ML19242A184

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Submits Slides to Be Inserted Into 790613 Transcript for ACRS Subcommittee on Reactor Operations Meeting Re Power Increase
ML19242A184
Person / Time
Site: Millstone 
Issue date: 06/14/1979
From: Simpson M
ACE-FEDERAL REPORTERS, INC.
To: Stephens C
NRC OFFICE OF THE SECRETARY (SECY)
References
ACRS-T, NUDOCS 7907310474
Download: ML19242A184 (34)
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C PMUC DMEW PMM RICHARD J MATSKO. MBA GEORGE A M O N I C K. CSR ALAN 1. P E N N. Ph. D.

STENOTYPE REPORTERS RCBERT J. MONICK. CSR GEORGE J JAKASCIN. MBA 444 NORTH C APITOL STREET ROBERT JAMES MONICK B S. W A S H I N GTO N, D. C. 20001 202 347 3700 JUNE 14, 1979 U.S. NUCLEAR REGULATORY COMMISSION DOCKETING & SERVICE BRANCH 1717 H STREET, N.W. ROOM 1141 WASHINGTON, D.C. ATTN: MR. CHASE R. STEPHENS DEAR CHASE: PLEASE FIND ENCLOSE COPIES OF SLIDES WHICH SHOULD BE INSERTED IN THE TRANSCRIPT IN THE MATTER OF ACRS SUBCOMMITTEE ON REACTOR OPERATIONd - POWER LEVEL INCREASE HELD ON WEDNESDAY, JUNE 13, 1979. SORRY FOR ANY INCONVENIENCE THIS MAY HAVE CAUSED YOU. VERY TRULY YOURS, AC - ERAL PORT RS, INp j (MISS) MARY A. SIMP N c. v N ATIONWIDE COVERAGE

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MILLSTONE UNIT NO. 2 ACRS MEETING - JUNE 13, 1979 LICENSING AND OPERATING HISTORY CONSTRUCTION PERMIT APPLICATION -- FEBRUARY 12, 1969. CONSTRUCTION PERMIT ISSUED -- DECEMBER 11, 1970. MAJOR NSSS COMPONENTS DELIVERED -- FEBRUARY / MARCH 1972. FSAR SUBMITTED -- AUGUST 15, 1972. ACRS SUBCOMMITTEE SITE IOUR -- JANUARY 26, 1974. SER ISSUED -- MAY 10, 1974. ACRS SUBCOMMITTEE MEETING -- MAY 22, 1974. ACRS FutL COMMITTEE MEETING -- JUNE 6, 1974. OPERATING LICENSE ISSUED -- AUGUST 1, 1975. 6 (,' s/

MILLSTONE UNIT NO. 2 OPERATING HISTORY L .1 (MDC CAPACITY FACTOR, BASED Ori 796 MDC NET = 66.6%) OPERATING LICENSE ISSUED -- AUGUST 1, 1975 i .NITIAL CRITICALITY -- OCTOBER 17, 1975 'MMERCIAL OPERATION -- DECEMBER 26, 1975 IESEL GENERATOR REPLACEMENT OU. AGE (3.5 WEEKS) T '-t DECEMBER 20, 1976 - JANUARY 13, 1977 5 ~TUEE MAIN CONDENSER (6.5 WEEKS) f,' 7, 1977 - JUNE 21, 1977 1.si REFUELIf4G/ STEAM GENERATOR TUBE PLUGGING (35.5 WEEKS) -VFMBER 20, 1977 - APRIL 27, 1978 (MDC CAPACITY FACTOR, BASED ON 810 MDC NET = 94.4%) ~~ ~ ~I CALITY -- APRIL 21, 1978 1 s: Powan -- MAY 8, 1978 DND REFUELING (10.5 WEEKS) iRCH 10, 1979 - MAY 22, 1979 g,,.y J ICALITY -- MAY 18, 1979 ' MWT POWER -- MAY 31, 1979 O za2

