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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Forwards Rev 16 to "Inservice Testing Program,San Onofre Nuclear Generating Station,Unit 2" & Rev 11 to "Inservice Testing Program,San Onofre Nuclear Generating Station,Unit 3."

Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 R. M. ROSENBLUM July 31, 1991 TELEPHONE MANAGER OF (714) 454-4505 NUCLEAR REGULATORY AFFAIRS U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen: Subj...

LER 93-005-00:on 930126,notified of an air leak on fail-safe accumulator sys for drywell vent valve due to degradation of O-ring seal.Work request generated to replace versa valve. W/930222 ltr.

e Commo.lth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 CWS PMLTR 93-0095 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 February 22, 1993 Licensee Event Report 93-005, Docket 050249 is being submi...

Concurs w/intent of Reg Guide 1.97,Revision 2.Design & procurement of matls for changes will begin immediately. Study underway to determine performance of thermocouples at various locations.

ACCESSIO,V( iV(3R:F A C IL(5 0:-38750:-388AUTHI,NAMEICURTI6P,V(. H ~REC IP ~ VAMEISCHWENCERPA»,0~REGUL'A(TORY INFORMATIOV O'ISTR'IBUT»ION SYSTEM» (RIOS)8111180411» OOC ~ OATEI: 81/11/13 NOTARIZED;'VO OOCKEIT( 4Susquehanna» Steam; E'1ectr ii c Stationi Uni ti 1

LER 90-015-00:on 900910,reactor scram occurred due to spurious trip signal from steam leak detection sys temp switch.Caused by equipment failure.Temp switch TTS-25-216D was replaced.W/901010 ltr.

,10 CFR 50.73TS 6.9.2PHILADELPHIA ELECTRIC COMPANY !*LIMERICK GENER ATING ST ATIONP. O. BOX A,SAN ATOG A. PENNSYLV ANI A 19464(218) 3271200 amt,2000October 10, 1990u. a. ugo =, c,x.3..,. .,,,,u................,,....50-353License Nos. NPf-39'NPF-85;U.S. Nuclear Regulatory Commi...

Forwards responses to NRC questions resulting from review of TS Change Request 54.Revised TS pages also encl.

SAXTON NUCLEAR EXPERIMENTAL CORPORATION*"uE)GENERAL P U B LIC UTILITIES SYSTEM'- 'SNEc.Jersey Central Power & bgnt Company.qyPennsy#vania Electne CompanyPE JcMenoontan Edison CompanyMAIUNG ADDRESS.TELEPHONE:1 Upper Pond Rd.C301-93-2008 (201) 316-7000Parsippany, NJ 07054SEC-93-...

LER 94-015-00:on 940909,missed TS 4.0.5 surveillance on MS drain (MSD) valves due to inadequate procedure.MSD valve stroke tests performed & procedures governing repetitive task sheets will be revised.W/941011 ltr.

...po.,NOrt.l1North Atlantic Energy Service CorporationP.o. nox 300'AtlanticSeabr k, NII 03874L (603) 474-9521, Fax (603) 474-2987The Northeast Utilities SystemTed C. FeigenbaumNYN- 94114Senior Vice President 3.Chief Nuclear OfficerOctober 11,1994United States Nuclear Regulato...

Application for amend to license DPR-35 re proposed TS change to standby gas treatment & control room high efficiency air filtration sys requirements.

_ - _ _ . . - - _ --- - -- -- .'. ,10CFR50.90G|Boston EdisonPdgom Nuclear Power StatonRocky HJi RoadPlymouth, Massachusetts 02360|L. J. OHvierVice President Nuclear operationsand station OnectorSeptember 6,1994||BECo Ltr. #94-099U.S. Nuclear Regulatory CommissionAttention: Doc...

First set of CP interrogatories & request to produce.

. . _ . .. - -- . .- - .,.,'AY9,QfE0j,APR -7 p3;g,April 7, 1983|,.._:~e_1 _a r! UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION- L iATOMIC SAFETY AND LICENSING BOARD|'Before Administrative Judges:4FMarshall E. Miller,-ChairmanliGustave A. Linenberger, Jr.4Dr. Cadet H. Ha...

Proposed tech specs adding "-89" after ASTM D3803 in testing requirements specified for SGTS & MCR filter sys charcoal & changing test temp for testing SGTS charcoal from 80 C to 30 C.

. ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___*..Attachment 2to U-602302LS-91-023 .Page 1 of 6Current TechnicalSpecifications Marku...

Callaway Plant, Unit 1, Revision OL-23 to Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems.

