ML20140H496

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Revised Pages for SEFOR TS Addendum to Proposed Change 3
ML20140H496
Person / Time
Site: 05000231
Issue date: 09/08/1970
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GENERAL ELECTRIC CO.
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References
FOIA-97-34 NUDOCS 9705130163
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ATTACHMENT A l

REVISED PAGES FOR THE SEFOR TECHNICAL SPECIFICATIONS ADDENDUM TO j 1

PROPOSED CHANGE No. 3 I l

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9705130163 970505 PDR FOIA VARADY97-34 PDR 1

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d I. No fuel rods shall be 'p laced in the center drywell.

J. Fissi6n chambers, experimental foils or oxide fuel samples having a total reactivity worth of less than 60c and containing a total of not more than 0.5 Kg fissile material may be placed in the l

t center channel (or in a drywell in the center channel) for irradia-tion at power levels equal to or less than 100 KWt. Experimental

l. foils containing less than 10 mg of fissile material may be irradiated
at reactor levels above 100 KWt.

K. Fuel rods which have defects as defined below shall not be reinserted l

in the core: l l-

l. 1. Cladding rupture, cladding perforation, or other observable defects which may cast reasonable doubt on the integrity of the rods.
2. Local swelling of the cladding in excess of 10 mils ur bowing 1 of the rod sufficient to prevent reinsertion of the rod into the core.

l 3. An increase of more than 1/2 inch in the column height of l l either fuel segment.

L. The gross gamma cover gas monitor shall be demonstrated to be capable of detecting a fission gas release equivalent to about 1% of the 20 MWt equilibrium inventory in a fuel rod before the j reactor is operated above 10 MWt. If such sensitivity is not demonstrated, a more sensitive monitor shall be installed.

M. If the gross gamma monitor becomes inoperable, the reactor shall

! be shut down, except under the following circumstances:

If a reactor test is in progress, (other than FRED transient test I

program) and the monitor should fail, reactor operation may con-

, tinue for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, if no unexpected changes in cover gas activity indicative of changing fuel condition have been observed just pre-ceding the failure, and if cover. gas samples are taken for spectral analysis at intervals of approximately four hours.

N. The reactor power shall be limited such that the maximum linear power density of a guinea pig rod located under the innermost port

! does not , exceed a value corresponding to the linear power density of the standard hot fuel rod if the reactor were operated at a power of 22 MWt with 600 fuel rods in the core. "

3.3-2 Proposed Change No. 3 September 8, 1970

. ,.,-4 ,

(1) observe the continuous monitoring system under operating condi-tions to diagnose the cause of failure or mal-cperation of the

. syst'em;

(2) permit an orderly completion of a test series, so that tests .com-pleted prior to the failure do not have to be repeated; (3) plan for an orderJy shutdown of the reactor.

During periods of reactor operation when the continuous fission gas monitor is inoperable, batch samples will be taken at intervals of approximately four hours. This sampling frequency will assure that any trends that might i develop will be identified.

1 Guinea pig rods located under the innermost refueling ports operate at a ,

power density 151 higher than that of the standard hot rod in the core.(

It is desirable to leave these rods in the core during operation up to the design power level of 20 MWt to demonstrate the expected margin with respect to linear power density in the SEMR fuel rods. If guinea pig rcr's are located under the innermost ports during reactor operation above 17.5 MWe, the reactor power will be limited, based on the total number of fuel rods in the core, so that the maximum linear power density of a guinea pig fuel rod-does not exceed the maximum linear power density for which the safety of standard fuel' rods has been assessed.( ) 'The reactor power limit for such operation shall be determined by the equation:

P g

=

22N/(600 X) where: P g

= maximum allowable power, MWr.

N = total number of ftel rods in the core 600 = The minimum allowable 1. umber of fuel rods in the Core.

X = The ratio of guinea pig rod power to the power of

- a s,tandard rod located nearest the center of the core. ,

. ,b I For a core loading of 636 fuel rods (used during initial operation to 10 MWt) l I

.g.

and guinea pig rods located under the innermost refueling ports (X = 1.15),

the value of P g would be 20.3 MWt. _

l

! 3.3-7 l a Proposed Change No. 3 September 8, 1970 G, , j

j References,

  • l (1) , SEFOR FDSAR,, Volume I, Para. 4.5.3.1, pp 4-50 and 4-51

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(2). SEFOR FDSAR, Volume II, Para. 12.3.6, pp 12-15 and 1.-16.

