ML20126E330

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Submits Info Re Operating Difficulties at Facility Concerning Failure in Main Steam Bypass Valve Control Sys. Intends to Reload Facility to Normal Core Size During Outage & Resume Normal Operation
ML20126E330
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/28/1964
From: Haueter R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Boyd R, Doan R
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101190469
Download: ML20126E330 (10)


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M. F.00EP 5. BOYL Dt! RING RECEt1T TELEPHONE CONVEE5ATION5 WITH MEMBERS OF YOUR WAS REOUTSTFD TbAT INFORMATION BE SUBV.1TTED RELATIVE OM2r.TINC DIr} !CO'. TIES AI THE BIG RhCK Po!NT N'JCLEAF PLANT - DOC);El 50-155.

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i AT 2-? C PF. ON TEFT:II if, is(4, A TAILU!:E IN T1E MAIN ETEtt Y'- /. e 1

VM.VE CH:'.F.Cl s ;- Tir. C AUoLI' THE V ALVI TO OPEA Fl'LLY.

ATTEFT1 BY 761 0FER ATOF TO CLOJT THE VALVE BY ACTUATINC THE MANUAL OVERFIDT EV11CH T/.! LEI, Ak,! THE hiACT0F S CE /J.I'El Ot; INDICATEI HIC 1' TLUX Oh PICO-/ P"ITE):

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Tpt pp. AV-E0W. OT REACTOS PP.ESSEE TrFC!.:C' TFT EYTI55 VILVi WA!, STOPPED EY CLOLINC THi. MAIN STEAP ISOLATION VALVI.

A'1 EEA CICT PEI.5S G E LEVELEL OTT AT ABr.U1 250 F5IC.

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.. M 2 i. 'i j f.5 P'r!, LTI L I 21 N;. BOTH CONTROL RCD OSCILLATOR TE;T3 At ET.45. OSCI(L ATICE TESTS.

A1 T):E TIr.E OF TFE BTF A' S VAuVi hAL-Tl"4CTION, STABILITY TE5TS AT APPR0XIMATELY 150 MVT WGE IN PkOC):ESS.

T'.L C0;*ThCL ROT, OSCILL ATOR TESTS HAD JUST BEEN COMPLETT.D AND PREPAE A-TIONS VII;E L7CIE WAY TO OSCILLATE THE BTPASS VALVE.

INITIAL CONDI-TIONS WERE AS TOLLOWS -

REACTOR POVEk LEVEL - ADPROXIMATELY 150 MVT GE4fy? T0F. OU1PUT - APPK07.1MATELY 43 MVE

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A ChlTROLACDPATTERN-(1L RODS TULLY. 61THDR AUN EI(])DT B2 AT-NOTCH 1E,

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P FEELJATER 00'!Ti0L 0,'! MANUAL BYPASS VALVE 5. PERCENT OT'EN CHR 3NOLOGY OF EVENTS -

T PLUS 0 SEC - BYFASS VALVE OPENED T FLUS S SEC - U"FLCCESSTUL ATTEMTT TO CLOSE BYPASS VALVE T PLUS 17 SEC - REACTOR SCRAMMED ON HIGH TLUX T PLUS 27 SEC - SECO'ID UNSUCCESSTUL ATTEMPT TO CLOSE BYPASS VALVE T FLUS 53 SEC -' STAP.TED CLOSING MAIN STEAM ISOLATION = VAL"I T PLUI 77 SEC - MAIN STEAM ISOLATION TRIP.

VALVE 50 PERCENT CLOSED T PLUS 103 SEC - MAIN STEAM ISOLATION VALVE 100 PERCENT CLOSED T PLUS 107 SEC - BYPASS VALVE CLOSED ANALYSIS OT TRANSIENT -

IT WAS SOMEVHAT TORTUITOUS THAT THIS MALTUNCTION OCCURRED DURING R&D TESTING, SINCE R&D INSTRUMENTATION AND HICH SPEED RECORDERS WERE IN SERVICE AND THUS 'INFORMATION WAS COLLECTED THAT OTHERWISE WOULD NOT HAVE BEEN AVAILABLE.

wn,5zwunuwts aswway a wr esws6NUUL%V SHOWN,TO BE LESS THAN 65 PERCENT OF THE STEADY STATE LEVEL PRIOR TO THE TRANSIENT.

