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Monthly operating rept for Jul 1993 for Clinton Power Station,unit 1.W/930809 ltr.

*.-6 - -lilinois Power Company*,Clinton Power Station.P.O. Box 678Clinton. IL 01727Tel 217 935-8881ILLIN 91Su-602171P@WERL3o-93(oa-09>-tF8E.'100cAugust 9. 199310CFR50.36,Docket No. 50-461U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555Subject: Clin...

Proposed Tech Specs 3/4.8.1.1 re ac sources-operating.

Attachment 3to U-602194 .ELECTRICAL POWER SYSTEMS30 I*AC SOURCES - OPERATIf1G,SURVEILLANCE REQUIREMEf1TS (Continued 14.8.1.1.2(Continued),that the other properties specified in Table 1 of ASTH-0975-89 are!met when tested in accordance with the tests specified in ASTM-D975-89.3...

Special rept:on 910404,during surveillance diesel generator 1A reached required voltage & frequency but failed to close & phase undervoltage relay B-C tripped.Cause not determined.Racking mechanism will be inspected & lubricated.

. _ _ _ _ _ _ _U 601834*,** ,v47 91(05-06)LPILLINDIS POWER8E.tooCCLINTON l'OWI It STATION. I'.O. ItON 078. CtlNTON, IL1 INDIS Ul727-007 N. ^1 ELEl'IlON E 12171 Ki5 bM )_May 6, 1991Docket No. 50-461Document Control DeskNuclear Regulatory CommissionWashington, D.C. 20555Subject:...

Special rept:on 940624,inoperabilities of meteorological monitoring instrumentation channels for more than 7 days identified.Personnel worked expeditiously to return meteorological instrumentation to operable status.

4#* r .liknois Power CompanyChnton Power StationP.O Box 678Chnton. IL 61727 ,Tel 217 935-8881ILLIN9ISP44WERE29$(27 12>te8E.100cJuly 12, 1994Docket No. 50-46110CFR50.36Document Control DeskNuclear Regulatory CommissionWashington, D.C. 20555Subject: Special Report: Failure to Re...

Proposed tech specs,replacing MAPLHGR limit factor 0.85 for single recirculation loop operation w/ref to core operating limits rept & correcting number of nozzles in RHR containment spray Train A.

_ _ _ _ _ _ _ ___ -_ - __ . _ _ _ _ - ...lAttachment 1* **jto U-601848Page 3 of f,POWER DISTRIBUT,I.O_N._t lM115,BASES_3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (Continued)b. Model Change1.Core CCFL pressure differential - 1 psi - Incorporate the assumptionthat flow f...

Forwards public version of draft Amend 28 to FSAR,App 13.B, consisting of Rev 2 to Emergency Plan OAP1890.00S.Rev should resolve SER Outstanding Issue 18 (NUREG-0853).

U-0675__ .Elinois Power Company 2 g10- )-L500 south 27TH STREET P. o. BOX S11. CECATUR. ILLINCIS 62525-1805Docket No. 50-461 October 14, 1983___.-Director of Nuclear Reactor RegulationAttention:Mr. A. Schwencer, ChiefLicensing Branch No. 2Division of LicensingU.S. Nuclear Regu...

"Clinton Power Station Annual Radioactive Effluent Release Rept Jan-Dec 1994." W/950426 ltr.

'IIllinois Power Company t- i,Chnton Power StationiP.O Box 678| Chnton. IL 61727Tel 217 9%8881L30 95(04 -26 )LP1 A.120April 26, 1995Docket No. 50-46110CFR50.36a10CFR50, App I, IV.B.1Document Control DeskNuclear Regulatory CommissionWashington, D.C. 20555Subject: Clinton Power ...

Proposed Tech Specs correctly identifying operational condition for which proposed exception to Tech Spec 4.0.4 is applicable re surveillance requirements for source range monitor functions under Tech Spec 3/4.3.6.

- _ _ - _ - _ _ _ _ _ _ _ - _ _ _l*.,.,ATTACHMENT To *'U-601736PaEc 1 of?U-601730LS-87-039Page 16 of 22INSTRUMENTATION3/4.3.6 CONTROL ROD Bt0CK INSTRUMENTATIONL1HITING CONDITION FOR OPERATION,_The control rod bicek instrumentation channels shown in Table..'.3.6-1 3.3.6shall be...

Proposed tech spec 3/4.4.3.1, "RCS Leakage - Leakage Detection Sys."

