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Application for Revision Of Certificate of Compliance No. 9235 For The Model NAC-STC (Revision 13A) - Supplemental Information Needed.

February 12, 2014 Mr. Anthony L. Patko Director, Licensing Engineering NAC International 3930 East Jones Bridge Road, Suite 200 Norcross, GA 30092 SUBJECT: APPLICATION FOR THE REVISION OF CERTIFICATE OF COMPLIANCE NO. 9235 FOR THE MODEL NAC-STC (REVISION 13A) – SUPPLEMENT...

03/05/2014, HCVS-WP-01 Dedicated Motive Force Rev. A (NRC Review).

HCVS-WP-01: Hardened Containment Vent System Dedicated and Permanently Installed Motive Force Revision A, March 04, 2014 Purpose The purpose of this paper is to provide an interpretation of NRC Order EA 13-109 element 1.2.6 regarding the requirement that the Hardened Contain...

South Texas Project, Units 3 and 4 - Response to Request for Additional Information.

0Nuclear InnovationNorth America LLC122 West Way, Suite 405NINRLake Jackson, Texas 77%66979-316-3000May 21, 2014U7-C-NINA-NRC- 140010U. S. Nuclear Regulatory CommissionAttention: Document Control DeskOne White Flint North11555 Rockville PikeRockville, MD 20852-2738South Texas ...

Unistar Nuclear - Calvert Cliffs Power Plant Unit 3 COLA (Final Safety Analysis Report), Rev. 8 - 01 FSAR Front Matter

Calvert Cliffs NuclearPower Plant Unit 3Combined LicenseApplicationPart 2: Final Safety AnalysisReportRevision 8March 201© 2007-2012 UniStar Nuclear Services, LLC.All rights reserved. COPYRIGHT PROTECTED2This page intentionally left blank.CCNPP Unit 3© 2007-2012 UniStar Nuclea...

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Revision to Radiological Emergency Response Plan and Implementing Procedures

~ ~ DUKE ~ ENERGY~ January 6, 2020 Serial: RA-19-0474 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Subject: Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Brunswick Nuclear Plant 8470 River Rd SE Southport, NC 28461 10 CFR 50.4(b)...

Forwards addl info re multiple structure amplified response spectra evaluation of piping sys design,per NRC 800725 request.Table 1,identifying status of each problem & basis for acceptability under Phase I effort,encl.

._ . - _ _ _ .w ,.VinorwrA Er.ucrnic ann Powna COMPANYRzenxown,Vamosm ze can61September 26, 1980Mr. Thomas Novak, Assistant DirectorSarial No. 685for Operating ReactorsN0/RMBDivision of LicensingDocket No. 50-338U. S. Nuclear Regulatory CommissionLicense No. NPF-4Washington, D...

Responds to NRC 820121 ltr re violations noted in IE Insp Repts 50-259 81-37,50-260/81-37 & 50-296/81-37.Corrective actions:OI-77 revised to include all mods performed & valve checklist run on radwaste sys.

T,-,. .* *. ..,.TENNESSEE VALLEY AUTHORITYCH ATTANOOGA. TENNESSEE 3740I'400 Chestnut Street Tower II*Marohp,71962 P12 : 5 "U.S. Nuclear Regulatory CommissionRegion IIATTN: James P. O'Reilly, Regional Administrator*101 Marietta Street, Suite 3100'Atlanta, Georgia 30303Dear Mr. ...

"EI Hatch Nuclear Plant Evaluation of Failure of Time Delay Relays in RWCU Differential Flow High Instrumentation During Design Basis Events."

. - .. . .- . _ , _ . . . - - _ - - .. . .-;,-t.:.,.ENCLOSURE 4,*EAS 24 0489-DRF A00 03470l3MAY 1989 1:, .I14.... EDVIN I. HATCH NUCLEAR FIANTt'EVALUATION OF THE FAILURE OF THE TIME DEIAYREIAYS IN THE RWCU DIFFERENTIAL FIAV HIGH .INSTRUMENTATION DURING DESIGN BASIS EVENTS..J.L...

LER 84-019-00:on 840902,ventilation isolation actuation sys started.Caused by operator error during changing of ventilation discharge duct monitor.Monitors returned to normal & sys reset.Procedures under review.W/841002 ltr.

)~.1-U.S. NUCLEA3 4 EOULATORY COMMISSIONNRC Form Je5'APNIOVED Out asO. 3190-C104* * *'a ' * */8""LICENSEE EVENT REPORT (LER)DOCKET NUMBER (2)PAGE (JBFACiLITV NAME mFort Calhoun Station, Unit No.1o Is l o lo t o |2181 5 i |OF| 013TITLE 144|VIAS Actuation! EVENT DATEISI LER asuM...

