELATED TO EXTENSION ...

Davis-Besse, Unit 1, Environmental Assessment, Related to Application for Exemption to 10 CFR Part 50, Appendix R.

Octobert 15, 1992Docket No. 50-346 Mr. Donald C. Shelton Vice President, Nuclear - Davis-Besse Centerior Service Company c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652 Dear Mr. Shelton: SUBJECT: ENVIRONMENTAL ASSESSMENT RELATED TO AN APPLICATION FOR EXEMPTION ...

Notice of Enforcement Discretion (NOED) for Florida Power and Light Regarding St. Lucie Unit 2.

February 22, 2006Florida Power and Light CompanyATTN: Mr. J. A. Stall, Senior Vice PresidentNuclear and Chief Nuclear OfficerP. O. Box 14000Juno Beach, FL 33408-0420SUBJECT: NOTICE OF ENFORCEMENT DISCRETION (NOED) FOR FLORIDA POWERAND LIGHT REGARDING ST. LUCIE UNIT 2 [TAC NO...

Brunswick Draft SAMA Response 1.h.

Richard Emch - Draft SAMA Response 1.h Page 1From: "Kozyra, Jan" To: "Richard Emch' Date: Wed, Mar 30, 2005 12:24 PMSubject: Draft SAMA Response 1.hThe attached draft response is the item we wish to discuss on Thursdayafternoon.<>CC: "Clements, Talmage" , "Heath, Mike", "Label...

Provides response to NRC RAI on license amend 94-08 re line- item TS improvements to reduce SR for testing during power operation.

PR.IC3'R.IMY'ACCELERATED RIDS PROCESSING)REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9504190123 DOC.DATE: 95/04/14 NOTARIZED: YES DOCKETgFACIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific Ga 0500027550-323 Diablo Canyon Nuclear Power Plant, Unit...

LER 97-004-00:on 971024,radiation monitor alarm were noted due to higher than normal radioactive gas concentration resulted in CVI.New R-12 alarm setpoint was maintained for duration of refueling outage.

NRC FORM 366r4-95)U.S. N R REGULATORY COMMISSIOLICENSEE EVENT REPORT (LER)(See reverse for required number ofdigits/characters for each block)APP ED BY OMB NO. 3150-0104EXPIRES 04/30/98ESTIMATED BURDEN PER RESPONSE To COMPLY WITH THISMANDATORY INFORMATION COLLECTION REQUEST: 5...

Submits addl info on maint history of multistud tensioner & justification for continued operation.Floor layout encl.

IREGULA~ INFORMATION DISTR IBUTIOt. SYSTEM (RIDS)ACCESSION NBR: 8803160002 DOC. DATE: 88/03/02 NOTARIZED: NO DOCKETFACIL:STN-50;528 Palo Verde Nuclear Stations Unit ii Arizona Publi 05000528AUTH. NAME AUTHOR AFFILIATIONVAN BRUNT> E. E. Arizona Nuclear PowerProspect< formerly A...

0518 - R304B - GE BWR_4 Technology - 11.6 Service and Instrument Air Systems.

General Electric Systems Technology Manual Chapter 11.6 Service and Instrument Air Systems Rev 09/11 11-6-i USNRC HRTD TABLE OF CONTENTS 11.6 SERVICE AND INSTRUMENT AIR SYSTEM ........................................................ 1 11.6.1 Introducti...

IR 05000171-11-008; on 10/26-10/27/11; Peach Bottom Atomic Power Station Unit 1, Delta, PA.

Docket No. License No. Inspection No. Licensee: Facility: Location: Inspection Dates: Inspector: Approved By: U.S. NUCLEAR REGULATORY COMMISSION REGION I INSPECTION REPORT 05000171 DPR-12 05000171/2011008 Exelon Generation Company, LLC Peach Bottom Atomic Power Station Unit 1 ...

09/01/2011 Agenda for Public Teleconference With Mitsubishi Heavy Industries, Ltd., to Discuss the Review Status and Design Changes Related to the United States - Advanced Pressurized Water Reactor Digital Instrumentation and Controls.

-Meeting Agenda-US-APWR MHI/NRC Weekly DCD Chapter 7 Conference Call September 1, 2011 -Meeting Agenda- US-APWR MHI/NRC Weekly DCD Chapter 7 Conference Call September 1, 2011 7:30 – 9:00 am EDT Room T10-C2 Bridge Line information: Domestic: 888-455-8930 International: 1-21...