CALLAWAY - SP3.0-iTABLE OF CONTENTSCHAPTER 3.0DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, ANDSYSTEMS....................................................................................................... 3.1-13.1 CON...

Tech Spec 2.1.1 for operable components. PROBABLE DELETE:DUPE OF 8011180461.

__ . .. - ..3./-...- 2. 0 LIMITING CCNDITIONS FOR OPERATION2.1 Reactor Coolant System2.1.1 Operable ComponentsApplicabilityApplies to the operable status of the reactor coolant systemcomponents.' Objective'To specify certain conditions of the reactor coolant system'components....

LER 93-001-00:on 930226,requirements of TS 3.3.7.5 were not met due to vendor failure to design flywheel & unexplained capped constant bleed drain on air tank resulting in high compressor current.Labels installed.W/undated ltr.

, __ _ . _!!!U-602119:!L45-93(04-12)-LP*I P werCompany-.Clinton Power StationP.O. Box 678a'Clinton, IL 61727l Tel217 935-8881;ILLIN9tS'P(wWER|r10CFR50.73;,Docket No. 50-461Document Control' Desk,Nuclear Regulatory Commission iWashington, D.C. 20555'Subiect: Clinton Power Stati...

Rept of util investigation & resolution of issues identified as potential unreviewed safety questions in IE 801211 ltr.

. - . _- - .. _-. -- .,,.- .|||UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSION||In the Mattar of ))lJ.ONSCLIDATED EDISON COMPANY OF )Docket Nc. 50-247'NEW YORK, I riC . ' Indian Point, Unit )No. 2) ),;I,4i'o# PORT OF CONSOLIDATED EDISCN'S'INVESTIGATION AND RESOLUTICN OF....

LER 89-015-00:on 891223 & 24,problem w/reactor protection sys (RPS)/uninterruptable power supply static inverter caused loss of power to RPS panel.Caused by failure of gate drive boost card.Isolations reset.W/900119 ltr.

n_10 CFR-50.73.',.' *.PHILADELPHIA ELF.CTRIC COMPANY-LIMERICK GENER ATING STATIONP. O. BOX AS AN ATOG A. PENNSY LV ANI A 19464(215) 3271200 Ext. 2000u. a. ucco nuic x, s.., e.c.January 19,'1990.......,7'.".'.".'",'.'..**.......Docket No. 50-353I. License No. NPF-85U.S. Nuclear...

LER 98-004-00:on 981120,failure to perform surveillance within required time interval,was determined.Caused by leaking vent valve.Engineering personnel evaluated alternative methods for performing channel check.

*..NRC FORJ 366 U.S. NUCLEAR REGULATORY COMMISSIONAPPROVED BY OMB NO. 3150-0104 EXPIRES e6/322001action [eqNs750N R ps' lea t ed s erLICENSEE EVENT REPORT (LER) N *a' E *rh'*y3'3y M ' E 5 E'M M .'WE Db 5-0001. er o Pa Red rha g ts/chara fo e bo a co oerhred to res tDe$ on $11'...

LER 98-020-01:on 980609,inadequate flow balancing of shutdown water sys resulted in less than required flow to water sys loads.Caused by inadequate initial design.New SX min flow path for Div I & II SX pumps has been established.

i]NRC FQ1M 308U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS ND 3150-0104 EXPRES 08/30/2001+'-a- to, .n- -UCENSEE EVENT REPORT (LER)10|2"'"*"'JO.e"n'!|*|n"d' ||'"r"d|||Te's"'.",s ,*8Esolenses to the Resonis Monsgenent Ssaneh (T 4 F33L U.S. NusherRegimetery Cornrrum.en. Wae...

Forwards M Gibson correspondence re similarities between Chernobyl & US commercial power plants,for response.

: <-. ...' p+ -_|'21Cnifeb Stafes SenafeWASHINGTON. O C. 20510.:July 30, 1986,Office of Congressional Affairs DirectorNuclear Regulatory Commission1717 H Street, NWWashington,iD.C. 20555,i,|;i| Dear Sir:Enclosed please find correspondence that I have receivedfrom Mary Gibson c...

LER 97-024-01:on 970619,discovered violation of TS 4.0.5 re ASME Section XI SRs.Caused by misinterpretation & wrong assumptions.Procedures were revised to require development of repair/replacement plans for snubber replacements.

