ML20148H105
| ML20148H105 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/16/1972 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8011170182 | |
| Download: ML20148H105 (4) | |
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T.7% \\ S7 TIME 2\\30 PM DATE\\MAY 16, 1972 USMc Lt MAYl 61972 c>-75 i
1972 WU 16 PM 3 18 '0, ufL SECTION g mesy
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UNITED STATES ATOMIC ENERGY COMMISSION 4
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MAY161SI26 TA A7 ENTION\\
DIVISION OF REACTOR LICENSING
,S. ATClllC Ensact C1"is! SCION
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LICENSE NO. DPR-3 \\ DOCKET NO. 50-29\\
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KRSUANT TO SECTION 50-29 07 THE COMMISSION \\S REGULATIONS, YANKEE ATO::I ELECTRIC COMPANY HEREBY RECUESTS AUTHORIZATION TO MAKE T'E TCLLOUING CHANGE \\
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?.:?05ED CHANGE \\
REFERENCE IS MADI. TO SECTION 400 07 THE LICENSE A??LICATION, SATETY ANALYSIS, PARTICULARLY PAGE 400\\2 AND TO
?A?.AG?.A?H D.2.D OF THE TECHNICAL SPECIFICATIONS ATTACHED AS
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.??I:CIX A TO THE LICENSE AND AS AMENDED IN PROPOSED CHANGE NO. 99.
- C ?ROPOSE THE 70LLOUING\\
"IFERATION OF THE YANKEE REACTOR AT RIDUCID OUTPUT, INCREASED 5"?.7EILLANCE ANI OPERATING RESTRICTIONS, A HIGHER MAIN COOLANT i
SCE3:' 00" CENTRATION, REDUCED MA'IN COOLANT AV;: RAGE TEMPERATURE AND f
PAGE *1 2.I 07 TME 24 CONTROL RODS CAPABLE OF DROPPING IN LESS THAN 2.4 2678 i
ZZ00=S.a 8011170 / M TfflS DOCUMENT CONTAINS POOR QUAUTY PAGES l
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hEASO,NFORCHANGE\\ DURIbJTHECONTROLR0DEXERCISd(.NDDROP l
.T[ME. TESTING. PROGRAM, DIFF1CULTY WAS INCOUNTERED WITH. CONTROL
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ROD NO. 18, LOCATED IN SHUTDOUN GROUP D.
A DETAILED TEST PRO-GRAM WAS CONDUCTED.
RESUL7's OF THE TEST PROGRAM REVEkLED THAT CONTROL ROD'NO. 18 CAN BE WITHDRAUN FROM THE CORE, BUT DOES NOT PROPERLY DROP INTO THE CORE.
DUE TO THIS FACT, YANKEE HAS CHOSEN i
T0 ' COMPENSATE FOR THE SHUTDOWN REQUIREMENTS OF C' NTROL ROD NO. 18 i
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BY-ADDING THE EQUIVALENT OF THE CALCULATED 1-1/2\\ DELTA K/K WORTH i
0F THE-MOST WORTHY CONTROL ROD AS FOLLOWSN 1.
REDUCING PLANT OUTPUT PLANT OUTPUT SHALL BE LIMITED TO S3\\ OF FULL POWER.
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2.
INCREASING THE MAIN COOLANT SORON CONCENTRATION AND INCREASING THE CONTROL ROD WITHDRAWAL PROGRAM I
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I FIGURE 103-5 ALLOWS THE PLANT TC ACHIEVE CRITICALITY UITH CONTROL ROD GROUP B AT 50 -INCHES.
THIS RESTRICTION HAS BEEN INCREASED TO ALLOW CRITICALITY WITH CONTROL ROD GROUP A 35 INCHES \\SEE ATTACHED REVISED FIGURE \\.
