ML20148F223

Discusses 720516 Proposed Change 100 & 720518 Supplemental Info Re Control Rod Withdrawal Program Mods.Authorizes Control Program Change Per 10CFR50.59

ML20148F223
Person / Time
Site:	Yankee Rowe
Issue date:	05/18/1972
From:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
To:	Vandenburgh D YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8011040722
Download: ML20148F223 (4)

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D'~- y DISTRIBUTION L$

• W. Dooly, DR R. Engelken (3)

H. K. Shapar, OGC h@.

9 MAY 181972 N. Dube (5)

, J. R. Buchanan, ORNL g%

T. W. Laughlin, DTIE @5 Docket No. 50-29 THIS DOCUMEt1T C0tlTAl!4S AEC PDR - ~ - '

POOR QUAUTY PAGES g3 (

J ocket File "

.-DR Rc ading - gf L Reading Yankee Atomic Electric C m Br nch Reading  :

ATIth Mr. Donald E. Vandenburgh Vice President D. J. Skovholt p[l .

T. J. Carter 20 Turnpike Road R. J. Scheme:

Westboro, Massachusetts 01581 Change ho.100 ABurger . 'b>

License No. DPR-3 SATeets '#

l Gentlemen: ACRS (16) ..

R. Boyd This refers to your Proposed Change No. 100, dated May 16, 1972, R. DeYoung ard supplemental infonnation contained in your teletype of g&.mp '

May 18, 1972, requesting authorization of a change in the TechnicalRHVollmer Specifications appended to License No. DPR-3 for the Yankee reactor.

'Ibe proposed change would modify the control rod withdrawal program to allow operating the reactor with one of the 24 control rods s inoperable, gj 9M The infomation you have submitted indicates that during the Core X control md drop testing program you detemined that control rod h*

No.18 (located in the Shutdown Group D) exhibited erratic perfor- L I-mance end you concluded that this rod must be considered to be f.g inoperable. All other 23 control rods dropped in less than 2.4 y secords consistent with the value that you have used in the 41 reanalyses of accidents for Core X operations. 5 QL To meet the specified shutdown rargin with control rod No.18 )$

inoperable, you propose the revised contml rod withdrawal program i shown on Picure 103-5 in Proposed Change No.100 This progran re- d.P quires full withdrawal of Control Rod Group B (ccmpared with the D presently cpecified 50 inches withdrawal limit); it also requires 6 s 35 inches withdrawal of Cont"o1 Group A for allowing the reactor to attain criticality. The additional control rod withdrawals are .$

provided to offaaet the shutdown reactivity assumed to be unavailable frcm the inoperable control rod No.18. You have also detennined that b(

M the additional control rod withdra> t1 must be compensated by adding more boron to the reactor coolant to an increased boron concentratim of M@

w;.d about 2350 p;n at zero power.  %

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We have reviewed the infomation you have submitted on your evaluation of the safety consicerations associated with the change in the control %g rod dithdrawal program, including 'he effects on accidents oralyzed g.

u eciemly. Additicr.1 conW1 rod "itMrn m1 ment"y P=

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C 4 Yankee Atatic Electric Ccopany MAY 18 I97Z 1l the hot channel factors as determined previously in the thermal and hydrnulic analysis for Core X. We have therefore concluded that the change in the control rod insertion limits win not decrease the Core X margins of the hot channel factors or the D!B ratios. The added control rod withdrawal in conjunction with the' needed increase in the boron concentration will result in operational restriction on ,

reactor powcr at about 83% of licensed power and consequent decrease of the reactor coolant average terperature from 530 F to 514 F. This -

will result in an increase of important margins of safety. Further t increase of boron in the reactor coolant and the increase in control 4 tud withdrawal would affect only the boron dilution accident assumed to occur when the reactor is at full power. Your reanalysis of this  ;

accident ehws that the increase in the reactivity addition during u the accid.ent that results in an increase of the D:0 ratio for operation 1 with 4 loops end a decrease of the DNB ratio fro 11.92 to 1.88. We conclude that this decrease is not significant com ared with the re- a quired F B ratio of 1.3. <

We have also reviewed the control red drop tires of selected rods, .

measured during startup testing of Cores VI thmugh X. We have con- e cluded that these data do not reveal a significant trend of deterioration i+

of control rod performance over a nu d er of years. J!cwever, to assure continued confidence in the obility of the control rods to perfom k

Edg the intended function when needed you will increase the control rod surveillance program in addition to continuing the required rod j $,

exercises during reactor operation. During pericds of May 27-28, June 10-11 4. i and July 1-2, 1972, you will perfom rod drop testing of the 23 control rods with the reactor in the hot standby condition. An increase in the W

P measur_d drop tire of any rod of nore than 0.3 second conpared with the i?

highect drop time measured during the 3 consecutive test drops during }l Core X startup testing shall be cause to suspect abnormal deterioration in the perfomance of this rod. Yankee shall promptly notify the k

ply Cotmission, investigate the rod perfornance deterioration and submit a report on the findings. To rect lir.iting conditions for operation, $gg the measurcd drop tine of any rod shall not exceed 2.4 seconds. Within g g,

30 days following the control rod drop testing on July 1-2, 1972, Y d ee will submit a proposed progran for continued routine control rod y surveillance. In addition, Yankee will perfom rod drop testing during M July 29-30, 1972, and every fourth weekend thereafter, unless n revised fg y

schedule has been approved by the Canission prior to that time. We conclude that the pivposed plan for control rod surveillance is acceptable.

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fem AIC-3Ia gRev,9 53) AECM 0240 u t seneresar reintnie orren i ,,se o-se.. sis g

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F Yankoo Atomic Electric Cmpany MAY 181972

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l We have concluded that the proposed change does not involve =; '

significant hazards considerations not described or implicit in the Final Safety Ant 0ysis Report, ard that the health and safety of the public will not be endangered by operation of the Yankee reactor in ,.

the manner proposed.

Accon11ngly, pursuant to Section 50.59 of 10 CPR Part 50, the control i rod withdrawal program is changed as in11cated in the attached Figure 103-5. 4 i

'y" Sincerely, 4 n

/s/ r Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing

Enclosure:

Figure 103-5 x

cc: C, ,Q;nne Blinn, Esquire Day, Derry & Iknmit! '

Counselors at Inw 1 Constitution Plaza l'artford, Connecticut 06103 '

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