.. - . . - - ~ _ .|.. p,1:-.) Attachment 2'-...to U-602265 -|..LS.94-005*Page 1 of 2Proposed Clianges to tiieCurrent Teclinical SpeciGcationstt,,B.II1|.)-i'-9403160251 940311PDR ADOCK 05000461'?.PDR:.|..1,Attachment 2to U-602265 i ,' REACTOR C00LAffT SYSTW LS-94-005|3L4 4'.3RE...

Proposed Tech Specs exempting measured Type C leakage rates for feedwater check valves 1B21-F032A & B.

_ _ _ _ - _ - - _ _ _ _. ..' U-601784 * *LS-91-001|;-5-Pane 8 of 11.'(8)Post-Fuel Loadina Initial Test Proonsm (Section 14, SER, SSER 5and SSH 6),Any changes to the initial test program described in Section-14;of the FSAR made in accordance with the provisions of10 CFR 50.59 s...

Forwards SE completed per 10CFR50.59 for reclassification of select containment isolation valves.

k. ]1flhnos Power CompanyChnton Power StationP O. Box 678Chnton, IL 61727..Tel 217 93s-8881;U402191P(wWERt3093(iO413tP!8E.100cjp.p 99{:'. Docket No. 50-461 10CFR50.59iDocument Control Desk|Nuclear Regulatory Commission!Washington, D.C. 20555;Subject: Submittal of Safety Evalua...

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...

LER 94-003-00:on 940415,reactor thermal power level exceeded 100 percent of rate thermal power due to unexpected reactor recirculation system flow control transient.Corrective action:replaced solenoid & controller module.W/940513 ltr.

. - .- - . . ,. . . . . . _ . , -'.lilinois Power Company -* *Clinton Power blatu*P.O. Box 679Citnton, IL 61727 ' ... - .Tel217935 8881. Ext 3200John G. Cooki*Vice PresidentiILLINOISu-602287 -PG/WEREc$ $ *#i1Docket No. 50-46110CFR50.73JGC-072-94Document Control Desk May 13, 19...

Proposed Tech Specs correcting typos & refs to FSAR,testing to be done during initial plant startup & incorporating revised operating power/flow map for two reactor recirculation loop operation.

Att:chment l' . 4to U 601650'-..Page 9 of 38Table 1Affected. Bases PagesifAffected Section,Associated.DoscribedTable or Finure_ Channe Nn=her~EA&R2.2,1, item 11 l' B 2-93/4.1.31".B 3/4 1 23/4.1.4 .l'B 3/4 1 4Table B 3.2.1 1 l''B 3/4 2-3'3/4.2.3.1 'B 3/4'2-5-Figure B 3/4,2,3-1 ...

Proposed Tech Spec 6.2.3.2 re composition of independent safety engineering group.

FAttachm:nt 2to U-601858'.' 2.S-91-015'Page 4 of 5...ADMINISTRATIVf CONTROLS6. 2. 3 INDEPENDENT SAFEiY ENGINEERING GROUP (ISEG).FUNCTIONG. 2. 3.1 The ISEG shall function to examine unit operating characteristics,iiRC issuances, industry advisories, Lic.ensee Event Reports, and...

Forwards LER 90-003-01 re 13 Rosemount transmitters being inoperable due to loose housing covers & broken neck seal. LER revised to update info provided,including licensee contact,C/A & maint work document numbers.

._ _ --_ __- _ilibnois Power Company/Chnton Power Station/ P.o Box 678 e. ,Chnton, IL 61727 .-Tel 217 935-5623Fax 217 935 4632 .tJohn G. Cook"' " "ILLIN91Su$*6IP4WMRu5-95(07 -13 )LP'2C.220JGC-288-95July 13, 1995Docket No. 50-461 10CFR50.73.Document Control DeskNuclear Regulato...

Commonwealth of MA response to MA Governor Ofc of Energy Resources petition to participate as interested state agency in proceeding.Expresses some remarks,but does not object participation.Certificate of Svc encl.

', , -NRC PUBLIC DOCU5ENT E00MUNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARD)In the Matter of ))Docket No. 50-471BOSTON EDISON COMPANY, et al., )"SP)GPilgrim Nuclear Generating Station, ) gUnit 2 )%gr|jaJUN 5197.8 617.-|p-== i...

Responds to NRC 810812 ltr re violations noted in IE Insp Rept 50-461/81-18.Corrective actions:QA engineer trained in implementation of trend analysis procedure.