TO ACCOMPLISH THIS AND ADD A PORTION OF THE REQUIRED SHUTDOWN, THE MAIN COOLANT BORON CONCENTRATION HAS BIEN INCREASED TO APPROXIMATELY 2350 PPM AT 2ERO POWER.
A REANALYSIS OF.
THE BORON DILUTION ACCIDENT AT 2400 PPM AND FULL POUER HAS BEEN COMPLETED.
THE FULL POW'ER BORON DILUTION REACTIVITY ADDITION RATE DURING FOUR LOOP OPERATION INCREASES FROM 9.4 X 10-6 DELTA K/K PER SECOND AT. 2000 PPM TO 11.3 X 10-6 DELTA K/K PIR SECOND AT 240C PPM.
REFERRING TO FIGURE 401-1, IT IS SIEN THAT THE MINIMUM DND RATIO DURING THE TRANSIENT ACTUALLY IMPROVES, COING FROM 1.61 TO 1.66.
FOR THREE. LOOP OPERATION THE REACTIVITY ADDITION RATE DURING A SORON DILUTION INCIDENT INCREASES FROM 10.7 X 1C-6 DELTA K/K ?IR SECOND. TO 12.8 X 10-6 DELTA M/K PER SECOND.
FROM FIGURE
rsr Wo. 38, LOCATED It! SHUTDOUN CROUP D.
A DETAILED TIST PRO-1 CRAM WA3 CONDUCTED.
RESULTS OF THE TEST PROGRAM REVEALED THAT CONTROL ROD NO.
IS CAtJ BE WITHDRAUN FROM THE CORE, BUT DOES NOT PROPERL'i DROP INTO THE CORE.
DUE TO THIS FACT, YANKIE HAS CMOSIfl TO COMPFN3 ATE FOR THE SHU7DOUN REQUIREMENTS OF CONTROL ROD NO 18 BY ADDIrlG THE EQUIVALENT OF THE CALCULATED 1-1/2\\ DELTA K/K WOR OF THE MOST UORTHY CONTROL ROD AS FOLLOWS\\
1.
REDUCING PLANT OUTPUT PLANT OUTPUT SHALL DE LIMITED TO 83\\ OF FULL POWER.
2.
IrlCREASIt1C THE MAIN COOLANT DOR 0ll C0t!CENTRATIOff AND INCREASItlC THE C0tlTROL ROD WITHDRAUAL PROGRAM FIGURE 103-5 ALLOWS THE PLANT TO ACHIEVE CRITICALITY UITH CONTRO ROD GROUP b AT 50-INCHES.
THIS RESTHICTION HAS BEEN INCREASED TO ALLOW CRITICALITY UITH CONTROL ROD CROUP A 35 ItlCHES \\SEE ATTA REVISED FIGURE \\.
TO ACCOMPLISH THIS AND ADD A PORTIO!! 0F THE REQUIRED SHUTDOWN, THE MAIfl COOLANT DORON CONCEtlTRATION HAS 3EEt!
INCREASED TO APPROXIMATELY 2350 PPM AT ZERO POUER.
A RIAt!ALYSIS OF DIE BORON DILUTION ACCIDENT AT 2400 PPM AND FULL POUER HAS BEEN COMPLETED.
THE FULL POWER BORON DILUTION REACTIVITY ADDITION RATE DURING FOUR LOOP OPERATI0fl IflCREASES FROM 9.4 X 1G-6 DELTA K/K PER SECOND AT 2000 PPM TO 11.3 X 10-6 DELTA K/K PER SEC0f 2400 P'M.
REFERRIflG TO FIGURE 401-1, IT IS SEEN THAT THE MIt!IMU" DND RATIO DURIllG THE TRANSIENT ACTUALLY IMPROVE 3, GOING FROM 1.61 TO 1. 66.
FOR THREE LOOP OPERATION THE REACTIVITY ADDITI0ff RATE DURING A BORON DILUTION IrlCIDENT INCREASES FROM 10.7 X 1C-6 DE K/K PER SECOND TO 12.8 X 10-6 DELTA K/K PER SECOND.
