ML17263A637

LER 94-002-02:on 940202,containment Pressure Channels P-947 & P-948 Were Inoperable.Caused by Water Being Trapped in Low Point of Line.Corrective Action:Iron Oxide Scale Was Removed & Sensing Line restored.W/940506 Revised Ltr

ML17263A637
Person / Time
Site:	Ginna
Issue date:	05/06/1994
From:	MECREDY R C, ST MARTIN J T ROCHESTER GAS & ELECTRIC CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-002, LER-94-2, NUDOCS 9405100227
Download: ML17263A637 (18)

Text

ACCELERATED DISTRIBUTION DEMOblSj.RA'i'LON 5 Yd l elvi t t REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9405100227 DOC.DATE: 94/05/06 NOTARIZED:

NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION ST.MARTIN,J.T.

Rochester Gas&Electric Corp.MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244

SUBJECT:

LER 94-002-02:on 940202,Containment Pressure channels P-947&P-948 were inoperable.

Caused by water being trapped in a low point of line.Corrective action:iron oxide scale was removed&sensing line were restored channels.W/940506 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED LTR (ENCL L SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

D A 05000244 D RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: AEOD/DOA AEOD/ROAB/DS P NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME JOHNSON,A AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR/j3SGh.

SPLB BEG FILE 02 N1~F LE Ol L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1=1 1 1 1 D R~ygoqz g(>Lop.D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D D FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27 c ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, Nr~r c'I x 51acc ROCHESTER N.Y.14649-0001 ROBERT C.h<ECREDY Vice Prerident Crone, Nuclcrrr Production TELEottONE aBEa CODE Pre 546.2700 Maj;;:6, 1994 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555

Subject:

LER 94-M2, Re@)sigil'.":,.:,':2>

Containment Pressure Transmitters Inoperable, Due to Blockage of Sensing Line by Corrosion Products, Causes a Condition Prohibited by Technical Specifications R.E.Ginna Nuclear Power Plant Docket No.50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of,"Any operation or condition prohibited by the plant's Technical Specifications", the attached Licensee Event Report LER 94-002, Revisio'j',':;::,::,':2::;::

is hereby r'nMCeMr'rnen w submitted.

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This event has in no way affected the public's health and safety.Very ruly yours, obert C.Mecr y xc: U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector~fc r;" rr 4 Q'r," l,I

P P NRC FORM 366 (5-92)U.S.NUCLEAR REGULATORY CQOIISSIOH PROVED BY Qlg NO.3150-0104 EXPIRES 5/31/95 LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters for each block)ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.ST NUCLEAR REGULATORY COHHISSION, l}ASHINGIOH, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31/0-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FAGILITY NAME (1)R.E~Ginna Nuclear Power Plant DOCKET HQlBER (2)05000244 PAGE (3)1 OF 14i TITLE (4)ContairN}ent Pressure Transmitters Inoperable, Due to Blockage of Sensing Line by Corrosion Products, Causes a Condition Prohibited by Technical Specifications MONTH 02 DAY YEAR 02 94 EVENT DATE 5 YEAR 94 LER NllBER 6 SEQUENTIAL NUMBER REVISION NUHBER--002---'02:: 4'ac'ONTH DAY YEAR REPORT DATE 7 FACILITY NAME DOCKET NUMBER FACILITY NAHE DOCKET NUHBER OTHER FACILITIES INVOLVED 8 OPERATING MQ)E (9)POWER LEVEL (10)N 098 20.402(b)20.405(a)(1)(i)20.405(c)50.36(c)(1) 50.73(a)(2)(iv) 50.73(a)(2)(v) 73.71(b)73.71(c)20.405(a)(1)(ii) 50.36(c)(2) 20.405(a)(1)(iii) X 50.73(a)(2)(i) 20'05(a)(1)(iv) 20.405(a)(1)(v) 50.73(a)(2)(ii) 50.73(a)(2)(iii) LICENSEE CONTACT FOR THIS LER 12 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50'3(a)(2)(x) OTHER (Specify in Abstract below and in Text, NRC Form 366A THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: Check one or more 11 NAME John T.St.Hartin-Director, Operating Experience TELEPHONE NUMBER (Include Area Code)(315)524-4446 CQlPLETE ONE LINE FOR EACH CQlPOHEHT FAILURE DESCRIBED IN THIS REPORT'13 CAUSE SYSTEM COHPONENT MANUFACTURER REPORTABLE TO NPRDS CAUSE SYSTEH COMPONENT MANUFACTURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (If yes, complete EXPECTED SUBHISSION DATE).X NO EXPECTED SUBH I SS I ON DATE (15)HONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten tines)(16)On February 2, 1994, at approximately 1642 EST, with the reactor at approximately 989 steady state power, Control Room operators determined that Containment. Pressure channels P-947 and P-948 were inoperable. Based on post-event review of computer data, this condition was in violation of Technical Specification Table 3.5-2 Action Statements. Immediate corrective action was to defeat the inoperable channels by placing the affected bistables in the tripped condition. The underlying cause of the event was an obstruction in the common containment pressure sensing line for P 947 a-nil P-948Fi'i<1'6'sultiri&gjfro'm 4'..:ll":: '"9!i-: s.:*-ll':-'oi':,,:::!!P!:::,,::!!W!ii,:,".:::::ii ': ':-"-i!ilia::