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crt.: m 1E PAP 57EV 'T t'!FFEDENT COPE BEP.ML CONDi~ 0.'N vr,\\ '.'LL ill " . hRE 2560 fu!r/5tQ^~ 2560tiWr/51100F I 2700 TNT /5490F I STEAR 6ENERATon OUTLET FLOW 11,135,500 LBS/HR 11,151,200 LaS/Ha 11,834,700 Las/HR STEAM GENERATOR OUTLET PRESSURE 839 PSIA 880 PSIA 875 PSIA STEAM GENERATOR SATURATION TEMPERATURE 523.7 F 529.3 F 528.60F STEAM GENERATOR OUTLET tblSTURE CONTENT 0.2% 0.2% 0.2% TuRalHE IHLET STEAM FRESSURE 802 PSIA 841 PSIA 836 psgA FEEDWATER FLOW TO STEAM GENERATOR 11,151,000 LaS/;.. 11,166,700 LBS/HR 11,849,800 Las/HR FINAL FEEDWATER IEMPERATURE 430 F 429.5 F 435.2 F CONDENSATE FLOW 7,927,000 tsS/HR 7,893,300 LBS/HR 8,367,700 Las/HR TOTAL llEAT REJECTED 5.83 x 10 btu /HR 5.82"x 109 BTuhm 6.13 x 10 Bru/HR 9 9 c x.. F.XPECTED 6ENERATOR OuTPur l 851.9 MWE 854.8 tillE 901 A MWe

i CORE j,' REACTOR VESSEL EQUIVALENT _~ j DI AMETER,/- M I.D 136 " ,/ i s' l . U ii I T i L_ s 7 '/[T / l \\'h 1 1 i i t-t iI1 i i g[ / //- i iiit i11 1 1I -y. r'g i s j } I I 1 i l 1 I I l.l ! / ,{ k l

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GUIDE TUB 5 (D 3 / UD gw nwww mam+m w w eyj y Yl', l L >iiii ,is!x i:2313 SPACES '^' Mf6 '. "M.I" i j AT 0.580" M '! ' l 9[

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-0.140" 0 'T5 E 0.580" m Fg0D m-FUEL RODS 0.200" WATER GAP pn n c,m. mn n ? E y y t. v UhW% k I Reactor Core Cross-Section m 1

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MP2 CORE PHYSICAL PARAMETERS 43ER OF FUEL ASSEMBLIES 217 l._L ASSEMBLY ARRAY 14 x 14 ASSEMBLY DIMENSIONS 7.98 in. x 7.98 in. .fi OUTSIDE DIAMETER .3765 in. .: OUTSIDE DIAMETER .440 in. 7 THICKNESS .028 in. f.:0 PITCH .580 in. FUEL HEIGHT 136.7 in. QUIVALENT DIAMETER 136.0 in. OF CONTROL ELEMENT ASSEFBLIES 73 O

MILLST0f1E POINT II CYCLE 3 CORE LOADItiG INITIAL IfilTIAL AVERAGE NUMBER SHIM TOTAL /6 0 ! fiUMBER OF Ef1RICHMEliT BURfiUP* OF LOA 1ING TOTAL FUEL D7 ' ' Ti ASSEMBLIES WT% U-235 Mild /PRU SHIMS WT% BeC SHIFTS RODS 5 2.33 25,400 12 2.7 60 820 0 7,040 40 2.82 19,700 0 16 2.82 24,800 12 .83 192 2,624 12 2.82 24,900 12 .46 144 1,968 0 8,448 f 48 3.03 7,600 0 0 - 4,224 0 24 2.73 .,_l,0, 6 00, 0 8,448 48 3.24 0 0 0 4,224 i 21 2.73 0 0 217 396 37,796 " O '.: 'F CYCLE 2 LEfiGTH OF 8,700 fidD/T. JCLE 3 LENGTH: 10200 MJD/MT. I E i,, su v u.

MP2 PHYSICS CHARACTERISTICS CYCLE 2 CYCLE 3 DISSOLVED BORON ppm 660 830 HFF, BOC BORON WORTH ppm /",dp HFP, BOC 88 93 HFP, BOC 77 82 MODERATOR TEMPERATURE 10-46p/0F COEFFICIENT HFP, B0C .6 .2 HFP, E0C -2.0 -1. 8 g AVAILABLE CEA WORTH %6g BOC 9.0 9.7 EOC 10.0 11.0 STUCK CEA WORTH %dp BOC 3.0 3.1 E0C 3.1 3.5 EJECTED CEA WORTH %dp HFP .31 .29 HZP .74 .65 PEAKING FACTORS 1.440 1.598 FR Fxy 1.546 1.584 l: !L:l

MP2 LOW PO'n'ER PHYSICS TEST RESULTS MEASURED PREDICTED CBC (PPM) AR0 1212 (70 135) 1205 (AR0) ARI 888 861 ITC (x10'4tgo/ F) 0 BANK 7 THRU 2 INSERTED .686 .721 AR0 +.269 +.372 BANK WORTHS (%f2,C) BANK 7 .637 64 BANK 6 .250 25 BANK 5 .172 16 BANK 4 .875 95 BANK 3 .671 .72 BANK 2 1.139 1.08 OVERLAP 3.743 3.80 POWER DISTRIBUTION CHECK AT 50% POWER MEASURED: POWER DlSTxIBUTIONS AGREED TO WITHIN 5% OF PREDICTED. p e V L s