(3) SEFOR FDSAR, Para. 16.4.2.5 and 16.4.2.6.1.1, pp 16-26 and 16-28.

(4) SEFOR FDSAR, Para. 16.2.1, p 16-4.

(5) - SEPOR FDSAR, Appendix B, Para. B ,, p B-3.  ;

(6) SEFOR FDSAR, Supplement 10, p 3-10.

1

- ( 7) SEFOR FDSAR, Volume-I, Para. 4.2.2.2.2, p 4-2. ,

1 (8)~ SEPOR FDSAR, Volume 11, Para. 12.2.1, p 12-3.

(9) SEFOR FDSAR, Volume II, Para.16.2.4.3.

(10) SEFOR FDSAR, Supplement 21, pp 2, 3.

(11).SEFOR FDSAR, Supplement 3.

(12) SEFOR FDSAR, Supplement 21, pp 1-17.

(13) SEFOR FDSAR, Volume I, Para. 4.2.2.4, p 4-9.

! (14) SEFOR Technical Specifications, Bases, p 2.1-3.

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L Proposed Change No. 3 September 8, 1970

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1 l DEAR MR. MORRIS \ ,

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PROPOSED CHANGE NO. 3 TO THE SEFOR TECHNICAL SPECIFICATIONS WAS 1

jiUBMITTED TO YOU ON JULY 8, 1970. AS A RESULT OF DISCUSSIONS WITH l . . ..
% . MEMBERS OF YOUR STATT, WE HAVE DECIDED TO PROPOSE ADDITIONAL CHANCES
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I au . VMICH SN00LD BE CONSIDERED WITH THE JULT 5 SUBMITTAL.

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J . ,1 I y' 470RTY-TNREE COPIES OF THESE ADDITIONAL CHANCES ARE TORTHCOMINC. PLEASE j

.MAlg, A, M'. ADD TiESE PACES TO THE PREVIOUSLY SUBMIT

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ADDENDUM TO PROPOSED CH'ANCE NO. 3 TOR THE SOUTHWEST EXPERI-MENT,AL TAST OXIDE REACTOR

, RE\- LICENSE 'DR-15

, DOCKET 50-231 I

I GENERAL ELECTRIC CO.

310 DECUIGNE DRIVE ShMNYVALE, CALIT. 9408 5 i .,s, ,

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,,' ADDENDUN TO PROPOSED CHANGE NO. 3 TOR THE SOUTNVEST EXPERIMENTAL TAST DVcWIDEREACT98 A. <

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' SUDMITTEDl0N JULT4,1979. TKIS ADDENWN PROPOSES ADDITIONAL CNANCES

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c,TNE TECIstISALi !TICATI665[SE'CRANSED BT SUBSTI11rTINS. PAWES-

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It) .THE, MARCIN ON THE ENC' OSED PAGES, s W

. 1WF III. DISCUSSION 1

! 8 CENERAL ELECTkTC FEELS THAT THE INFORMATION PRESENTED IN PROPOSED CHANG 4 NO.,3, DATID JULY 8, 1970, PROVIDES VALID AND SUFFICIENT REASONS FOR PERMITTING Ti'E CUINEA PIC RODS To REMAIN UNDER THE INNERMOST REFUELINC i

j PORTS WHILE THE SEACTOR IS OPERATED AT THE DESIGN POWER LEVEL. WE 4

ALSO FEEL THAT SUCH OPERATION WILL PROVIDE IMPORTANT INFORMATION FOR

i. BOTH THE SEFOR PROCRAM AND THE LMFBR PROCRAM.

1 i

i j THE SAFETY EVALUATION OF PROPOSED CHANGE NO. 3 WAS BASED ON THE

{ POSSIBILITY OF OPERATINS AT 22 MVT. HOWEVER, THE MAXIMUM PLANNED

, POWER LEVEL IS ONLY 20 MWT. IF THE PROPOSED CHANCE IS APPROVED, THE HICH FLUX TRIP LEVEL FOR THE SAFETY SYSTEM VILL BE REDUCED To i

ThE VALUE OF PMAX, CALCULATED AS EXPLAINED IN THE BASES FOR PROPOSED SPECIFICATI9N 3.3.N, WHENEVER THE REACTOR IS OPERATED AB0VE i

i 17.5 MWT AND ONE OR NOR: CUINEA PIC RODS ARE LOCATED UNDER TIE"INNERN0ST PORTS. THIS WILL PROVIDE ASSURANCE THAT TE CUINEA

@ PIC RODS ARI NOT OPERATED AT LINEAR POWER DENSITIES CREATER TNAN I

I E TEAT FOR WHICN TE SAFETY OF STANDARD RODS NAS BEEN ASSESSED. \REF.

