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Submits responses to potential integrated design insp findings for structural disciplines listed on Attachment A. Item reviewed & accepted by NRC,per 840120 telcon.

',.E lsooh!OOOIS a constructorsinc.'Eas" o-m =va.30 South 17th Streetso.no='" o= tLi', ','g;^,Post Office Box 6223'Philadelphia, PA 19101January 20, 1984File: 11.5.2Mr. Robert Shewmaker'U.S. NRC Office of Nuclear Reactor Regulation4350 E.W. Highway.h'East-West TowersF g'JbWest...

Rev 3 to "Submerged Demineralizer Sys," technical evaluation rept & Apps 1-5.

._.Nucim 7gg3sz,.cos,,y3ISSUE DATEAugust 16, 1985EITsD NSR~O NITSDIVISIONTECHNICAL EVALUATIONREPORTFORSubmerged Demineralizer System_b/' /8 6d MMDATECOG ENG?|5| Wd'Y3- |TfD c _.DATERTRO bCOG ENG MGR._ DATEi2735$$!Sogsaggggggggg0g20DOCUMENT PAGE1OFP PDRJ- _ _ _ _ __No.TECHNICAL...

Submits response to violations noted in insp rept 50-155/98-03.Corrective actions:staff reviewed decommissioning surveillance testing on safety-related sys, structures & components.

._. - - _ - - - - . _ - . . __. - _ _ _ _ _ - _ - _ _ _ _ _ _ _ - - _ _ _ - -1-,|. __,W Df*. .A CMS Energy Cimmny Big Rock Point Nuclear Plant Kenneek P. hnners10269 l&31 Nonn Site General ManagerCharlevoix, MI 49720|July 14, 1998Nuclear Regulatory CommissionDocument Control D...

Insp Rept 50-362/87-25 on 870803-28.Two potential violations noted.Major areas inspected:repair activities associated w/ Atmospheric Steam Dump Valve 3HV-8419 & Main Feedwater Isolation Valve 3HV-4048.

.- _ _ _ _ _ _ --- -,-_ _ --- - -%}-,,,,,>;'O. S. NUCLEAR REGULATORY COMMISSIONc REGION V/,,.)J''';#Report No.50-362/87-25"EA-87-174,uDocket No. 50-362>,<'License No. NPF-15i'sLicensee: Southern California Edison Company.,P. O. Bor,800'2244 Walnut Grove AvenueRosemead. Califor...

LER 98-022-01:on 980427,common mode failure of CI check valves was noted.Caused by corroded bushings caused by improper matl selection.Replaced shaft bushings & o-ring bushings w/bushing made of approved matl.W/980701 ltr.

_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . ____ _..eDuquesne Ligit Company Ben;V lley Power Station'Shippingport, PA 15077-0004..RICHARD D. BRANOT (412) 393 7622Division Vice President Fax (412) 393-4905oys nJuly 1,1998L-98-138Beaver Valley...

Proposed Tech Specs re immediate notification requirements of LER sys.

(HBR-06) 3.1.2 Heatup and Cooldown 3.1.2.1 The reactor coolant pressure and the system heatup and cooldown rates (with the exception of the pressurizer) shall be limited in accordance with Figure 3.1-1 and Figure 3.1-2, and are as follows: a. Over the temperature range from co...

AREVA Design Control Document Rev. 3 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.2.2 Component Cooling Water System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 3 Page 9.2-259.2.2 Component Cooling Water SystemThe component cooling water system (CCWS) is a closed loop cooling water system that, in conjunction with the essential service water system (ESWS) and the ultimate heat si...

Responds to request for addl info concerning Monticello individual plant exam submittal per Generic Ltr 88-20.

ACCELERATAD DOCUMENT DISTJ UTION SYSTEM REGULA9Y INFORMATION DISTRIBUTIOW YSTEM (RIDS) ACCESSION NBR:9302220084 DOC.DATE: 93/02/15 NOTARIZED: NO DOCKET # FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTH.NAME AUTHOR AFFILIATION PARKER,T.M. Norther...

Beaver Valley, Unit 2, Updated Final Safety Analysis Report, Revision 21, Section 12, Radiation Protection.

BVPS-2 UFSAR Rev. 14 12-i CHAPTER 12 TABLE OF CONTENTS Section Title Page 12 RADIATION PROTECTION...........................12.1-1 12.1 ENSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS LOW AS IS REASONABLY ACHIEVABLE .........12.1-1 12.1.1 Policy Considerations......

Encl 1 (CoC) to Ltr M V McMahon, AREVA, Inc., re Revision No. 6 of Certificate of Compliance No. 9302, Docket No. 71-9302 (TAC L24893) (NUHOMS-MP197, NUHOMS-MP197HB).

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION(8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1. a. CERTIFICATION NUMBER 9302 b. REVISION NUMBER 6 c. DOCKET NUMBER 71-9302 d. PACKAGE IDENTIFICATION NUMBER USA/9302/B(U)F-96 PAGE PAGES 1 OF ...

Forwards corrected pages of affected ERDS data point library.Changes indicated by sidebar.

CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ACCESSION NBR:9711040023 DOC.DATE: 97/10/27 NOTARIZED: NO DOCKET # FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co. 05000269 50-270 Oconee Nuclear Station, Unit 2, Duke Power Co. 05000270 50-287 Oconee Nuc...

Application for amend to License NPF-43,revising Tech Specs 3/4.3.7.5,3/4.6.6.2 & 3/4/10.5 re list of required instrumentation in order to minimize need for interpretation in Tech Spec 3/4.3.7.5.