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Corrective action was taken to clear the obstruction from the affected tubing, leak test the penetration piping and transmitter tubing, and verify the proper operation of P-947 and P-948.Corrective action to preclude repetition is outlined in Section V (B).i NRC FORH 366 (5 92) NRC FORM 366A (5-92)U.S NUCLEAR REGULATORY COWIISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REGUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEH ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMEHT BRANCH (MHBB 7714), U.S.NUCLEAR REGULATORY COMMISSION,'WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NNER 2 05000244 LER NUMBER 6 YEAR SEQUENTIAL 94-002-REVISION PAGE 3 2 OF>3TEXT (If more space is required, use additional copies of HRC Form 366A)(17)PRE-EVENT PLANT CONDITIONS'he plant was at approximately 98'teady state reactor power with no major activities in progress.Instrument and Control (I&C)Department personnel were investigating Containment Pressure channel P-947.This investigation was initiated by a Maintenance Work Request/Trouble Report (MWR/TR)written January 20, 1994 by Control Room operators because the Main Control Board pressure indication for P-947 (PI-947)was observed to be reading slightly lower than the indication for Containment Pressure channels P-945 and P-949 (PI-945 and PI-949), which are also on the Main Control Board.II.DESCRIPTION OF EVENT A.DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES: o June 24, 1992, 1500 EDST: Containment (CNMT)pressure channel P-947 output indication starts to become inconsistent with channels P-945 and P-949, as monitored on the Plant Process Computer System (PPCS).(This is based on post-event review of archived data on the PPCS.)Event date and time.o January 20, 1994: Control Room operators submit MWR/TR on PI-947 Main Control Board indication. o February 2, 1994, 1642 EST: Discovery date and time.o February 4, 1994, 0007 EST: Containment Pressure channel P-947 is restored to operable status.o February 4, 1994, 1536 EST: Containment Pressure channel P-948 is restored to operable status.NRC FORM 366A (5-92) NRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY CAIIISSION L1CENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0'104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140 0104), OFFICE OF MANAGEMENT AHD BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET HIER 2 YEAR 05000244 94 LER HIHIBER 6 SEQUENTIAL -002--REVI SIGH 02 PAGE 3 3 OF 9!4'EXT (If more space is required, use additional copies of NRC Form 366A)(17)B.EVENT: On January 20, 1994, Control Room operators observed that one Main Control Board indication for CNMT pressure, PI-947, was reading slightly lower than the other two indicators, PI-945 and PI-949.They initiated a MWR/TR, for I&C personnel to investigate the difference in readings.On January 21, I&C performed the annual calibration of the channel.The channel (P-947)responded properly to both the electronic checks and to actual pressure signals inserted into the transmitter (PT-947).After reviewing post-calibration trending data and archived PPCS computer traces of CNMT pressure, I&C noticed that channel P-947 was still not tracking consistent with channels P-945 and P-949.Further investigation was conducted on February 2, 1994, to identify if there could be any possible mechanical and/or electrical problems with P-947.On February 2, 1994, at approximately 1612 EST, with the reactor at approximately 98%steady state reactor power, Control Room operators declared channel'P-947 inoperable. The affected bistables were placed in the tripped condition. To verify the operability of the redundant CNMT pressure channels, the operators then caused a small change in CNMT pressure by depressurizing CNMT per operating procedure 0-11,"Control of Mini Purge Exhaust Valves While Depressurizing Containment". I&C personnel monitored