Forwards Emergency Operating Procedures Insp Repts 50-324/88-200 & 50-325/88-200 on 880926-1007.

-- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _o .UNITED STATES[,# 'g NUCLEAR REGULATORY COMMISSION-'7,pWASHINGTON, D. C. 20555k . . . . . p#February 23, 1989Docket Nos. 50-325, 50-324Mr. E. E. Utley)Senior Executive Vice Presidenti3Carolina Power and Light CompanyP.O. Box 15...

Insp Repts 50-282/87-15 & 50-306/87-14 on 870831-0924.No violations or deviations noted.Major areas inspected: implementation of Generic Ltr 83-28 in areas of equipment classification,vendor interface & post-maint testing.

..,- .3i'O.S. NUCLEAR REGULATORY COMMISSION iILREGION III|!'Reports No. 50-282/87015(DRS); 50-306/87014(DRS)i' Docket Nos. 50-282; 50-306 Licenses No. DPR-42; No. DPR-60|Licensee: Northern States Power Company'414 Nicollet Mall iMinneapolis, MN 55401iFacility'Name: Prairie Isl...

Forwards Rev 2 to "Pump & Valve Inservice Testing Program Plan," in response to Generic Ltr 89-04.

_ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _.: ,f THE CLEVELAND ELECTRIC ILLUMINATING COMPANYP.O. DOX 97 5 PERRY, OHIO 44081 5 TELEPHONE(216) 259-3737 3 ADDRESS-10 CENTER ROADFROM CLEVELAND: 241 1850Serving The Best Loca...

Forwards addl response to Generic Ltr 83-28,Item 1.2, "Post- Trip Review:Data & Info Capabilities," per 860415 telcon. Status of responses to generic ltr also encl.All action items either complete or closed.

vo4N UTILITIESo.n.,.i On,c.. . soie.n s1,.. . e.,iin. Conn cticutv e cue,ncw w semes= cwm-1 .m m.c.es i.ic c ***P.O. BOX 270o e-a .. ia m . cw--H ARTFORD, CONNECTICUT 06141-0270k k J C 3 E,7 ,$'d,(203) 665-5000May 13,1986Docket No. 50-423B12063A05364Office of Nuclear Reactor R...

Proposed Tech Spec Table 3.3.2-3,deleting requirement to perform time testing on various temp switches & thermocouples.

6ENCLOSURE 1 TO NLS-86-081PROPOSED TECHNICAL SPECIFICATION PAGESBRUNSWICK-1TEMPERATURE SENSOR RESPONSE TIME TESTING(85TSB22)6611180257 861113DRADOCK OSOu4(1852NLU/pgp)_ _ _ . _ _ _ _ _ , ._ _ . _ , _ _ . . _ . _ _- _ _ ,..SUMMARY LIST OF REVISIONSBrunswick-1Page No. Descriptio...

Letter informing that the Commission has filed the enclosed "Notice of Proposed Issuance of Amendment to Provisional Operating License" with the Office of Federal Register for publication.

MAR 2 6 1975 Docket No. 50-244 Rochester Gas and Electric Corporation ATTN: Mr. Edward J. Nelson, President 89 East Avenue Rochester, New York 14604 Gentlemen:DISTRIBUTION - NRC PDR ,Local PDR ORB#1 Reading JRBuchanan TBAbernathy KRGoller RAPurple TVWambach SMSheppard SVarga T...

McGuire Nuclear Station, Units 1 & 2, Revised TS Bases Pages.

Mr. T. C. McMeekin Decprber 2, 1994 Vice President, McGu<,_ Site Duke Power Company 12700 Hagers Ferry Road Huntersville, North Carolina 28078 SUBJECT: PROPOSED REVISION TO TECHNICAL SPECIFICATION BASES FOR MCGUIRE NUCLEAR STATION, UNITS I AND 2 (TACS M91006 AND M91007) Dear M...

LER 85-024-01:on 851103,blocking removed from drywell oxygen analyzer lines A & C before valves repaired & tested.Caused by operator failure to ensure inoperable isolation valve properly tested.Blocking restored.W/860602 ltr.

- . - - - - _=a som aosuJ. asuCLazad t eiukAT047 Consasassionape #0vtD Oweneo.asso-oicieLICENSEE EVENT REPORT (LER)' ' * " ' ' ' ' ' ' ' ' ' 'f ACILITY snaast tilDOCRET mwmat A tal PAGE6EPeach Bottom Atomic Power (;rnrion - Unir ')0|6[0[0|0f>|7|7 1 |OF|0 | 4TITLE tesNon-Compli...