T'..0981-L/LL/ND/S POWER COMPANY''Q3 (09-09)-L,.'~. 500 SOUTH 27TH STREET, DECATUR. ILLINO!S 62525 -September 9, 1981Mr. John F. Streeter, Acting DirectorEnforcement and Investigation StaffU.S. Nuclear Regulatory CommissionRegion III799 Roosevelt RoadGlen Ellyn, IL 61037Dear M...

Forwards details re organic matls section of SER,per 811202 meeting w/Chemical Engineering Branch.

!'.. , =U-0376_/LLINDIS POWER 00MPANYL30-81 (l2-03)-6500 south 27TH slREET. DECATUR, ILLINOls 62525tDecember 3,1981|Mr. James R. Miller, Chief/hiStandardization & Special Projects Branch/.4h-Division of Licensi19 ]%\I1,Office of Nuclear Reactor RegulationTO Og0g4|U. S. Nuclear...

Responds to Bulletin 88-008,Suppl 3, "Thermal Stresses in Piping Connected to RCS." Detailed analytical review & proposed schedule for implementing required actions scheduled to be completed by 900625.

_ _ . . _ . . . . _ . . . _ _ _ . . . .a e,U- 601623L3 0-90 (03 -16 )-LP-8G.130ILLINDIS POWER COMPANYCLINTON POWEf4 ST ATION P.O box 678. CUNTON. ILL INOIS 61727-JSP-0193-90March 16, 1990Docket No. 50-461U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashing...

Forwards revised emergency response capability implementation plan schedule & submittals to reflect new submittal dates of 850101 for control room review program plan & 850701 for summary rept per Supp 1 to NUREG-0737.

-hd'N4,U-0647Illinois Power Com7054-83(07-05)L500 SOUTH 27TH STREET, P. o. BOX 511, DECATUR. ILLINOl5 62525-1805Docket No. 50-461July 5, 1983Director of Nuclear Reactor RegulationAttention:Mr. A. Schwencer, ChiefLicensing Branch No. 2Division of LicensingU.S. Nuclear Regulator...

"Study of Necessity to Perform ODYN Reanalysis on Clinton Power Station," Revision 1.

. ~ .. .-.,uJA STUDY OF THE NECESSITYTO PERFORM AN ODYN REANALYSIS'' ON CLINTON POWER STATION-.,tf1.4Illinois Power Company! July 9, 1981|,:-,.:')P. G. Breezeel:Staff Engineer l'.Revision 1 |~8111250322 8111d5,PDRADOCK05000g11/20/81.-.-PURPOSE','The purpose of this study.is to...

LER 89-036-00:on 891113,incorrect connection of source to terminals directly below correct terminals caused Div 1 isolation of RCIC sys.Caused by personnel error.Personnel briefed on need to use ladders/stools.W/891213 ltr.

r. .l|*.0*U- 601567!L45 89(12 13)-LP|*,.20.220--|LLIN0/8 POWER 00MPANY',.:i,L December 13, 1989!j,10CFR50.73t.!'Docket No. 50 461'U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555iSubject: Clinton Power Station . Unit 1Licensee Event Reoort No. 89 0...

"Summary Rept on Static,Dynamic & Relaxation Testing of Expansion Anchors in Response to NRC IE Bulletin 79-02."

... . . _ . . . _ . - . _,i|;'SUMMARY REPORT;STATIC, DYNAMIC AND RELAXATION TESTINGOF EXPANSION ANCHORS IN RESPONSE TOiNRC I.E. BULLETIN 79-02Ii,JULY 20,1981O:.,IaeiOIRDOD; G_ - . . . _ . _ _ . _ . _ _ . - _ - . . _ . - _ _ . _ . - . _ _ . . _ _ _ _ - . _ . _ _ _ _ _ _ _ _ . _...

Informs of inability to respond to NRC 830208 request re impact of regulatory backfit cost since util has no operating plant to use as baseline for comparison.Support expressed for backfit evaluation effort.

APR 11 Est. .0982-LILLIN0/S POWER 00MPANYIPCLINTON POWER STATION, P.O. BCx 678. CLINTON. ILLINCIS 61727April 8, 1983Mr. James R. TourtellotteChairmanRegulatory Reform Task ForceU. S. Nuclear Regulatory CommissionWashington, D. C. 20555.Subject: Impact of Regulatory Backfitting...