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Part 21 rept re deficient undersized welds in gas stripper module,mfg by Norwalk Fabricators,initially reported 801008. Util will perform repair if C-E accepts responsibility for repair procedures.

H i lhdGJ 13 .4 T'P',N I /. t FCTv5 6 FN>o A L 6 nlL U4! 8i>>'>>J""PART 21 IDBRIFICATION NO.%-ws-cmC&PAWIRE$nTd%4m'-4 QDAE OF LETER.-dthiD00ETID.Go- %DATE DISTRIBtflEDd5'lticm-ORIGINAL REPORTf__SLPPLDBRARY"DISTRIBLITION:-REACTOR (R))(FLEL CYCLE &SAFEGLIARDS (S)t'ATERIALS (FD*;...

Monthly operating rept for Jan 1981.

..OOPERATING DATA REPORTDOCKET NO. 050-0298DATE Wh - mr 2, 1981COMPLETED BY Paul BallingerTELEPHONE 402-825-3811OPERATING STATUS. N tes1. Unit Name:Cooper Nuclear Station2. Reporting Period:January 19813. Licensed Thermal Power (MWt):23818364. Nameplate P.ating (Gross MWe):778...

Monthly operating rept for Mar 1988.W/880405 ltr.

, ,1.'|., ..'..\.OPERATING DATA REPORT,-,.DOCKET NO. 050-0298*DATE na_ns_nnCOMPLETED BYJ. T. ScheuermanTELEPHONE f an219?s-1811OPER AYING STATUSNotes ~1. Unit Name: .$7ser Nuclear StationMarch 19882. Reporting Perio( .3. Licensed Therual Pown G.!Wt): 2 3 819364. Narneplate Rat...

Monthly operating rept for Feb 1988.W/880307 ltr.

._ .. . . ..'..... .*.OPERAllNG DATA REPORT*DOCKET NO. 50-29DATE 880209COMPLETEDBY S.)HIPPLETELEPHONE ifli)812-8100-OPERAilN3 STATUS................1. Unit hare: Yankee R0we2. ReportingPeriod: January,19883. LicensedthersalPower(NWt):600,4. WaseplateRating(GrossNie): 1655. Des...

Task Order No. 020 Under Delivery Order No. NRC-42-07-036.

ORDER FOR SUPPLIES OR SERVICES PAGE OF PAGESIMPORTANT: Mark all packages and papers with contract andlor order numbers. BPA NO.i.1 21. DATE OF ORDER 2. CONTRACT NO. (If any) 6. SHIP TO:APR 4i 2 j NRC-42-07-036 __________________________3. ORDER NO. MODIFICATION NO. ENCE NO. a,...

Fourth interim deficiency rept re potentially overstressed embedded plates.Initially reported on 820412.Multiple supports attached to plates w/o design review of plate capacity.Preliminary const spec issued.Next rept by 830404.

* ~TENNESSEE VALLEY AuTHORiTY CHATTANOOGA, TENNESSEE 37401 40 Chestmzt Street Toemi II VOR-50-390/82-39, -391/82-36 31.3-5043/8/2-67, -439/82-60 Ycw-5o-56/82-18, -%67/82-18 ET0-50-518/82-18, -520/82-18 U..Nula m 1w 31atory Commission Regan fl Attn: Mr.. Jew P. O'Reilly, Region...

Requests info re number of employees stationed at TMI & qualification of personnel.

*F) .-. _ ._ _. , .I hI t i, L,..,e%$ Y- hw WW pfY $ pi . ."?. ,o e. k * b C'.j'S- **-u , t, <"L ;, ,,%,,,,,.[7 Y, t''"-7 / h t.e,d#L 6[ -w (,,C,,LOf*h/gkfbA I-J-+t,L f -'' ] f, .. s- /; ...' ._..g'g,6 - ((~ . .,. ' p r'!- v a ,y | -_ b4 h_./1.s , ''p $ ,L,,*y n . . - g/) .- -...

AO 73-11-12:during review of Spring 1973 refueling outage Tech Spec update,discrepancy noted in pressure setpoint trip of recirculation pumps.Caused by design error.Design will be changed.

y-/-NI-;% .sNIAGARA MOH AWK POwtR CORPORATIONNIAGARA MOHAWK.)gg,@Og [[ggf 'p'4, soo cme sovavano wesyNgsva cuses v. omoaj go 6g1~November 30, 1973OA'C7[hMr. Donald J. SkovholtAssistant Director For Reactor OperationsDivision of Reactor LicensingU. S. Atomic Energy CommissionWa...

Order (granting hearing request & establishing schedule for submitting hearing file).* FJ Calabrese 970314 hearing request granted.NRC staff directed to file hearing on or before 970508.W/Certificate of Svc.Served on 970408.

8;j. rUNITED STATES OF AMERICA ,NUCLEAR REGULATORY COMMISSION;ATOMIC SAFETY AND~ LICENSING BOARD PANEL. gBefore Presiding Officer.G. Paul Bollwerk, III, Administrative-Judgeg g .g pj gSpecial Assistant:. Thomas D. Murphy, ' Administrative Judge 0FFICE OF SECRETARY00CKETING & S...

