ML20136C722

Discusses Method for Steam Generator B Integrity Checking. WR Stagg 790406 Memo to G Urquhart Re Clarification of Question 1 on once-through Steam Generator B Leak Encl

ML20136C722
Person / Time
Site:	Crane
Issue date:	04/08/1979
From:	Kosiba R BABCOCK & WILCOX CO.
To:	Denise Wilson BABCOCK & WILCOX CO.
References
TM-0947, TM-947, NUDOCS 7910010543
Download: ML20136C722 (8)

Text

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. . TMI DOCUMENTS _

DOCUMENI NO: Y '"

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COPY FADE ON OF DOCUMENT PROYIDED BY METROPOLITAN, EDISON COMPANY.

. Supervisor, Document Control, NRC t

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Tyl$ BABC0CK & WILCOX COMPANY ,

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'. POWER GENERATION GROUP t To l

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Subj. Date STEAM GENERATOR B INTEGRITY . - .

APRIL 8, 1979, 0235

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. ITEM'P.B.110F YOUR ANALYTICAL TASKS FOR BASE PLAN REQUESTED THAT B&W DEVELO?

. A METHOD FOR STEAM GENERATO,R B INTEGRITY CHECKING. B&W JIAS REVIEVED OUR l

. . . 1 KNOWLEDGE OF THE INTEGRITY OF B STEAM GENERATOR AND PRESENT THE FOLLCWING ,

FACTS: ,

I. STRUCTURAL ANALYSIS -

- l 9

)

B&W IIAS PERFORMED A CALCULATION (CALCULATION 32-110467-00) WHICH - )

. DETERMINED TUBE TO SHELL TEMPERATURES OF THE TMI-2 OTSG'S DURING A LCSS'. -l  ;

OF TEEDWATER TRANSIENT FOR THE FIRST 17 HOURS. THIS CALCULATION DETER-MINED THE MAXIMUM TUBE LOAD DEVELOPED. A SUMMATION OF THE RESULTS OF THIS ANALYSIS ARE AS FOLLOWS:

'A. DURING THE FIRST 15 MINUTES OF THE TR NSIENT, THE TUBES,WERE IN .-

. COMPRESSION. THE MAXIMUM CALCULATED COMPRESSIVE LOAD WAS APPROXI-MATELY 525 POUNDS WITH AN ALLOWABLE VALUE OF 850 POUNDS TO PRE'.T.*T BUCKLING.*

B. THE MAXIMUM CALCULATED TENSILE LOAD IN THE FIRST TWO HOURS WAS ALSO l

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. APPROXIMATELY 525 PCUNDS. THE ALLOWABLE TENSILE LOAD FOR A IS 1919 POUNDS AT 300 P. THIS IS THE TIME IN WHICH IT WAS REPORIID THAT THERE WAS A PRIMARY TO SECONDARY LEAK. l

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~. C. THE MAXIMUM CALCULATED TENSILE LOAD OCCURRED AT APPROXIMATELY .

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17 HOURS WHEN THE TUBE LOAD WAS 862 POUNDS AGAIN COMPARED TO THE 1919

{' POUND ALLOWABLE LOAD.

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D. THE MAXIMUM TUBE LOAD OBSERVED DURING THE SMUD RAPID COOLDOWN IN

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MARCH OF 1978. WAS CALCULATED AT 1691 POUNDS TDISILE. THIS IS TWICE ,

THE MAXIMUM NUMBER CALCULATED FOR TMI-2. NO STEAM GDIERATOR DAMAGE OCCURRED DURING THE SNUD 'TRANSID1T.

E. . THE ROLLS USED TO ROLL'THE TUBES TO IHE TUBESHEET HAVE,BEEN TESTED TO SHOW THE CAPABILITY OF HOLDING 1700 POUND TUBE LOAD. THEREFORE, B&W DOES NOT CONSIDER IT FEASIBLE THAT THE LOADS ' SEEN DURING THE  :

' TMI TRANSIENT HAD DAMAGED THE TUBE TO TUBESHEET WELDS.

II. POTENTIAL PRIMARY AND SECONDARY LEAKS

\

B&W HAS ASSESSED ADDITIONAL OTSG B RADIO CHEMICAL DATA WHICH STRONCLY .<

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SUGGESTS THAT THE STEAM GENERATOR IS NOW NOT LEAKING. DATA TAKDi ON r)

( 3/30/79, 3/31/79, AND 4/03/79 INDICATES THAT SOME REACTOR COOLANT (BETWEEN 1 AND 880 GALLONS) WAS INTRODUCED INTO THE B OTSG ON A ONE-SHOT BASIS. THESE VALUES VAR,Y DEPENDENT ON ASSUMED REACTOR COOLANT ACTIVITY.