Korea Hydro & Nuclear Power Co., Ltd - Revised Response to RAI 235-8275 for Question 12.03-41 (Non-Security-Related Information/Non-Proprietary).

12.03-41_Rev.1 - 1 / 5 KEPCO/KHNP REVISED RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION APR1400 Design Certification Korea Electric Power Corporation / Korea Hydro & Nuclear Power Co., LTD Docket No. 52-046 RAI No.: 235-8275 SRP Section: 12.03 – 12.04 Radiation Protection...

Submits addl info re post-LOCA status of reactor coolant pumps seal cooling,per NRC 850719 request.Rev 1 to Procedure 41EP-12201 re emergency operations encl.

SUBJECT:: Submits addi» info re post LOCA, status of reactor coolantpumps"seal coolinggper NRC 850719 request;Rev 1-toProcedure 41EP 12201 re .emergency operationsencl'ISTRIBUTIONCODE.: AOOID COPIES RECEI)ED»LTR J',ENCI../SIZE;''+''ITLE:'OR'ubmittal: General Distr ibution .NOT...

Informs of participation in GE owners group & disbanding of BWR plant owners group.Forwards summary of responses to TMI-2 Lessons Learned Task Force requirements.Expects to implement items prior to receipt of OL.

REGULATORY FORMATION DISTRIBUTION'4 SY M (RIDS)ACCESSION NBR:8002120580 OOC~ DATE 80/02/06 NOTARIlEDt NOFACIL'Susquehanna Steam Electric Station~ Unit 1~ Pennsy I va0 38 Susquehanna Steam Electric Station< Unit 2i PennsylvaA, TH,N AUTHOR AFFILIATIONCURTISiN ~'6~ Pennsylvania P...

Forwards proposed amend to FSAR re CESSAR iodine removal sys & responses to NRC 830422 ltr.Proposed FSAR amend combined w/responses closes out sump ph issue in SER Sections 6.4 & 15.4.8 & TMI Item III.D.3.4.

REOULATOINFORMATION DISTRIBUTION O«TEM (RIBS)"AOCE'SSION NBR:8306170326'OCBDATEe 83/06/13 NOTARIZED: YES DOCKET0'ACIL:STN~50528 Palo Verde Nuclear Station( Uni,t 1('rizona Publi 05000528STN-.50-529 «Palo Verde Nuclear Station( Uni,t 2( Arizona Publi .05000529'STN 50 530,Palo V...

Revision 3 to steam generator repair rept.Contains responses to requests for addl info.

• • .r• REMOVE v~~ v l. l. ·. viii r ~ . ' ' PALISADES-PLANT SGRR Rev 2 Rev 2 Rev 1 _ . INSERT Rev Rev Rev x ,,,.. · ' Rev 2 .. ,< ; /.J .. , ·•, .. ~·'figure 3-3.:.i'~ --·-~ev ov-1:.:: :l~ .. y~: .. · ;_.. '· Ta-b1e ·4-.~J=2.. · Re-v ··a.Y'· · vi/ vii/ viii~ x Figure 3-3-2 Ta...

LER 86-032-01:on 860825,component cooling water (CCW) flow less than specified in FSAR.Caused by throttling of HX outlet valves.Analysis to determine actual flow requirements for CCW sys completed.W/890323 ltr.

LICENSEE EVENT REPORT (LER) U.&. lllUC\.IAll lllOUU. T'Ot!Y COS •IOlll """'°"ID OM1 llO. J1 I0-01 Oo1 IXl'lllll: It.II• l'ACllJTY .... 111 jllGCICIT -II 111 I ·-· ta PALISADES NUCLEAR PLANT Io 115 1o1o1o1215 15 1 loF 01 3 TITLI It! COMPONENT COOLING WATER FLOW LESS THAN SPECIF...

Calvert Cliffs Nuclear Plants, Units 1 and 2 - Draft Request for Additional Information Regarding Risk-Informed Technical Specification Completion Times (CAC Nos. MF7415 and MF7416; EPID L-2016-LLA-0001).

From: Marshall, MichaelTo: "Stewart, Glenn H:(GenCo-Nuc)"Cc: "Villar, Enrique:(GenCo-Nuc)"; James Danna (James.Danna@nrc.gov)Subject: CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 - DRAFT REQUEST FOR ADDITIONAL INFORMATIONREGARDING RISK-INFORMED TECHNICAL SPECIFICATION COM...