THIS LEVEL WAS CONTIRMED BY ALL TOUR IN-CORE ION CHAMBERS CONNECTED TO HIGH SPEED RECORDING EQUIPMENT.

DUE TO THE NONSYMETRIC 44-BUNDLE "6NTIGURATION WITH RESPECT TO THE OUT-0T-CORE ION CHAf'SERS, WE DO N ATTACK UNUSUAL SIGNITICANOL TO THE DIFFERENCE IN PEAK READINGS E JJEEN ALL REC 0dDED CHAMBERS FOR A PRESSURE TRANSIENT OF THIS TYPE.

QUANTITATIVE ANALYSIS OF EXPECTED RESPONSES WOULD BE EXTREMELY DITTICULT, HOWEVER, THE GENERAL ETTECT 1

0F THE RAPID DEPRESSURIZATION WOULL DEFINITELY LEAD ONE TO EIPECT SIGNITICANT8,f INCREASED NEUTRON LEAK 4GE FROM THE CORE AND THE 00RRESPONDIhC INDICATION OF HIGHER POWER LEVEL ON OUT-0T-CORE INSTRUMENTS THAN ACTUALLY EXISTED.

THISWASVERITIEDON'ALLTIhr CIC,S WITH THE LOVEST READING BEING ABOUT 90 PERCENT OF STEADY-STATE LEVEL AND THE HIGHEST READING ABOUT 1A8 PERCENT OF STEADY-STATE l

LEVEL, ALL COMPARED WITH THE ACTUAL iRANSIENT PEAX OF LESS THAN (5 PERCENT.

IT CAN BE SHOWN THAT A DECREASE IN WATER DENSITY OF 30 l

PERCENT TOR THE REFLECTOR THICKNESS PRESENT ON THREE SIDES OT tHE 44-BUNDLE CORE WOULD RESULT IN AN INCREASED NEUTRON LEAKAGE OT &

TACTOR OF R TO 3.

THIS DENSITY REDUCTION IS TELT TO BE VELL WITHIN THE RANGE OF CONDITIONS THAT ACTUALLY EXISTED DURING THE TRANSIENT.

l IT SHOULD,BE NOTED TNAT THE N0DERATOR TEMPERATURE INCREASE RESULTING FROM A PRESSURI INCREASE WILL RESULT IN A MODERATOR DENSITY DECREASE AS EEKIIII WILL A RAPI3 PRESSWRE DECRIASE. BOTH E55 ULT IN A CONSERTA-l TITE OUT-0T-CORE ION CHANRD TRANSIENT INDICATION.

SUMMARIZD s

ELOW ARE TWE RESULTS OT TKERMAL-XYDRAULIC ANALYSES BASED UPON TEE ASSUMPTION THAT SIGNITICANT STERPOWER CONDITION CT APPROIINATELY 1A9 PERCDtT ACTUALLT DID EXIST -

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MAX..TUEL TEMT 3,170 3,95C MAX. CLADDING TEMP 525 623 MIN CRITICAL WEAL TLUX RATID 2,21 1.8 6 AT OVEP PC'.'

MAX. AVG POWER DENSITY 55 56 ENERGY RELEASE DUEING 18-SE00 G TRANSIE*'!

S.M 7 5'T-: E3!:h 2,72C MVT-SECCNJ3 IT CAN BE SEEN TWAT IT IS VERY UNLIKELY THAT ANY 00?.E PARAMETER EXCEEDED THE INITI AL STEADY-STATE LEVEL DURING THE TRANSIENT, EVEN UNDER THESE ASSUMPTIONS.

RECORDINGS OF THE INLET AND OUTLET THERMOCOUPLES IN THE INSTRUMENTED TUEL BUNDLE PERMITTED ACCURATE MEASUREMENT OF THE RATI 0F CHANGE OT 000LANT TEMPERATURE.