Documents status &/or completion of actions committed to in 940429 response to NRC Bulletin 93-002,Suppl 1, "Debris Plugging of Emergency Core Cooling Suction Strainers."

'Ccmmenwsilth Edlien,A 1400 Opus Place-Downers Grove. Illinois 60515,June 17, 1994,Office of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, DC 20555Attention: Document Control DeskSubject: NRC Bulletin 93-02, Supplement 1, DebrisPlugging of Emergency C...

2020/06/23 GEH BWRX-300 SMR TR RAI - Request for Additional Information 9745

From: Franovich, Rani Sent: Tuesday, June 23, 2020 7:32 PM To: GEH-BWRX-300RAIsPEm Resource Subject: Request for Additional Information 9745 Attachments: Letter 4 RAI_9745 Public.pdf Rani Rani Franovich NuScale Design Certification GE-Hitachi BWRX-300 Design Review H...

Proposed revised Tech Specs,Pages 85,93,146,146a,156 & 156a re limiting conditions for operations & surveillance requirements for reactor coolant leakage monitoring sys.

._ - -_a.,. ,-,. . , ... . .TABLE 4.2 EMINIMUM TEST AND CALIBRATION FREQUENCY FOR DRYWELL LEAK DETECTION.Instrument ChannelInstrument FunctionalCalibrationInstrument-TestFrequencyCheck.!|I1) . Equipment Drain Sump Flow Integrator. (1)Once/3 monthsOnce/dayL2)Floor Drain Sump Fl...

Forwards summary rept in response to IE Bulletin 84-03, "Refueling Cavity Water Seal." Failure of seal not concern due to type of seal utilized.

.- - - - - - -pm&-.THE CLEVELANDELECTRIC ILLUMIN ATING COMPANYP.O. box 5000 - CLEVELANo oHlo 44101 - TELEPHONE (216) 622-9800 - |LLUMINATING BLDG. ~ 55 PUBLICSoVAFIEServing The Best Location in the NationMURRAY R. EDELMANNovember 27, 1984vicE PRESloENT PY-CEI/01E-0019 LNUCLEAR...

Forwards public version of Rev 11 to Emergency Plan Implementing Procedure EP R-6, "Radiological Fire" & Rev 13 to EP M-6, "Nonradiological Fire." Encl 2 identifies privacy/proprietary info.W/860807 release memo.

-- - _ _ _ _ _ _ _ _.y m,.IPACIFIC OAS AND E LE C T RIC C O M PANYbOFJ3{77 BEALE STREET . SAN FR ANCISOO, CAUFORNI A 94106 . (415)781 4211 * Twx 910 372 6587July 29, 1986sw . . o. . ,,,,, ,,M1","'.Ume.,PGandE Letter No.: DCL-86-221Mr. John B. Martin, Regional AdministratorU. S...

Responds to NRC 870120 ltr re violations noted in Insp Rept 50-286/86-21.Corrective actions:operators placed switches in automatic,pre-warmup check-off list performed & all equipment demonstrated to be in proper condition.

-.f.DC3 *123 Main StreetWhite F%ns, New Wrh 10601914 681.6240#> NewWrkPbwer C"i"T:seet& AuthorityMarch 10, 1987" ~**IPN-87-014U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Subject: Indian Point 3 Nuclear Power PlantDocket No. 50-286Inspection No....

Forwards addl info re NUREG-0737,Item II.F.1 concerning noble gas effluent monitor,in response to NRC request.Noble gas effluent monitors are powered from ac offsite power. Procedures will be submitted by 811101.

- - _ _ _ _ _ _ _ _ _ _1*.]MISSISSIPPI POWER & LIGHT COMPANYHe| ping Build MississippiEmaMhMidd5P. O. B O X 16 4 0, J A C K S O N, MISSISSIPPl 39205NUCLE AR PRoOUCTIoN DEPA3f MENT\NQ-m2)h g [U.S. huclear Regulatory Commission ogOffice of Nuclear Reactor RegulationWashington, D...

Forwards summary re 30-day integrated gamma & beta doses to control room operators following design basis LOCA from calculations performed by S&W per TMI Item III.D.3.4. Summary provides general methodology,assumptions & data.

* .GPU Nuclear CorporationNNOIM7loo lnterpace ParkwayParsippany, New Jersey 07054-1149(201)263-6500TELEX 136-482Writer's Direct Dial Number:June 17, 1985Mr. John A. Zwolinski, ChiefOperating Reactors Branch No. 5U.S. Nuclear Regulatory CommissionWashington, D. C. 20555Dear Mr....