' ^

TE LATER SAMPLES INDICATE A NORMAL HALF-LIFE DECAY OF THE ACTIVITY WITHIN THE B LOOP. (REFER TO ATTACIDIENT) , l l

III. ALTERNATE MEANS OF INDUCING RADIOACTIVE WATER INTO THE B STEAM CENERATOR POTENTIAL ALTERNATE METHODS ARE SHOWN ON THE ATTACHED SKETCHES. THESE

, ALTERNATE PATHS ARE THE VENT AND DRAIN LINES.

IV. POST-TRANSIENT STEiM GENERATOR PERFORMANCE - -

B&W CONSIDERS THE MOST PERTINENT STEAM CENERATOR INTEGRITY TEST HAS BEEN l .- 1000 PSI DELTA P WHICH HAS BEEN ON THAT UNIT SINCE THE. TRANSIENT. IT IS B&W'S UNDERSTANDING THAT THERE HAS BEEN NO CHANGE IN SECONDARY SIDE -

PRESSURE OR UNPLANNED CHANCES IN SECONDARY SIDE STEAM CENERATOR LEVEL.

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• IF THERE WAS A PRD!ARY.TO SECONDARY LEAK THROUGH THE STEAM CENERATOR,

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WE EEL'IEVE IT SURELY WOULD HAVE BEEN EVIDENT DURING THIS TDCE. THE

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.! NORMAL TECHNIQUE FOR DETECTING SMALL 1 GPM LEAKS IS TO PRESSURIZE

. 'als SECONDARY SI'DE '0F THE STEAM GENERATOR TO 100 PSI.

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SUMMARY

B&W CONSIDERS THE CALCULATIONS PRESDITED'ABOVE THAT THERE IS NO GROSS .

STRUCTURAL DAMAGE TO THE STEAll GENFRATORS. THE TMI-2 UNI,TS DID HAVE A

. .

• COMPLETE, 100% BASELIh*E EDDY CURRENT INSPECTION. HOWEVER, SEVERAL TUBES WITHIN THE B STEAM GENERATOR.HAD NOISY SIGNALS. THEREFORE, IT IS POSSIBLE

.r THAT AN INDIVIDUAL TUBE COULD HAVE LEAKED DURING THE TRANSIENT. HOWEVER, .-

BASED ON THE RADIO CHDIICAL ANAL.YSIS OF THE SA}TLES TAKEN WHILE THE UNIT .

~

i - WAS UNDER 1000 PSI DIFFERENTIAL PRESSURE, WE BELIEVE THAT THERE IS A VERY SMALL CHANCE THAT THE GENERATOR, IN FACT, EAS A LEAK. THEREFORE, WE . -

,D, RECOMMEND THE FOLLOWING ACTION: .

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(* -

1. AS PRECISELY AS POSSIBLE, MONITOR THE STEAM GENERATOR LEVEL FOR ANY

. INDICATION OF PRDIARY TO SECONDARY LEAKS. LEVEL CHANCES CAUSED BY

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. CHANGES IN TDIPERATURE MAY HAVE TO BE ACCOUNTED FOR.

2. CONTINUE TO SAMPLE. AS POSSIBLE, SECONDARY SIDE WATER. THIS SHOULD CONTINUE TO SHOW THE NORMAL DECAY OF THE RADI0 ACTIVE WATER WHICH IS NOW l

+

IN THE B SECONDARY SIDE ASSUMING A ONE SHOT INJECTION. -

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4 THE BABCOCK & WILCOX C0!1 patly POWER GEiERATIOil GROUP .

To l- s (181-2,4 Adder.F.:= ~

L CARY LTTtQlMART .

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• Sub). .i CLARITICATI0t! Oil OTSG "B" LEAK, QUISTI0tt 1

' APRIL 6,1973 5: 00

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- . Je have accessed add.itional "3" OTSG radio chemical data which strongly -

suggest that the S'.G. is not nov 1esking. These data were collected as follovs: . , , . .

- '. 3/30/79 0900 .

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h.2 pCi/ce .

. I-131 -

I-133 2.1 pCi/cc .

0.27 pC1/cc

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. Cs-136 0.022 pC1/cc -

Cs-137 0.028 pC1/cc - -

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• I I-131 2. h 'W i /c c 9 x 10 1 C1/cc

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Cs-134 .lx10-2 g 1/cc ,

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Cs-137 h.2 x 10-2 pegj,, ,

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I-131 2.8 pCi/cc .. ' '. .- -

97xIg-2 pCi/cc

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7e-133 3.9 x10~ uC1/cc .

pCi/cc

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. Cs-134 9 x 10~3 Cs-137 3.6x10-2 UCi/cc

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- . Based on these data our position remains that some reactor coolant (between _

.. I and 880 gallons depending on Vhen) Vas introduced to the "3" OTSC,but that the Unit is,not 1eaking nov. (see cemo - Bell /Levstek to Vomack of h/3/I9). .

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