test points for CNMT pressure channels P 945 g P 947 P 948)and P-94 9 with a digita l multimeter .During this depressurization, at approximately 1642 EST, two channels (P-947 and P-948)did not show any response to the small change in CNMT pressure.The Control Room operators formally declared P-948 inoperable at approximately 1658 EST.The affected bistables were placed in the tripped condition per emergency restoration procedure ER-INST.1,"Reactor Protection Bistable Defeat After Instrumentation Loop Failure".P-947 and P-948 sense CNMT pressure via a common line (CNMT Penetration 203A).A CNMT entry was made to verify that this sensing line for PT-947 and PT-948, (Pen.203A)was not mechanically blocked.Pen.203A was visually verified not to be externally obstructed. The valve lineups for the pressure transmitters (PT-947 and PT-948)were verified to be correct.HRC FORM 366A (5-92) NRC FORM 366A (5-92)U.s.NUcLEAR REGULATDRY cQel lssloN LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMENT BRAHCH (MNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTOH, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3140 0104), OFFICE OF MANAGEMENT AND BUDGET'WASHIHGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NUMBER 2 05000244 LER NINBER 6 YEAR SEQUENTIAL 94--002--REVI SION 02 PAGE 3 4 OF.34 TEXT (If more space is required, use additional copies of NRC Form 366A)(17)On February 3, 1994, a work package for troubleshooting and repair of the CNMT penetration line was prepared.A CNMT entry was made and Pen.203A was pressurized to thirty (30)pounds per square inches above atmospheric pressure (PSIG), using surveillance test procedure PTT-23.17B,"Containment Isolation Valve Leak Rate Testing Containment Pressure Transmitters PT-947 and PT-948 Pen 203A".PT-947 and PT-948 did not respond to this pressure, which indicated a blockage in the piping for Pen.203A or in the common instrument tubing line.Backflushing with one-hundred-twenty (120)PSIG air supply to clear the blockage was unsuccessful. Pen.203A was isolated inside CNMT to provide double barrier isolation for CNMT integrity. The instrument tubing was disconnected outside CNMT.The instrument tubing was found to contain water, but this water was not the source of the blockage.The 1/2 inch carbon steel tubing for Pen.203A was found to be mechanically blocked with a thick sludge.The blockage was removed.The tubing was reassembled and preparations were made to test the tubing.On February 3, 1994, at approximately 2207 EST, Pen.203A was declared inoperable to perform required Appendix J testing.The Limiting Condition for Operation (LCO)for Technical Specification (TS)3.6.3.1.was entered.Pen.203A was tested in accordance with surveillance test procedure PTT-23.17B,"Containment Isolation Valve Leak Rate Testing Containment Pressure Transmitters PT-947 and PT-948 Pen 203A".It was documented in PTT-23.17B that PT-947 and PT-948 now accurately responded when the penetration was pressurized to 60 PSIG.PTT-23.17B was successfully completed at approximately 2336 EST and Pen.203A was declared operable at approximately 2340 EST.On February 4, 1994, at approximately 0007 EST, P-947 was declared operable.The transmitter and rack calibration procedure for channel P-948 was performed later in the day on February 4, and P-948 was declared operable at approximately 1536 EST on February 4, 1994.HRC FORM 366A (5 92) NRC FORM 366A (5-92)U S.NUCLEAR REGULATORY CQNIISSIOH LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXP I RES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATIOH COLLECTION REOUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEHENT BRANCH (MNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION> WASHIHGTOH, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NUMBER 2 05000244 94--002 02 LER NUMBER 6'YEAR SEOUENTIAL REVISION PAGE 3'5!.:;:.'OF i:.;":;1'4 TEXT (If more space is required, use additional copies of NRC Form 366A)(17)~~>>>>>>>>>>mcgrr~~w~XCwO,.