USING THIS MAXIMUM RATE OF CHANGE OF MINUS 5 DEEP.EES T PER SECOND, AND ASSUMING THE INNER SURTACE OF THE REACTOR ~

YESSEL IS CHANGING AT THIS RATE, A VERY CONSERVATIVE STRESS ANALTSIS SHOWS A STRESS AMPLITUDE OT 67.7EPST yur".ppgp to ygg 54,3 KpSI -

THE DESIGN STRESS AMPLITUDE FR0h AMMENDMINT 5, TIGURE IV, BIG ROCK POINT TINAL HA2 ARDS

SUMMARY

REPORT - THIS RESULTS IN A' WO USING ASME 111 FATIGUE CURVE, TIGURE N-A15A, AT LEAST 330 122 KPSI.

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5IMILAR CYCLES ARE PERb 5SIBLE.

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A:;A YiI 5 U 9413.0L F;D - DRIVE I:A Tl":: TION:

4 CONTROL R T Dr.:VI3 L-3 AND A-t. WERE EXE401SE: SEVER /.L tit'ES DifRING THE C00l. D01.". 0F TFIE F.E A^ TOR, VITH DR1YE E-3 GIVEN MORE ATTD;TIO:!.

RE'f?ONSE CHARACTERISTICS WERE CONO STENT WITM THOSE FOU!J DURIN'.

THE EARLIER CASL Of GALLING ON FEi;;.UARY 20, 19 63, WH I CP WAS RG'ORTED If4 SH-2.

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'0-i R i t." E-3 EEiEc.2,E ' T ' T THE INDEX T'JDE V ~ CA: LD ci.M i MO.; ~ 07 ! T ? L'I 40 T h PRODU;INC !. LA51E NUhislF. 01 tsIP5.

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TE.5E Cd F5 *t s 4Eb 7.N AND AROL'?.D Tr:.. COLLE1 REit.11ER Ar GU!TE SL EF E AS k7 LL A' IN THE COLLET FIST 0!;.

041' OR MNIT. OF '*HECE Cl.I P,". Ilt r -

LOCKi D T4 C0;1ET IN THE CPEN PJ5I?l0N.

FisD ENIDENCED-FIGH FRICTIori BETVEEtJ POSI!10N3 00 AND C3.

IT.I V f. A -4 THE ICn TMI' Wr.3 TODNP CALLER IN THIS Alti.f.,

CALLIN: VAL ALSO EVIDENT IN THE GUIDE SLEEVE, ESPECIALLY IN THE UNPLATED AREA 0T TFE CUIDE SLEEVI.

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DR IV E C-4 W AS Rd.0 6.L n : i :.r. u!wvASING 0} THE FULL '5ND THE Rs.MOVAL OT THE SUPPORT TudE5 IN ITS VICINITY.

A 70EEIGN OBJECT WAS TOUND

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f TO BE WEDGED BETVETN AN INLEX TUBE NOT0d AND THE CONTROL. ROD DRIVE NO22LE EXTENSION, THUS PREVENTING ROD VITHDP.AWAL.

THE DRIVE WAS TOUND TO BE IN GCOD CONLITION.

THE FOREIGN OBJECT WAS THE HEIAGONAL HEAD OT A 1/2-INCH STAINLESS STEEL BOLT, WITH ACTIVITY LEVEL of APPROIIMAIELY 1/5/ 1 NR/HR.

IT IS CONOLUDED THAT THIS BOLT HEAD UNDOUBTEDLY ORIGINATED IN THE STEAM DRUM, PROBABLY AS A RESULT OF DRUM INTERNALS REMOVED DURING CONSTRUCTION TOLLOVING THE INITI AL TLUSHING OF THE SYSTEM.

THE BREAK DID NOT APPEAR To BE NEW.

AS A PRECAUTIONARY MEASURE, HOWEVER, A DEUM MANHOLE WILL LE REMOVED DURIN-THE PETSENT OUTACE AND DRUM IRTERNALS INSPECTED.