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l h',fh;p,.Anu..,'.,ai,;{ LEVEL' JET JITEIN 10R 2\[0'T' TE 50VER' LEVEL APPEARS '70 'B 7

l b aFEA31BLE FOR SPECIAL TESTS. ~ NOWEVER, SHOULD'THIS APPRGACH PROVE 4 a. '

l 4* Ts.3E WWFEASISLE,1CENERAL ELECTRIC;WILLsRE-5WBRIT TIE REWIEST '

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ATTACHMENT A t

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. . REV'ISED PAGES FOR THE SETOR TECHNIC AL SPECITICATIONS .

' ADDENDUM TO PROPOSED CHANGE NO. 3 l 1

i NEW PACE \

5 NO RIEL RODS SHALL BE PLACED IN THE CENTER DRYWELL.

J. TISSION CHAMBERS, EXPERIMENTAL TOILS OR OXIDE FUEL SAMPLES HAVING A TOTAL REACTIVITY WORTH OF LESS THAN 60 CENTb AND CONTAININC A TOTAL OF NOT MORE THAN 0.5 KC TISSILE MATERIAL l

MAY BE PLACED IN TE CENTER CHANNEL \0R IN A DRYWELL IN TE

- ', CENTER CllANNEL\ TOR IRRADIATION AT POWER LEVELS EQUAL TO OR

e. I LES$.TNAN 100 KWT. EXPERIMENTAL TOILS CONTAINING LESS TRAN h[, , ,

. 10 MC 0F TISSILE MATERIAL MAY BE IRRABIATED AT REACTOR

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WA FUEL RODS UNICR'MAVE". DEFECTS AS DETINED BELOW SMALL NOT BE

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CLADDING RUPTURE,. CLADDING PERTSRATION, OR OTEER l 9 ,yy h..,9BSERVABLEDETECTSVNICEMATCASTREASONABLEDOUBT en:. ' GN TEE 'INTEGRITT OF THE RODS, y 1 . .

' 2.' . LOCAL SWELLING 0F THE CLABDING IN EICESS OF 10 MILS 7h w $" ' I " 9130VING OF TE ROD SUTTICIENT TO PREVENT RElN-ggts + .

, - SERTION-0T TE R0D INTO TE CORE. ,

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' l,NCIEIME' 0F NORE TRAN $/2 INCN {N TE COLUISI

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" - yM'8ENSWSTRATES, A,N0E SENSITIVE MSNfkfR-SNALL 9EyINSTALLEB. ,

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[CAlelA NONITOR BECOMES IN0PERABLE, TIE REACiDE SEALL

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,m.,.-- aa ="^ v ABO'IE ao MBTo IF SUCH SENSITIVITY IS NOT DEMONSTRATED, A MORE SENSITIVE MONITOR SHALL BE INSTALLED.

M. IT THE GROSS GAMMA MONITOR BECOMES INOPERABLE, THE REACTOR SHALL BE SHUT.DOWN, EXCEPT UNDER THE TOLLOWING CIRCUMSTANCES \

, IF A REACTOR TEST IS IN PROGRESS, \0THER THAN TRED TRANSIENT TEST PROGRArt\ AND THE MONITOR SHOULD FAIL, REACTOR OPERATION MAY CON-

,. TINUE FOR 24 HOURS, OF NO UNEXPECTED CHANCES IN COVER CAS ACTIVITY INDICATIVE- 0F CHANGING RJEL CONDITION HAVE BEEN OBSERVED JUST

, PRECEDING THE TAILURE, AND IT COVER GAS SAMPLES ARE TAKEN FOR l SPECTRAL ANALYSIS AT INTERVALS OT APPROXIMATELY TOUR HOURS.

l N. THE REACTOR POWER SHALL BE LIMITED SUCH THAT THE MAXIMUM LINEAR POWER DENSITY OF A GUINEA PIG ROD LOCATED UNDER THE INNERMOST PORT l DOES NOT EXCEED A VALUE CORRESPONDING TO THE LINEAR POWER DENSITY OF THE STANDARD HOT nlEL ROD IT THE REACTOR WERE OPERATED AT A POWER OF 22 MWT WITH 600 RIEL RODS IN THE CORE.