~~~X>>X><<>>~>~,a~,.eocevmOW~yXaxc ..W>>>WZ>ya,. m>>>,<~.>,s.>>~a~m~y g~.~>>>>>>~P,:i.,.': ",:,,",.';,;: q,i'.;;,.:'f; P';'i';:;.'.-'.;.i:;;.'::;x':".,,~n;".'.; a HRC FORM 366A (5-92) ~~ NRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS IHFORMATIOH COLLECTIOH REQUEST: 50.0 NRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMEHT BRANCH (MHBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NIMBER 2 05000244 LER NUMBER 6 YEAR SEQUENTIAL 94--002 REVISION 02 PAGE 3-."I."':.-'$~1'-'EXT (If more space is required, use additional copies of HRC Form 366A)(17)C~INOPERABLE STRUCTURES i COMPONENTS I OR SYSTEMS THAT CONTRI BUTED TO THE EVENT: None D.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: are 8, was SI,)~946 Engineered Safety Features that rely on CNMT pressure inputs Safety Injection Actuation (SI), Steam Line Isolation, and Containment Spray Actuation (CNMT Spray).None of these features was affected by the inoperability of P-947 and P-94 because at no time, from June 24, 1992, to February 4, 1994, CNMT pressure at or near the actuation setpoints (4 PSIG for 18 PSIG for Steam Line Isolation, and 28 PSIG for CNMT Spray During this period, the redundant channels (for P-947 the channels are P-945 and P-949;for P-948 the channels are P-and P-950)were in service and were not taken out of service unless the affected bistables were placed in the tripped d t""":,',, E".",X.;:.V',,';i>jj(i9'),.;!,, CI P'.".'-':"::."": -""'!!!""";,:;: con z tz.onj~<e)('0'epr":.;:,,'"'xol-,';::.::.,'aper'axe%'ai'ei:jr,':,,::'sine;>,"::(ji) i;:,:,:::se'concls': ':on;"::":: 9'8cQmb:eÃ,'l:;:::.'04:.;::::;"':f 99,2,:;":~ E.METHOD OF DISCOVERY: This event was first identified due to the astute observation of a Control Room operator on January 20, 1994, who questioned a slight difference in indications for CNMT pressure.The small deviation between redundant channels was within the tolerance of Main Control Board instrumentation channel checks.The monthly Channel Functional Tests and annual Channel Calibrations associated with these channels (as required by TS Table 4.1-1 for units¹17 and¹25)did not detect the obstructed tubing line due to the location of the obstruction. The sludge was located between CNMT and the root isolation valves for PT-947 and PT-948.These root isolation valves are closed during performance of the necessary tests and calibrations, in order to pressurize the volume between the valve and the pressure transmitter. This method of testing is consistent with the definition of Channel Functional Testing, as defined in TS 1 t 7~3~a~The fact that this event affected both channels P-947 and P-948 was identified as a result of the investigations performed by I&C personnel on February 2, 1994.NRC FORM 366A (5.92) NRC FORH 366A (5-92)U.S.NUCLEAR REGULATORY CQHISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OHB NO.3150-0104 EXPIRES 5/31/95 ESTINATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORNATION COLLECTION REQUEST: 50.0 HRS.FORWARD COHHEHTS REGARDING BURDEN ESTIHATE TO THE INFORHATIOH AND RECORDS HAHAGEHENT BRANCH (HNBB 7714), U.S.NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3110.0104), OFFICE OF NANAGEHEHT AND BUDGET WASHINGTON DC 20503.FACILITY NAHE 1 R.E.Ginna Nuclear Power Plant DOCKET H NBER 2 05000244 LER HIHIBER 6 YEAR SEQUENTIAL 94--002--REVI SIOH 02 PAGE 3 TEXT (If more space is required, use additional coPIes of NRC Form 366A)(17)A more detailed review'of the archived PPCS records of CNMT pressure concluded that channel P-947 had not responded to changes in CNMT pressure since June 24, 1992, beginning at approximately 1500 EDST.Note that while CNMT pressure channel P-947 is monitored by the PPCS, channel P-948 is not.In addition, PI-948 (and also PI-946 and PI-950)have a scale of 10 to 200 PSIA (absolute pressure). By comparison, PI-947 (and also PI-945 and PI-949)have a scale of 0 to 60 