Revision 2 to inservice testing program re turbine driven auxiliary feedwater pump recirculation test line.

[] - (8 0 04 290 96bFarley Nuclear Plant Unit 1Inservice Testing ProgramREVISION INSERTION INSTRUCTIONSFebruary 27, 1980Section/Page InstructionValves:-3-55 and 3-101Replace3-102 Add.e- _ - _ _ _ _ . _ ...e-Table V-l Valve Test ProgramSystem flame: Aux. Feedwater S.c. tem Revi...

Submits clarification of impact upon separation criteria by exceptions allowed in 8.3.1.2.19 of FSAR re SER Outstanding Review Item 15 in response to 770114 verbal request.Installation inspected & found acceptable.

- -_ mNRCrenu 195_ U.S. NUCLEAR REGULAT@HY COMMISSION DOCKET NUMCE R,!unsn50-3 %|,_# " ' " " " " " ' ".,,:JRC DISTRIBUTION roR . .RT 50 DOCKET MATERIAL|To: FROM: ATE oF DOCUMENT [J P Stolz Toledo Edison Co1-29-77|Toledo, Ohio' '~DATE RECEIVED--V' L E Roe1 g7 77$LETTEH .OnoTon ...

Summary of 841005 meeting w/util re restart before completion of seismic upgrade.

fY$UhA$*MUUUi33 op1NUCLEAR REGULATORY COMMISSION-,,{WASHINGTcN,Dr.20555\...../CFFICE OF THECOMMISSIONEROctober 12, 1984 .:.ItEMORANDUM FOR:FilesFROM:James K. Asselstinewj-SUBJECT:MEETING WITH REPRESENTATIVES OF SOUTHERNCALIFORNIA EDISON--RESTART OF SAN ONOFRE 1.,On October 5,1...

Revised monthly operating rept for Nov 1983.

1NRC MONTHLY OPERATING REPORTDOCKET NO. 50-361UNIT NAME SONGS - 23DATE 12/15/83 (asIrevised 3/15/84)COMPLETED BY C. A. MorrisTELEPHONE (714) 492-7700Ext. 56264OPERATING STATUS1. Unit Name: San Onofre Nuclear Generating Station, Unit 22. Reporting Period: 1 November 1933 throug...

"Calculation of X/Q Valves for Control Room Intakes."

PLG-0913CALCULATION OF X/g VALUES FOR THE CONTROL ROON INTAKES Prepared forO.C. COOK PLANTbyPLG, INC.February 19939504140308950407PDR ADOCK 05000315„jPPDR~7479A02229300100500052TABLE OF CONTENTS1.0 Introduction and Summary2.0 Background3.0 Input Data4.0 Calculation of X/l} Val...

Provides info to clarify status of safety-related bldg roofs.Concrete roofs on safety-related bldgs,except reactor bldg,can withstand loads from water buildup up to roof parapets.Screenwell bldg not wholly safety-related.

~7REGULATORY FORMAT'ION DISTRIBUTION SY M (RIDS)ACCESSION NBR; 8511?'10043» DOC~DATE+ 85/1 1/06 NOTARIZED: NO DOCKETFACIL:5g. 410 Nine Mile Point Nuclear Stationi Unit 2< Niagara Moha 05000410AUTH~NAME. AU THOR AFFILIATIONMANGANiC',VS Niagara Mohawk'owerCorp'ECIP,NAMERECIPIENT...

Final rept re deficient welds & base metal in component cooling water heat exchangers,initially reported 810306. Liquid penetrant or magnetic particle exam will be conducted on cracks.Also reported per Part 21.

eI g'; TENNESSEE VALLEY AUTHORITY' 'CHATTANOOGA. TENNESSEE 37401.400 Chestnut Street Tower II _October 6, 1981YCRD-50-566/81-067CRD-50-567/81-04-&fh[w] [)%yx-ElMr. James P. O'Reilly, DirectorOffice of Inspection and Enforcement00T 141981*'U.S. Nuclear Regulatory ca==iasion52Re...

Forwards public version of revised emergency plan implementing procedures,including Procedures EP-201 re technical support ctr activation & EP-25 re radiation protection team activation.

_ _ _i >iir'r,'PHILADELPHIA ELECTRIC COMPANY ,2301 M ARKET STREETP.O. BOX 869911881 1981PHILADELPHIA. PA.19101 %2;MAR 091982>;8.2isi84isoosJosers w attaosen - gggu act. c ..oowerio= oin.m a=, M WEEEE 5g gD-.March 1, 1982Re: Docket Nos. 50-27750-278r,Mr. Harold R.Denton, Direct...

Responds to AEC 720127 ltr re violations noted in Insp Rept 50-302/71-05.Corrective actions:B&W QA investigating documents re decay heat pumps & reactor bldg spray pumps, & new form initiated to record concrete surface defects.