.g r-3ei> s-1,. - w -;* 8. Ralph SymeSm We Prekdeett*to .,, e m o.. . w. .,| | M !EdYAT 7 "|iI| ,tN:wenber 15, 1988 iNtC-88-0189 ji!!iU. S. tuclear Regulatory Cennission|Attnt Document Control Desk'Washington, D. C. 20555 ,:References: 1) Fermi 2 [NN: Docket No. 50-341-NN: Lic...

Insp Rept 50-293/88-30 on 881027-1118.No violations noted. Major areas inspected:licensee followup activities re loose anchor bolts in pipe support base plate,safety significance of subj discrepancy & response to Bulletins 79-002 & 79-014.

_ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ . . _ _* s '.' .: ,.,.,,- ...|U.S. NUCLEAR REGULATORY COMMISSIONREGION I.Report No. 50-293/88-30Docket No,'50-293,License No. OPR-35Licensee: Boston Edison CompanyPilgrim Nuclear Power Station3RFD #1 Rocky Hill Road;Plymouth, Massachusetts 023...

Rev 0 to 0096-020-CALC-01, "Callaway Waterhammer Load Calculation."

1. CALCGN 17 R EV.0 j--IA GE (do q-M 4>DOCUMENT APPROVAL COVER SHEETDOCUMENT NUMBER:0096-020-CALC-01Astr eROWN SOVER:DOCUMENT TITLE: Callaway Waterhamer Load CalculationABB IMPELL CORPOMATmNDOCUMENT TYPE:CLIENT:Union Electric Co.X CALCULATION-SPECIFICATION PROJECT:ESW Waterham...

Proposed Tech Specs,revising remote shutdown surveillances & limiting conditions for operation.

0.TABLE OF CONTENTSSCctionSectionPage1.0 DEFINITIONS1. 0-1SAFETY LIMITSLIMITING SAFETY SYSTEM SETTINGS1.1. FUEL CLADDING INTEGRITY2.1. FUEL CLADDING INTEGRITY1.1 -1A.Reactor Pressure >800 psia A. Trip Settings 1.1 -1and Core Flow >10% of RatedB. Core Thermal Power Limit (React...

Callaway Plant Unit 1 License Renewal Application - Request for Additional Information (RAI) Set #7 Responses.

ULNRC-05906 September 20, 2012 Enclosure 1 Page 1 of 28 CALLAWAY PLANT UNIT 1 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION (RAI) Set #7 RESPONSES ULNRC-05906 September 20, 2012 Enclosure 1 Page 2 of 28 RAI 3.1.1.027-1 Background: Licen...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 10 - Steam and Power Conversion System - Section 10.4.9 Emergency Feedwater System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 4 Page 10.4-7310.4.9 Emergency Feedwater SystemThe emergency feedwater system (EFWS) supplies water to the steam generators (SG) to restore and maintain water level and to remove decay heat following the loss of normal fe...

Seabrook, Updated Final Safety Analysis Report, Revision 15, Chapter 11 - Radioactive Waste Management.

SEABROOK STATION UPDATED FINAL SAFETY ANALYSIS REPORT CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT SEABROOK STATION UFSAR RADIOACTIVE WASTE MANAGEMENT Source Terms Revision 11 Section 11.1 Page 1 11.1 SOURCE TERMS The ultimate source of radioactivity for all plant systems a...

Susquehanna, Unit 1, Changes to Technical Requirements Manual.

Jul. 04, 2013Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2013-31838USER INFORMATION:GERLACH*ROSEY M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSEY M 07/04/2013LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL ...

Crystal River, Unit 3, Response to Request for Additional Information to Support NRC Electrical Systems Branch (EEEB) Technical Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527).

kProgress EnergyCrystal River Nuclear PlantDocket No. 50-302Operating License No. DPR-72April 16, 20123F0412-06U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Subject: Crystal River Unit 3 - Response to Request for Additional Information t...

TRM2 - Technical Requirements Manual, Unit 2.

Apr. 30, 2014Page1 of 3MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2014-19653USER INFORMATION:GERLACH*ROSEY M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TPANMMTTTAT, TMFC)RMATTCnmTO: GERLACH*ROSEY M 04/30/2014LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTRO...

AREVA Design Control Document Rev. 6 - Tier 2 Chapter 10 - Steam and Power Conversion System - Section 10.4.9 Emergency Feedwater System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 6 Page 10.4-7410.4.9 Emergency Feedwater SystemThe emergency feedwater system (EFWS) supplies water to the steam generators (SG) to restore and maintain water level and to remove decay heat following the loss of normal fe...

Weekly info rept for wk ending 880325.

'{J'rMarch 30, 1988 ;For: The ComissionersFrom:T. A. Rehm. Assistant for Operations, Office of the EDO |Subject:WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 25, 1988A sumary of key events is included as a convenience to those Connissioners .'who may prefer a condensed version...

Forwards request for 11 exemptions from 10CFR50,App R requirements,supplementing 830826 exemption requests & superseding Rev 0 to App R compliance assessment rept submitted in response to 830725-29 audit deficiencies.

-.* . 1TOLEDOh EDISONJOE VVLUAMS. JnDocket No. 50-346s-- vu n m_. .,tats) 249 e300License No. NFP-314'91 P49 smSerial No. 1255March 6, 1986Mr. John F. Stolz, DirectorPWR Project Directorate No. 6Division of PWR Licensing-BUnited States Nuclear Regulatory CommissionWashington, ...

Brunswick Steam Electric Plant - NRC Integrated Inspection Report Nos. 05000325/2017002 and 05000324/2017002 and Exercise of Enforcement Discretion.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 July 31, 2017 EA-17-123 William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001) Southport, NC 28461 ...