PSIG.It is assumed that P-948 had not responded to changes in CNMT pressure for the same amount of time as P-947.F.OPERATOR ACTION: The Control Room operators observed that the PI-947 reading was inconsistent on January 20, 1994, and initiated a MWR/TR.After both channels P-947 and P-948 were discovered to be inoperable, the Control Room operators performed emergency restoration procedure ER-INST.1 and placed the affected bistables in the tripped condition. Subsequently, the Control Room operators ensured that higher supervision and the NRC Resident Inspector had been notified of this event.G.SAFETY SYSTEM RESPONSES: None III.CAUSE OF EVENT A.IMMEDIATE CAUSE: The immediate cause of the event was the failure of P-947 and P-948 to respond to changes in CNMT pressure due to obstruction of the common pressure sensing line.NRC FORH 366A (5.92) NRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY CO}IIISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY QUI NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714)g U ST NUCLEAR REGULATORY COMMISSION>> l}ASHIHGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3150 0104), OFFICE OF MANAGEMENT AHD BUDGET WASHINGTON DC 20503.FACILITY NA}lE 1 R.E.Ginna Nuclear Power Plant.DOCKET NWBER 2 YEAR 05000244 94-002 02 LER NUMBER 6 SEQUENTIAL REVISION PAGE 3 TEXT (If more space is required, use additional copies of HRC Form 366A)(17)B.INTERMEDIATE CAUSE: The intermediate cause of the obstruction of the common pressure sensing line at Pen.203A was a buildup of corrosion products in this line, which is 1/2 inch OD, 0.065 inch wall thickness, carbon steel tubing.These corrosion products were visually examined and found to be reddish brown/black in color, visually resembling iron oxide scale.IL'bj,'s;l::.'bu'iaM) j<.,-.".'.e'f.::,.;Cori:.;epiq'ii:.:'.:;'pro'ducts C.ROOT CAUSE: The underlying cause of the ,,",:...,",;g>>e:,,g:":f*,: g,,"::,.: Calibratian f riO-s',, th>>e:,;:;::,::,".Sp'e'ifi'C SenSing line configuration. Z&C personnel have cali.brated these transmitters with a water-filled deadweight tester for many years.The configuration of the transmitter and sensing line forv'~<Pen'".::.'-.::.',:,203A prevented the drainage of all the water after calibration. After the transmitter was unisolated as part of the calibration process, the trapped water traveled down to the low portion of the sensing li enl:ii':.:h>>,>>ea~rlj!R:::i:, st hvg'A}Amvggv>>>>~hggge~>>gg>>hvg~pg 'va>>>>hghvgv'vgseggg~agvug>>vp'uhv>>AYAH%'&>>&Ah" v>>gev>>>>frigg:A>>vvrgguhvuhpDg>>hvahug&gsh>>hs YAm>>hhug>>A>>>>va+ggvgasgvger gIhae}::ieav>> eA'~i::,:::.'::::.~~sjMRQ@Perf oihrmanceijlxhn>>rigca'togrp>>'& re grege'0'a HRC FORM 366A (5-92) NRC FORH 366A (5-92).S.NUCLEAR REGULATORY CQIIISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORHATION AND RECORDS MANAGEMENT BRANCH (HNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (31i0-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NINBER 2 YEAR 05000244 94 LER NUMBER 6 SEQUENTIAL M--002 REVISION 02 PAGE 3 9;ii,"'OP;:sl%".4I TEXT (If more space is required, use additional copies of NRC Form 366A)(17)Stagnant water hae rema'ined in the carbon steel sensing~ee 5'hajj'i;:,':,':;4'0'i:.':,:.:Pjyi>><i203)"; for a substantial period of time a,f'5ejgje'ajh col'fbi'i%iixi. Under etteh'thp'se conditions, significant, corrosion of the carbon steel material 8ecvieid.The corrosion product, hydrated iron oxide (common rust)"'is voluminous, occupying many times the volume of the material lost to the corrosion process.Sufficient corrosion product accumulated to block the sensing line tubing, resulting in the inoperability of P-947 and P-948.IV.ANALYSIS OF EVENT This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B), which requires a report of,"Any operation or condition prohibited by the plant's Technical Specifications". CNMT pressure channels P-947 and P-948 were inoperable for a considerable length of