WE CONCLUDL TH AT THE CALLING OT THE TWO DRIVES TROBABLT RESULTET Tkot SMALL PARTICLES - IN SUSPENSION DUE TO THE CONSIDERABLE ACITATIDN PEESEKT IN THE REACT 02 VESSEL DURING THE TRANSIENT - WHICH WLRE DAAEN DOWN INTO THESE DRIVES, EYPASSING THE SCREENS.

- EXAMINATION OF THE SCREENS OF ALL THREE DRIVES REVEALED ONLY THE USUAL SLIGHT COATING OT CEUD THIS STARTED THE GALLING WHICF PROGRESSED AS THE DRIVES VERE EX ER CISED.

EXERCISING OF DRIVES SHCWING EVIDENCE OT HIGH TRICTION VILL BE LIMITED IN THE TUTURE TO FREVENT RECURRENCE OT THE DITTICULTT DESCRIBED ABOVE.

WE ARE PLANNING TO INSTALL IMPROVED SCREINS AND A MODITIED COLLET SLEEVE 05 ALL DRITES AS THE OPPORTUNITT FRESENTS ITSELT.

WE ARE ALSO CONTEMPLATING THE INSERTION AND TESTING OF SEVERAL MITRIDED 304 SS INDEI TUBES WHICH APPEAR To SE NUCH LESS SUSCEPTI ALE TO GALLING.

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Er/ PASS VALVE -

8 THE BYPASS VALVE MALFUNCTION APPEARS TO HAVE BEEN CAUSED BY STICKING Of THE HYDRAULIC SERVO VALVE.

IN ADDITION, THE MANUAL OVERRIDE CLOSURE FEATURE FAILED TO FUNCTION.

THE EQUIPMENT MANUFACTURER HAS BEEN CONTACTED TO THOROUGHLY ANALYZE THE DIFFICULTIES AND THE STSTEM VILL BE THOROUGHLT CHECKED OUT AND TESTED PRIOR TO RESUMINC OPERATIONS.

CONCLUSIONS -

IT IS HOPED THAT THE ABOVE DISCUSSION ANSWERS TOUR QUESTIONS WITH RESPECT TO THIS PLANT SHUTDOWN.

IF YOU HAVE FURTHER QUESTIONS, WE WOULD BE HAPPY To C0 INTO FURTHER DETAIL.

WE PLAN TO RELOAD THE BIG ROCK POINT To THE NORMAL CORE SIZE DURING I

THIS OUTACE AND RESUME NORMAL OPERATION.

THIS SHUTDOWN CAME AT THE TDY END OF TNE ADDITIONAL TESTING PERT 0 REED TO TURTHQ EXPLORE THE NEUTION TLUI OSCILLATIONS VMICH NAD 6CCURRD WITH TME SMALL 44-BUNDLE CORI.

WE TEEL THAT ALL PERTINENT INT 0RkA-TION' NAS EEN COLLECTED AND THAT TURTHER OPERATION WITM TNIS CORE WOULD SDVE LITTLE PURPOSE.

PRELIMINARY ETALIATION OT THESE ADDITIONAL TESTS CONTIRN EARLIER' 00NCLUSIONS TNAT TIE CORE WAS BEING DRIVEN ST EXTERNAL EICITATION AND TMAT TXE REACT 0t IS INHDENTLY STABLE.

A DETAILEB REP 0tf GN TIIS INTfICATION WILL RE SUBMITTED AS SOON AS PROCESSING 00 m m D.

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kOBERT L. HAVETER ASST ELECTRIC PRODUCTI0t1 SUPT - NUOLEAR 3

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A U. S, Ow.ERN M E N T PRIN TlN0 OF F ICE: 1964 - 725*839 DATE OF DOCUMENT, DATE RECEIVED NO.e N

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POSI OFFICE FILE CODE.

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REFERRED 10 DATE RECEIVED BY DATE t

Tal. substittinc info relative to roosnt Rock Boyd:

9-29 Sratingdiffic.:ltieeattheEiEnt, resulting from recent telcone w/

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ENCLO5URE5.

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