. - . . . - . - . . . ~ . - - _ - - -.-.--~~_-._...--._n--... .--t:i|NRC FDRM 366U s. NUCLEAR REGULATORY COMMisslON APPROVED BY OMS NO. 3160 0104*'(I 95) .EXPtRES 04/30/98|.'#oE'aW"f8TT'USI 6'oD5955"S' ^?feoE''c''"$Ia'YEi -LICENSEE EVENT REPORT (LER)>L'e"|8 . a s s1 M !" = M i...

Proposed Tech Specs changing surveillance requirements for HPCS pumps.Functional test will verify that each pump operates at flow rate greater than or equal to 50 gpm design flow rate.

__.EMERGENCY CORE COOLING SYSTEMS| 4/5.2.24 HIGH PRESSURE CORE SPRAY SYSTEMLIMITING CONDITION FOR OPERATION.4.2.24.1 The high pressure core spray (HPCS) system shall be operable with: |a. For the high pressure core spray mode:1. Two OPERABLE high pressure core spray pumps, and...

Summary of 870213 meeting w/licensee & other utils re preliminary overview of NUREG-1150, "Reactor Risk Ref Document" & description of plant results.Attendance list & viewgraphs encl.

. _ _ . . - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _-.g,. % UNITED STATES'ENUCLEAR REGULATORY COMMISSION of,; ,1WASHINGTON, D. C. 20666%,*....,/Docket Nos.: 50-327"and 50-328LICENSEE: Tennessee Valley AuthorityFACILITY: Sequoyah Nuclear PlantSUBJECT:HINUTES OF FEBRUARY 13, 1987 MEETI...

Forwards W response to RAI 640.155,Rev 1 (OITS 6055) re basis for concrete-to-steel gap assumed in AP600 WGOTHIC evaluation model.Response closed item,from W perspective.

;e.,Westinghouse Energy Systemsax355Electric CorporationPittsburgh Pennsylvania 15230 0355DCP/NRCl343NSD-NRC-98-5667Docket No.: 52-003-,.April 14,1998-Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555ATTENTION: T. R. QUAYSUlljECT:NRC REQUEST FOR ADDIT...

Forwards response to violations noted in insp repts 50-352/97-10 & 50-353/97-10.Corrective actions:appropriate LCO for HPCI sys & unified log entries for suppression pool spray sys reconstructed on 971214.

" ^Jame3D. von SuskNI'Vca Presidmt*Limerick Generating Staton, PEGO NUCLEAR esco snergv cem-v.PO Box 2300A Unit of PECO Energy .sMs11Sanatoga. PA 19464-092061o 718 3000 / Fax 610 718 3008|Pager 1800 672 2285 #0271 ,Internet address: jvonsuskil@peco-energycorn,|-10 CFR 2.201Mar...

Package of six comments opposing petition for rulemaking PRM-50-45,calling for site-specific EPZ instead of current 10-mile EPZ around nuclear plants.

_ . . _ . - . _ _ _ _ _ . _ _ _ _ _. _ _ . _ _.:PE.T_g[3QSecretaryU.S. Nuclear Regulatory Commission,87 FEB 19 P12:40'washington, D.C.20555'Attention:Docketing & Service Branch'Tn,!-Very truly yours,(W .*'*g ,||{MW,.'/}ud4 / f U- y g gf9 n~'",/.f, p,h!'Jiu lh +f CJA, afdCo Mxf...

Informs that 800321 response to 800121 & 0204 inquiries inadequate.Vagueness of Commission majority statement on activities of Special Inquiry Group noted.

ffH6NCTY.OlXTH CONGE E.S$ ,.C.MRLE.8 (O.e.Lt.8y1M I. K. LAD AW t,."It. CMal! M ADe. .- 3, .w. .e. Au . .a.9.e Avs . u,..O.E.7A..EVELES. . . . . . . .u,.-.* * * ....el.rs.x m ol.. ... ;";*, ,",, "**, ";'",,,,'y;"'"",f,, *,'',';"';* "'a'COMMITTEE ON INTERIOR AND INSULAR AFFAIRS,...

LER 96-003-00:on 960204,ESFA occurred due to loss of power to RPS/UPS power distribution panel caused by spurious actuation of underfrequency relay.Replaced relay.W/960305 ltr.

. _ . . . , - , , . - . . . - . - . - - . - . . . . . . _ . . - . . . - . . . _ . .- _- - ._1Limstick Generating Station*..A-vPECO NUCLEAReem %v %ov' -PO Box 2300A UNn or PfCO furacy Sanatoga. PA 19464-092010CFR 50.73:March 5, 1996 ,Docket Nos. 50-352'50-353License Nos. NPF-39...