time,co'n~yjj,' ~iBci,':qth ei Iragiji'eaM~rei of Ts Table 3.5-2, units g l.b., 2.b., and f.c.Operation i'is condition since June 24, 1992 is a condition prohibited by TS.An assessment was performed considering both the safety consequences and implications of this event.The results of this assessment are that there were no operational or safety consequences or implications attributed to the inoperability of P-947 and P-948 because: o A review of plant history and preventive maintenance history files has shown that the redundant CNMT pressure channels (P-945, P-946, P-949, and P-950)have been either operable or placed in the conservative tripped state from the Event date to the Discovery date,-':::,i,.'::except:";,:,:::if i:.,'pri aOp3Xrima'tel y~ii'iiii's.S;:;a!8 8'C end 8!'iOnl iiDrac enb'sr-'."i".25'p .:.i'2:,"'. o A review of PPCS data has shown that the redundant pressure channels have responded to pressurization of the sensing lines and pressure changes in CNMT.IV'i'sualgirn,epgot3cne." O'OCIFSilSC'e'p,'.:4548 to the same failure mode as P-947 and P-948.NRC FORH 366A (5-92) NRC FORM 366A (5.92)U.S NUCLEAR REGULATORY CQIIISSI ON LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY OMB NO.3150-0104 EXP I RES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENI'ND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NUMBER 2 05000244 YEAR 94 LER NUMBER 6 SEQUENTIAL --002-REVISION 02 PAGE 3'3 0i~O,F,,":::::3'4: TEXT (If more space is required, use additional copies of HRC Form 366A)(17)o The 2 out of 3 logi'c (2/3)required for actuation of SI was reduced to a 2/2 logic with the inoperability of P-947.Thus SI actuation from hkgh CNMT pressure (4 PSIG)would have occurred as assumed in the design basis.0 The diverse actuation circuitry for SI has three additional means of actuation (steam generator low steam pressure, pressurizer low pressure, and Manual).None of these diverse means was affected by the inoperability of P-947.o The 2/3 logic required for Steam Line Isolation actuation was reduced to a 2/2 logic with the inoperability of P-948.pressure (18 PSIG)would have occurred as assumed in the design basis.o The diverse actuation circuitry for Steam Line Isolation has three additional means of actuation (hi-hi steam flow with safety injection, hi steam flow and 2/4 low Tavg with safety injection, and Manual).None of these diverse means was affected by the inoperability of P-948.o The 2/3 plus 2/3 logic required for CNMT Spray actuation was reduced to a 2/2 plus 2/2 logic with the inoperability of P-947 and P-948':",::: exceptor.,':.'.:':,".approx';.mate1y,;".:;nine'!3'(9)j:",.,"second's: wCvWayC... ;'.Pj.V:;'P'5 mVN'+'.WNNRv..::+9~~"%Xv."V Nw."$"w)~.Ã>O'4'Wr>.a~v.~&(i:)).,w iw'%4iN5'gN'V'WC 'Op'.-:;:(pe'C'ember:;:.:'.;:,:24'j'"::.-,,'-:',1'9924 Thus, CkfMT Spray actuation'from ~h-CNNT pressuie (28 PSIG)would have occurred as assumed in the design basis.o The alternate actuation circuitry for CNMT Spray (Manual)was not affected by the inoperability of P-947 and P-948.HRC FORM 366A (5-92) NRC FORM 366A (5-92)U.S NUCLEAR REGULATORY CQBIISSIOH LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED BY OMB NO.3150-0104 EXPIRES 5/31/95 I ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MHBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTOH, DC 20555-0001, AHD TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET'WASHIHGTOH DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NNIBER 2 05000244 YEAR 94 LER NUMBER 6 SEQUENTIAL --002--REVISION 02 PAGE 3 L3~.,:OSCAR,@4c TEXT (If more space is required, use additional copies of NRC Form 366A)(17)N v c y pl p c p c y p"" vyypcCcw'~ypyykvcccccccwvcyyy~...CypvrMCtcpyyy ~w~gCvC: 'CpcvppypppyyCpgvyC"CCpycycxwq>w"C vw".vpw v w, sMw", yy, e>wyc, ypvwy'~sv}vv" vgCyp>wnyyyy yg.~wcyl~".ne~jSX-ai.:uaC'i'onjixsta4ie-@xoig~>enanne'i;:-P,; I'ccccppy+,,c,~p., Cv,av+$CCRj p&%0p'tcwx Ccvpppyvw xvwypepp?'v'p(%vC'?'v.,wpppw"pwp..fey Y:.., vyvywc'>.yyw A," vcwC,.