MP2 THERMAL HYDRAULIC PARAMETERS PARAMETER _ UNITS CYCLE 2 CYCLE 3 CORE POWER Mwt 2560 2700 INLET TEMPERATURE F 542 549 O 6 CORE FLOW RATE x10 LBM/FR 135.0 133.7 2 CORE AVERAGE HEAT FLUX BTU /HR-FT 177,700 183,000 2 TOTAL HEAT TRANSFER AREA FT 47,940 49,100 AVERAGE LINEAR HEAT RATE KW/FT 5.99 6.17 AVERAGE ENTHALPY RISE BTU /LBM 65 69 O V fg \\ I e

  • KEY CHANGES FR0ft CYCLE 2 MODEL CHANGES:

1 1. T-H MODEL - TORC /CEl (CYCLE 2 - COSM0/W3) - TORC MULTICHAfiNEL CODE T-H CODE - CE-1 CHF CORRELATION (LIMIT 1.19) 2. SMALL BREAK MODEL - MODELIf;G CHAf1GES TO CEFLASH - 4AS I 3. RMS STATISTICAL COMBINATION OF UNCERTAINTIES: l l - SETPOINTS - THERMAL PARGIll INPUT SYSTEM CREDIT CHAfiGES: 1. CORE POWER 2700 MJt (CYCLE 2 - 2560 KJt) 2. T INLET 549 F (CYCLE 2 - 542 F) 3. SCRAM TIME 3.1 SEC (CYCLE 2 - 2.75 SEC) 4. UNCERTAINTIES 6% ON Fr 7% ON Fq

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/00 5. RCP SPEED SENSING: CREDIT FOR RCPSS TRIP IN 4 PUMP LOF If4CIDENT

NORTHEAST UTILITIES MILLST0!1E POINT UNIT 2 CYCLE 3 DESIGN BASIS EVEtiTS (DBE3) CONSIDERED IN STRETCH POWER ANALYSIS AriTICIPATED OPERATIONAL OCCURREliCES FOR WHICH THE RPS ASSURES fl0 A!!ALYSIS STATUS VIOLATION _OF SAFDLs: CONTROL ELEMENT ASSEMBLY WITHDRAWAL REANALYZED REANALYZED BORON DILUTI0ri STARTUP 0F AN INACTIVE REACTOR C00LAfiT PUMP NOT ANALYZED REANALYZED EXCESS LOAD LOSS OF LOAD REANALYZED LOSS OF FEEDWATER FLOW REANALYZED EXCESS HEAT REMOVAL DUE TO FEEDWATER MALFUNCTION NOT ANALYZED REACTOR C00LAtlT SYSTEM DEPRESSURIZATION REANALYZED LOSS OF COOLANT FLOW REANALYZED ANTICIPATED GPERATIONAL OCCURRENCES WHICH ARE DEPENDENT Oft IllITIAL OVERPOWER MARGIN FOR PROTECTION AGAINST VIOLATION OF SAFDLs: LOSS OF COOLANT FLOW REANALYZED FULL LENGTH CEA DROP REANALYZED PART LENGTH CEA DROP NOT ANALYZED PART LEt!GTH CEA MALPOSITIONIllG NOT ANALYZED TRANSIEtiTS RESULTING FROM MALFU!1CTION OF ONE STEAM GENERATOR REANALYZED POSTULATED ACCIDENTS: REANALYZED CEA EJECTION STEAM LINE RUPTURE REANALYZED STEAM GENERATOR TUBE RUPTURE REANALYZED REANALYZED SEIZED ROTOR 9 ~C 20l

SUMMARY

OF MP2 CYCLE 3 TRANSIENT ANALYSIS RESULTS CEA WITHDRAWAL MIN DNBR - 1.58 liAX PRESSURE - 2358 PSIA TM/LP TRIP PRESSURE BIAS - 45 PSIA BORON DILUTION 10 MINUTES EXISTS FOR OPERATOR ACTICN EXCESS LOAD MIN DNBR - 1.41 LOSS Of LOAD MIN DNBR - 1.33 MAX PRESSURE - 2555 PSIA LOSS OF FEEDWATER MIN DNBR - 1.33 MAX PRESSURE - 2476 PSIA 15 MINUTES TO INITIATE AUX FEED. EXCESS HEAT REMOVAL DUE TO FEEDWATER PALFUNCTION BOUNDED BY PREVIOUS ANALYSIS RCS DEPRESSURIZATION TM/LP TRIP PRESSURE BIAS - 35 PSIA LOSS OF FLOW MIN DNBR - 1.19 MAX PRESSURE - 2301 PSIA CEA DROP MIN DNBR - 1.21 c; O J J i- .,,.. ~ -

