ML19242A184
| 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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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 j RS, INp (MISS) MARY A. SIMP N
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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/
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MILLSTONE UNIT NO. 2 OPERATING HISTORY L .1 (MDC CAPACITY FACTOR, BASED Ori 796 MDC NET = 66.6%) i OPERATING LICENSE ISSUED -- AUGUST 1, 1975
> .NITIAL CRITICALITY -- OCTOBER 17, 1975
'MMERCIAL OPERATION -- DECEMBER 26, 1975
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-t IESEL GENERATOR REPLACEMENTT OU. AGE (3.5 WEEKS)
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%)
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1 s: ~ ~I CALITY -- APRIL 21, 1978
< Powan -- MAY 8, 1978 DND REFUELING (10.5 WEEKS) iRCH 10, 1979 - MAY 22, 1979
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. hRE 2560 fu!r/5tQ^~ 2560tiWr/51100F I 2700 TNT /5490F
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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
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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
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CONDENSATE FLOW 7,927,000 tsS/HR 7,893,300 LBS/HR 8,367,700 Las/HR
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c x.. TOTAL llEAT REJECTED 5.83 x 10 9btu /HR 5.82"x 109 BTuhm 6.13 x 109Bru/HR '
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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
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MILLST0f1E POINT II CYCLE 3 CORE LOADItiG INITIAL TOTAL IfilTIAL AVERAGE NUMBER SHIM
/6 0 ! fiUMBER OF Ef1RICHMEliT BURfiUP* OF LOA 1ING TOTAL FUEL D7 ' ' Ti ASSEMBLIES WT% U-235 Mild /PRU SHIMS WT% BeC SHIFTS RODS 25,400 12 2.7 60 820 5 2.33 19,700 0 --- 0 7,040
- 40 2.82 24,800 12 .83 192 2,624
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16 2.82 24,900 12 .46 144 1,968 12 2.82 7,600 0 --- 0 8,448 f 48 3.03 0 --- 0 - 4,224
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24 2.73 .,_l,0, 6 00, , 3.24 0 0 --- 0 8,448
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CYCLE 2 LEfiGTH OF 8,700 fidD/T. JCLE 3 LENGTH: 10200 MJD/MT. .
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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
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PEAKING FACTORS 1.440 1.598 FR Fxy 1.546 1.584 l: !L:l
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MP2 LOW PO'n'ER PHYSICS TEST RESULTS MEASURED PREDICTED CBC (PPM) AR0 1212 (70 135) 1205 (AR0) ARI 888 861 ITC (x10'4tgo/0F) 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
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MP2 THERMAL HYDRAULIC PARAMETERS CYCLE 2 CYCLE 3 PARAMETER _ UNITS Mwt 2560 2700 CORE POWER
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O F 542 549 INLET TEMPERATURE 6 135.0 133.7 CORE FLOW RATE x10 LBM/FR 2 177,700 183,000 CORE AVERAGE HEAT FLUX BTU /HR-FT FT 2 47,940 49,100 TOTAL HEAT TRANSFER AREA KW/FT 5.99 6.17 AVERAGE LINEAR HEAT RATE
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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)
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- 2. SMALL BREAK MODEL - MODELIf;G CHAf1GES TO CEFLASH - 4AS I 3. RMS STATISTICAL COMBINATION OF UNCERTAINTIES:
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- THERMAL PARGIll INPUT SYSTEM CREDIT CHAfiGES:
- 1. CORE POWER 2700 MJt (CYCLE 2 - 2560 KJt)
- 2. T INLET 549 F (CYCLE 2 - 542 F)
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- 3. SCRAM TIME 3.1 SEC (CYCLE 2 - 2.75 SEC) .
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- 4. UNCERTAINTIES 6% ON Fr 7% ON Fq : i [, /00
- 5. RCP SPEED SENSING: CREDIT FOR RCPSS TRIP IN 4 PUMP LOF If4CIDENT
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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: REANALYZED CONTROL ELEMENT ASSEMBLY WITHDRAWAL REANALYZED BORON DILUTI0ri NOT ANALYZED STARTUP 0F AN INACTIVE REACTOR C00LAfiT PUMP 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 REANALYZED LOSS OF COOLANT FLOW . ANTICIPATED GPERATIONAL OCCURRENCES WHICH ARE DEPENDENT Oft IllITIAL OVERPOWER MARGIN FOR PROTECTION AGAINST VIOLATION OF SAFDLs: REANALYZED LOSS OF COOLANT FLOW REANALYZED FULL LENGTH CEA DROP
- NOT ANALYZED PART LENGTH CEA DROP PART LEt!GTH CEA MALPOSITIONIllG NOT ANALYZED REANALYZED TRANSIEtiTS RESULTING FROM MALFU!1CTION OF ONE STEAM GENERATOR POSTULATED ACCIDENTS:
REANALYZED CEA EJECTION REANALYZED STEAM LINE RUPTURE REANALYZED STEAM GENERATOR TUBE RUPTURE REANALYZED SEIZED ROTOR
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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
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MIN DNBR - 1.33 , _ _ _ ,, MAX PRESSURE - 2555 PSIA
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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
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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
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- . MP2 CYCLE 3 LARGE BREAK LOCA ANALYSIS PCT BREAK CYCLE 2 CYCLE 3 1.0 DES /PD 2110 F 2079 F
.8 DES /PD 21600F 2077 F
.6 DES /PD 1950 F 1.0 DEG/PD 2105 F 20800F U
.8 DEG/PD 2111 F 2081 F
.6 DEG/PD 19480F PLHR 15.6 KW/FT 15.6 KW/FT MAXIMUM LOCAL CLAD OXIDATION (10.7% (16.0%
MAXIMUM CORE WIDE OXIDATION (.58% (.73%
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MP2 SMALL BREAK LOCA R$5ULTS CYCLE 2 CYCLE 3 BREAK AREA PCT PCT
.5 10750F 1629 F
.2 15620F 16120F
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.02 662 F 558 F
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TABLE I LOW FLOW TRIP FUNCTI0tlit0M!NAL CHARACTERISTICS
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RCPSS TRIP FUNCTION PERFORMANCE C11ARACTERISTICS LOW FLOW 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 93% Nominal Trip Setpoint 91.7% 650 msec 450 msec Overall System Response Time
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MILLSTONE UNIT PC. 2 NEUTRON SURVEY ELEVATION 38'6" B = Before Shield A = After Shield trem/hr RF = Reduction Factor . ~7 R = Thousands (R/hr) Fo w1 B A RF N1 60R 1R 60 y
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MILLSTONE UNIT No. 2 NWTRON SURVEY ELEVATION 14 '6" arem/hr R EsuLT5 M NT B A RF
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ELEVATION 38'6" crem/hr Ps P E CM a! E s RESULTS N PO'N T IB A RF 20 1, N2 [00 e N4 N3 30
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GAMMA SURVEY ELEVATION 20'6" B = Before Shield erec/hr A = After Shield ~7 RF = Reduction Factor ,,,, R = Rem /hr , F C:wT B A' RF N1 8R 1 7R 5 Q8' r ;p N2 8R 1.7R 5 N 20' -
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