%,.vyvc'.vpp',r',~yy,'>:;cyA,"v>paved c i w7 w kine':<:;..'9:::.,".,s'i5~6n'~iiY 8r'voa'e'I,c()n,'i ':()n:,"'"'"VNSNh~~vccyNQRhfpMc4MxL'(&cvc'Cvykckc@c~ HRC FORM 366A (5-92) NRC FORH 366A (5-92)U.S.NUCLEAR REGULATORY C(NNISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY INIB NO.3150-0104 EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS~FORWARD CONHENTS REGARDING BURDEN ESTINATE TO THE INFORHATIOH AND RECORDS HANAGEMEHT BRANCH (HHBB 7714), U.S.NUCLEAR REGULATORY COHHISSIOH, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF HANAGEHENT AND BUDGET WASHINGTON DC 20503.FACILITY HAHE 1 DOCKET NIMBER 2 YEAR LER NlMBER 6)SEQUENTIAL REVI SI OH PAGE 3 R.E.Ginna Nuclear Power Plant 05000244 94--002--02 TEXT (If more space is required, use additional copies of NRC Form 366A)(17)r N:~".--: Based on the above, it can be concluded that the public's health and safety was assured at all times.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: o The iron oxide scale-was removed from the obstructed penetration sensing line and P-947 and P-948 were restored to operable status.o The other channels that monitor CNMT pressure were verified to respond to small changes in CNMT pressure.HRC FORH 366A (5-92) NRC FORH 366A (5-92).S.NUCLEAR REGULATORY C(HIIISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION PROVED BY QQ NO.3150-0104 EXP I RES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REOUEST: 50.0 HRS.FORWARD COHHENTS REGARDIHG BURDEN ESTIHATE TO THE INFORHATIOH AND RECORDS MANAGEHENT BRANCH (MHBB 7714), U.S.NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AHD BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NQIBER 2 05000244 YEAR 94-002 02 LER NIMBER 6 SEOUENTIAL REVISION PACE 3 l jig?'g'OP>:i,'s'.'>g'cg TEXT (If more space is required, use additional copies of HRC Form 366A)(17)B.ACTION TAKEN OR PLANNED'O PREVENT RECURRENCE: o PPCS computer points for CNMT pressure will be archived daily until the 1994 refueling outage to verify channel v V v v I)o The sensing lines for all CNMT pressure channels will be ins ected and cleaned out during the 1994 refueling outage.o The method of calibration of the CNMT pressure transmitters has been changed to use gas (instead of water)as the test ccQ~w&4~?v'wccggcg~ccc~ ccccv?+wvYp~v?ccw???v?c?vsNvccvc.'i. "(pY."wp&c?vv?v54<r"'v,cvcv g medium.?"ese::,xe'vms'ea:-:,:;,::proc'e'dUxe's.:;:::'.::vere'..::..u'si'd!-'.'to:;'::,per'for'ia prai~rit'i~i::::;i'IIc m~:rancp';! "'"'*""'"""'""""="" o Testing these containment penetrations has been enhanced to include formal documentation o'f pressure channel response.>~: e'kaid'~~b8inh"::~ins.i i','.i,""'epC'os't'a3'.: HRC FORH 366A (5-92) NRC FORM 366A (5-92)U.S.NUCLEAR REGULATORY CQHII SSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED BY (HLB NO.3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTIOH REQUEST: 50'HRS.FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MAHAGEMENI'RANCH (MHBB 7714), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.FACILITY NAME 1 R.E.Ginna Nuclear Power Plant DOCKET NINBER 2 05000244 LER NUMBER 6 YEAR SEQUENTIAL 94-002 REVISION 02 PAGE 3 m~"~O~~"~4 TEXT (If more space is required, use additional copies of HRC Form 366A)(17)VI.ADDITIONAL INFORMATION A.FAILED COMPONENTS: There were no failed components. The obstructed sensing line is 1/2 inch OD, 0.065 inch wall thickness, carbon steel tubing.Information about the vendor and manufacturer is not relevant to this event.B.PREVIOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: LER 92-003 was also an event caused by an obstructed pressure sensing line.However, the obstruction was caused by buildup of sludge from normal impurities in the process fluid (feedwater). The obstruction referred to in LER 94-002 was caused by corrosion from the interaction of the test medium and the sensing line materials. C.SPECIAL COMMENTS: None HRC FORM 366A (5-92)