FR0" FIGURE 401-2 IT IS SEEN THAT THE MItJIMUM Dt!B RATIO DURING THE TRANSIE{
DECREASES FROM 1.92 TO 1.S8.
Ifl EITHER MODE OF OPER ATION, A L ARGI FARCIN TO DNB STILL EXISTS.
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'l pkEDSINCETHEINITIALCONDITIONSDONOT. CHANGE.
3.
RIDUCING THE OPERATING AVERAGE-TEMPERATURE
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i THE MAIN COOLANT AVERAGE TEMPERATURE Is REDUCED FROM 530 DEGREE F TO 514 DEGREE F.
f 4.
INCREASING THE SURVEILLANCE PROGRAM I
1 A.
' EXERCISE - THE NORMAL CONTROL ROD EXERCISE PROGRAM SHALL BE CONT,I.NUED.
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CONTROL ROD DROPS - THI PLANT WILL BE TAHEN OFF THE LINE AND CONTROL ROD DROP TIMES MEASURED AS FOL'LOUS\\
A\\ THE FIRST UIEKEND AFTER FIVE EQUIVALENT FULL POWER DAYS.
l B\\
THEN THI FIRST WEEHEND AFTER NINETEEN EQUIVALENT FULL i
POWER DAYS.
j C\\ THE RISULTS.07 THE DROP TIMES SHALL BE ANALY2ED FOR SUBSTANTI AL CHANGES OR INCREASES IN TH\\ TREND.
IF ANALYSES CF THE DATA REVEAL THAT ADDITIONAL CONTROL RCD DIFFICULTIES ARE DEVELOPING THE U.S. A.E.C.
SHALL BE NOTIFIED.
.i D\\ IF NO SUSSTANTI AL CHANGES OR TRENM; ARE OBSERVED, i
l CONTROL ROD DROP TIMES SHALL BE OBTAINED WITHIN i
PA6C + 3 I
2678 EVERY SIXTY DAYS THEREAFTER.
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'VII, VIII, IX AND X HAS DEEN COMPLETED.
THE RESULTS OF TPE 00?}TR6L HDD CROP TIME REVIEU INDICATES T}IAT ONLY A SLIG}lT TREND
.IN TIME CAN SE OBSERVER ON THE AVERACE CONTROL ROD DROP TIMES FOR FACH CORE.
CORE AVG. DROP TIME - SUMMATION 24 DROP TIMES VI 1.91 24 VII 1.53 VIII 1.56 IX 1.59 X
1.79 AS A RESULT OF TME DETAILED REVIEU OF CONTROL R0D DROP TIMES, THE REVIEW OF CORE X ACCIDENT ANALYSES AND TPE PROPOSED MODE OF OPERATION, IT IS OUR OPINION TH AT TFE PLANT CAN LE SAFELY OPERATED AT THE PRO-POSED REDUCED "OUER LEVEL FOR TPE DllRATION OF CORE X.
SAFETY C0!:SIDERAT!ON\\
IN OUR OPINION, T)'E PROPOSED CPANGE DOES NOT PRESENT SIGNIFICANT PAZ ARD CONSIDERATIONS NOT DESCRIDED OR IMPLICIT IN THE LICENSE AFPLICATION AS AMENDED.
SCHEDULE OF CHA!:CEN TPIS CHANGE WILL DE PUT INTO EFFECT UPON RE-CEIPT OF YOUR APPROVAL.
THE PLANT REFUELING AND LOW POUER START-UP TEST PROGRAM HAVE DEEN COMPLETED.
TM.i PLANT AWAITS APPROVAL 0l THIS MATTER IN ORDER TO PROCEED WITH POWER OPER ATI0tl.
DONALD E. VANDENBURCH, VICE PRESIDENT, YANHEE ATOMIC ILECTRIC CO.
T}'E END ---
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