... g , 3.3-2

i- Pi9POSEB CHANGE NO. 3 J . J '.

j p $EPTEMBER 8, 1970 l

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4 JAflPLES WILL BE TAKEN AT INTEhVALS OF R HOURS. THIS SAMPLING TREQUENCY WILL ASSURE THAT

, ANY TRENDS THAT MICHT DEVELOP WILL BE IDENTIFIED.

t CUINEA PIC RO,DS LOCATED UNDER THE INNERMOST RETUELING PORTS OPERATE AT A POWER DENSITY 15\ HIGHER THAN THAT OF THE STANDARD HOT POD IN THE CORE \ RET. 13\. IT Is DESIRABLE TO LEAVE THESE RODS IN THE CORE DURING

' OPERATION UP TO THE DESIGN P0'wER LEVEL OF 20 MWT TO DEMONSTRATE THE EXPECTED MARCIN WITH RESPECT TO LINEAR POWER DENSITY IN THE SETOE RIEL l NOD S', IT GUINEA PIG RODS ARE. LOCATED UNDER THE INNERMOST PORTS DURING REACTOR OPERATION AE0VE 17.5 MWT, THE REACTOR POWER WILL BE LI-MITED, BASED'ON THE TOTAL NUMBER OF W EL RODS IN THE CORE, SO THAT THE MAXIMUM

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LINEAR POWER DENSITY OF A CUINEA PIC IUEL ROD DOES NOT EXCEED THE MAXIkUM LINEAR POWER DENSITY TOR WHICH THE SAFETY OF STANDARD IUEL l RODS'UASBEENASSESSED\ RET.14\. THE REACTOR POWER LIMIT TOR SUCH OPERATION SHALL BE DETERMINED BY THE EQUATION \

PMAX I 22N/\600 X\

l g-WHERE PMAX - MAXIMUM ALLOWABLE POWER, NWT N - TOTAL NUMBER OT nlEL RODS IN THE CORE

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. .. 600..; . --,. THY MINIMUM ALLOWABLE NUMBER OT nlEL RODS IN THE CORE. ,

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f. 3, X-- THE RATIO OF CUINEA PIC R0D POWER TO THE POWER OF A STANDA 4 c ,, y ... . . . . . ~ . .

a c'/ ./ ,- ROD LOCATED NEAREST THE CENTER OF THE CORE. )

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\X..\ 1.15\, RODS VALUE OF LOCATED PMAX WOULD BE UNDSR 20.3 MsT. THE INNE

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j REFERENCES i I J

I j \1\ SETOR TDSAR, VOLUME I, PARA. 4.5.3.1, PP 4-50 AND 4-51.

N2\ SETOR TDSAR, VOLUME II, PARA. 12.3.6, PP 12-15 AND 12-16.

8

\3\ SETOR TDSAR, PARA. 16.4.2.5 AND 16.4.2.6.1.1, PP 16-26 AND l ~

l 16-28 '

j \4\ S5f0R TDSAR, PARA. 16.2.1, P 10-4 N5\ SETORTDSAR,APPENDIIB,' PARA.B.5,PB-3.

! @ SETOR TDSAR, SUPP!,EMENT 10, P 3-10.

~

NYS' SETOR TDSAR, VOLUME I, PkRA. 4.2'2.2.2, . P 4-2 1

! .\ SETOR TDSAR, VOLUME II, PARA. 12.2.1, P 12'3k -

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l 95i ' SETOR TDSAR, VOLUME,II, PARA.16.2.4.3.

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{ gg,:,h. . ,,. SETOR TBSAR, SUPPLEMENT 21, PP 2, 3.

i {(,, SET 0RTDSAR, SUPPLEMENT 3.

i SETOR TDSAR SUPPL.EMENT 21, PP 1-17.

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i gat;rasAh_vownE If PanA. 4.i;i.=, P 4-9.

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W.p .W,1*N; .JETOR TECHNIVAL SPECITICATIONS, BASES, P 2.1-3.

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