ASYMMETRIC STEAM GENERATOR TRANSIENTS LOSS OF LOAD TO ONE STEAM GENERATOR MIN DNBR - 1.24 CEA EJECTION NO CLAD DAMAGE STEAMLINE BREAK FULL LOAD SUBCRITICAL BY.15% 6 9 BRIEF POWER INCREASE - 8% TO 12% NO LOAD BRIEF CRITICALITY .21%6pMX STEAM GENERATOR TUBE RUPTURE SITE B0UNDARY DOES ACCEPTABLE SIEZED ROTOR 1% FAILED FUEL SITE BOUNDARY DOES ACCEPTABLE e S U [OJ

MP2 CYCLE 3 LARGE BREAK LOCA ANALYSIS PCT BREAK CYCLE 2 CYCLE 3 1.0 DES /PD 2110 F 2079 F .8 DES /PD 2160 F 2077 F 0 .6 DES /PD 1950 F 0 1.0 DEG/PD 2105 F 2080 F U .8 DEG/PD 2111 F 2081 F 0 .6 DEG/PD 1948 F PLHR 15.6 KW/FT 15.6 KW/FT MAXIMUM LOCAL CLAD OXIDATION (10.7% (16.0% MAXIMUM CORE WIDE OXIDATION (.58% (.73% ~ ~,. a

MP2 SMALL BREAK LOCA R$5ULTS CYCLE 2 CYCLE 3 BREAK AREA PCT PCT 0 .5 1075 F 1629 F .2 15620F 16120F .1 1971 F 0 .05 1931 F - 1824 F 0 .02 662 F 558 F 6 9 e J VJ m

TABLE I LOW FLOW TRIP FUNCTI0tlit0M!NAL CHARACTERISTICS PERFORMANCE C11ARACTERISTICS LOW FLOW TRIP FUNCTION RCPSS TRIP FUNCTION (STEAM GENERATOR AP) 2.7% 1.5% System Overall Accuracy 0.8% 0.8% Bistable Drift Allowance 2.25% 1.0% System Noise 91.7% 93% Nominal Trip Setpoint 450 msec 650 msec Overall System Response Time P i , ' ~ K,' G

f [, v 8 REACTOR COOLANT PUMP SHAFT SPEED SENSIftG SYSTEM (TYPICAL CllAtlNEL) EXISTING RPS CONTAlflMENT C0?lTROL ROOM LOGIC a FREQUENCY TO SISTABLE DISC Oil SIGt(AL PROCESSING ACTIVE V0LTAGE + TRIP UNIT MOTOR TRANSMITTER g+ EQUIPMENT (EXISTING) I SHAFT E PROBE C0?lVERTER , (44 HOLES) S E SPARE PROBE REP MOTOR TRANSMITTER SETPOINT

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N8-N3 60R H4 l60R 1R 60 N5 f65R 1R l 65 /g N19 N6 4R 40 100 e / N7 'l.5R 10 150 NB 1.5R 10 150 _N15.N2 .516 . N1 ., N17 .N18 N9 31 150 33 N10 20R 600 33 n, h3 10R 400 25 N11 6R I f a N5 N12 A 3 e e 1 N14 N10 N13 19R 10R 400 25 N14 N15 yon l ,e ~ $13 Ii3 171 2 d4 'hl1 N16 6R N17 10R 400 25 _3 N18 p

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4 p yg, N21 7R 80 SS D' T N22 2R 30 67 N23 'mm [ ] e N7 N23 2R 30 67 ] '4 e N24 2R 39 67 N25 3R 40 75 I P_ j. WkOl&IL dSIt" ?!'*! T EXTRAPOLATED TO 100% POWER (2700 WTH) BASED ON 13% AND 50: SURVEYS I * /' O L u

MILLSTONE UNIT No. 2 NWTRON SURVEY ELEVATION 14 '6" arem/hr R EsuLT5 M NT B A RF N1 400 N6 N2 ino A (n N3 300 6 50 N4 800 eN7 N5 900 10 90 11 5 i j N6 300 N7 300 0 10 \\ 1;0 N9 I 1 N. . N4 1 N9 a o. s3 O l 1 s-N1 B = Before Shield N2 A = After Shield RF = Factbr of Reduction 5 g ' i). ;,% EXTRAPOLATED E 100% It'JER (2700 HvrH) g EASED ON 13% AND 50% SURVEYS p(- ,,.y yfiM "p,CX e,,r. ,--l,,,, I L..