_ _ -.WM'.mF LO RIL . POWERC O R P 0 H AT. J N~-..~ ''sr. rzrensneno rr.oninAv..February 21, 1972..United States Atomic Energy CommissionDivision of ComplianceRegion 2Suite 818230 Peachtree Street, NorthwestAtlanta, Georgia 30303Attention: Mr. John G. DavisDirector,f4&cs RfCaV...

LER 80-054/03L-0:on 800628,while testing control rods, position 30 for rod 46-11 & positions 12,13,16,17 & 19 for rod 14-35 did not indicate.Caused by defective reed switch for rod 46-11 & loose probe connector on rod 14-35.

r m, c um . . . . . . . - - . .... . .-.. - . -(7 77). . . 'LICENSEE EVENT REPORT*, ,,mCONTROL SLOCK: | | | 1 1 I I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI*I 6l o l i l I N I C l 3 | E l P | 1 |@|0 10 | - | 0 | 0 | 0 | 0 | 0 | - | 0 l o |@| 4 |1 |1 !1|1|@||l@7 8 9 LICE...

LER 82-134/03L-0:on 821201,primary containment atmosphere oxygen analyzer,1-CAC-AT-1263-2,indicated step increase in drywell oxygen concentration.Caused by 1262-2 analyzer experiencing instrument zero shift.Analyzer recalibr.

, ~ - ~-- -N ;C rOH,M 366-U.S. NUCLEC2 REGULAT;RY COMMISS8'Q.11)LICENSEE EVENT REPORT, , .CONTROL 8LOCX: || ]]| |lh(PLEASE PRINT OR TYPE ALL REQUIRED INFORMAh0N)jo |1| N | "| B | E | P | 1j@| 0 | 0 | - | 0 | 0 | 0 | 0 | 0 |- | 0 | 0 |@| 4 |1 |1 |1 | 1 |@|||@'3 9 UCE. SEE CODEi...

LER 82-079/03L-0:on 820811,control room operator determined by containment sump pump run times,unidentified leakage of greater than 1 gpm.Caused by valve 24GBS & steam generator steam flow trap leaking.

ouJo ~p.77)'LICENSEE EVENT REPORT. . .%CONTROL SLOCK: | | | | | |}h(PLE ASE PRINT C3 TYPE ALL CEOutRED INFORMATION). 8| N | J | S | G |S | 2 |@16 ol o| -| 0| 0] 0| 0] 0| -| Ol 0|@| 4 | 1| 1| 1| 1|@| ' ||go 17 8 9 LICENSEE CODE14 LICENSE NUMSER 26 26 LICENSE TvPg JO67 CAT 66CON...

Indian Point Energy Center - NRC Emergency Preparedness Annual Inspection Report Nos. 05000247/2012501, 05000286/2012501, 05000247/2012502, and 05000286/2012502; NRC Security Annual Inspection Report Nos. 05000247/2012401 and 05000286/2012401.

UNITED STATESNUCLEAR REGULATORY COMMISSIONREGION I21OO RENAISSANCE BOULEVARD, SUITE 1OOKING OF PRUSSIA, PENNSYLVANIA 1940G2713March 18, 2013Mr. John Ventosa, Site Vice PresidentEntergy Nuclear Operations, Inc.Indian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY ...

Revised monthly operating rept for Apr 1985.

,- -~- *. Page 5 of 8P&L CO.PLANT FERFORMANCE DATA SYSTEM PAGE iUN DATE 09/05/85 OPERATING DATA REPORT RPD36UN TIME 09:40:21 ROBINSON UNIT 2DOCKE1 NO. 050-0261COMPLETED DY A. E. SCOTTOPERATING STATUS .ELEPHONE (003)303-4524----------------..--------------1.UGIT NAME: ROBINSON ...

Provides description of containment water level sys,per 810108 ltr commitment.

REGULATORY INFORMATION DISTRIBUTION SYS EM ('RIDS)AGGRESSION NBR:8112300025 DOC ~ DATE: 81/12/23 NOTARIZED; NO DOCKET ¹FACIL:50-315 Donald C+Cook Nuclear Power,Plantr Unit lr Indiana 8 0500031550-316 Donald Co Cook Nuclear Power Plant~ Unit 2r Indiana 8 05000316AUTH,NAME . AUT...

Forwards steam generator insp results from current outage. Results show no new phenomena & verify general denting pattern within predictable limits consistent w/previous insp.Requests permission to return to full power operation.

REGULATORY 'ORMATION DISTRIBUTION SY 4 (RIDS)ACCESSION NBR:8012220301 DOC ~ DATE: 80/12/18 NOTARIZED: NOFACIL:50-251 Turkey Point Plant~ Unit 4~ Florida Power and Light CAUTHBYNAMEAUTHOR AFFILIATIONUHRIGg R,E~Florida Power L Light Co,RECIP ~ NAME RECIPIENT AFFILIATIONEISENHUT,...