MILLSTONE UNIT 10. 2 NEUIRON SURVEY ELEVATION -3'6" aree/hr e tsutT 5 PCxwT B A RF N1 200 N2 175 25 7 p3 N3 250 8 25 A I I N4 250 10 31 1p N8 NS 250 N6 200 8~ - - 25 Sc J 200 8 25 3,3 N9 _.g2 ...s ~ N9 / \\\\ FIO N N11 N12 I a r. t e. e N4 N11 d \\\\ l / / m M 812 --* E7 o c m SC ) ELEvaToa [ h\\ II l B = Before Shield A = After Shield RF = Factor of Reduction 'N6e' sw ,+ usl l POWER (2700 MVIP )jj j f f, [ [ _1lEtAshid t EXTRAPOLATED TO 100: h Gk PASD ON 13% A10 50% SURVEYS ') l !{ C-J

MILLSTONE UNIT HO. 2 NI2JTRON SURVEY ELEVATION 38'6" crem/hr Ps P E CM a! E RESULTS s N PO'N T IB A RF 20 1, N2 [00 e N4 N3 30 N4 30 N2

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MILLST0hT. UNIT 10, 2 GAMMA SURVEY ELEVATION 20'6" B = Before Shield erec/hr A = After Shield ~7 RF = Reduction Factor R = Rem /hr RF F C:wT B A' N1 8R 1 7R 5

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r N2 8R 1.7R 5 N 20' 8' N3 BR N4 SR 1.7R 5 N5 10R 1.7R 6 [ p N6 L50 20 22 a 2& b25 10 22 N7 ' 25 10 22 N8 C _N15.N2 .N16 . N1 o N17 ' .N1B N9 1R 200 5 N9 e N10 4R 600 7 N11 2.5R 400 6 L.5R I I

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N19 1R 50 20 I N20 B0 20 9 4 f N21 1.1R 40 27 T F N22 G00 20 20 N23 - y-m N23 350 15 23 6 N7 ~ 94 e .Ll. 11J N24 f.50 17 26 N25 '50 25 18 EXTRAPOLATD TO 100% Pob'ER (2700 MTH) j (~ MSD ON 13% AND 50% SURVEYS ,f. a-

ti1LLST0hT, UNIT 10. 2 CAMMA SURVEY ILtVATION 14'6" B = Before Shield A - After Shield urem/hr RF = Reduction Factor R DULTS Po wT B A RF !:1 gn N6 N2 50 6 8 ^ N3 60 25 2 US eN7 5 130 8 16 l { N6 50 25 2 N7 50 8 6 O \\ 8 NO N9 t yl a N8 . N4 ) y o N9 O N3 e I l T Ul N2 *ED ge-on {': c..:) N EXTRAPOIATED TO 100% PO'n'ER (2700 MkTil EASED on 13% AND 50 SURVEYS l \\

'ilLL>IONE UNIT 20. 2 CAMMA SURVEY ELEVATION -3 '6" E

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A RF N1 15 e N2 20 24 0 N1 N3 40 20 2 4 II I N4 l 40 6 7 )Q N8 N5 to N6 30 1 10 3 sc e 8 2' 50 280 0 N9 w7 e NB l-20 W 2- ,N10 / N9 \\\\ N10 N11 [ ~ N12 l ax j / l h4 N11 s \\\\ / /

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c ELivATOR S H5 'N6 e Er3APOLATED TO 100% PO'a?.R (2700 KC4) BASED ON 13% AND 50% SURVEYS Id. d , hf bOSU ;d [b 7 h MdOMi,hy 7a

., s MILLSIONE UNIT 10. 2 GA!OM SURVEY ELEVATION 38'6" s O crem/hr PIPECM Alf R E SUL T S ( Po'MT B A RF N1 NI 2.5 e N2 ,e

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12 o N7 N6 N5 y, 6 N8 \\ N6 * / ( i I CCNT AlwutwT I ~ l i l B = Before Shield A = After Shield PJ. Reduction Factor _"'t " m.T.ry p p n m q 7"3 Q j';) - ")' ",t' _ ' J,7 :. !) ) :,<, l ' i. ...t._,!,.. 1 r, ....t, .d. ; - i i ;. '. 4,\\ i, d... j ;j b '.J lf(l tj p~ 4 ud 1 U 6 - s. EXTRAPOLATED TO 100% PO WR (2700 E*IH) BASED ON 13% A10 50% SURVEYS 8 _}}

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