ML18142A706

Forwarding Revision to Tests Described in Applicant'S 03/27/78 Submittal Questions 6.1.E & 6.1.0 Re the Cycle 8 Fuel Reload

ML18142A706
Person / Time
Site:	Ginna
Issue date:	04/06/1978
From:	White L Rochester Gas & Electric Corp
To:	Ziemann D Office of Nuclear Reactor Regulation
References
Download: ML18142A706 (8)

Text

y rP ~qfff7~8 REGULATORY INFORI"IATION DISTRIBUTION SYSTEN <RIDS)

DISTRIBUTION FOR INCONING NATERIAL 50-244 REC: ZIEMANN D L ORG: WHITE L D DOCDATE: 04/06/78 NRC ROCHESTER GAS 8( ELEC DATE RCVD: 04/i0/78 DOCTYPE: LETTER NOTARIZED'O COPIES RECEIVED

SUBJECT:

LTR i ENCL i FORWARDING REVISIONS TO TESTS DESCRIBED IN APPLICANT"S 03/27/78 SUBNITTAL ON QUESTIONS 6. i. E 5 6. i. G RE THE CYCLE 8 FUEL RELOAD AT SUBJECT FACILITY.

PLANT NANE: RE GINNA UNIT i DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS REVIE}PER DISTRIBUTOR INITIAL: X JN INITIAL: ~

GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE AOOl)

FOR ACTION: BR +4W/7 ENCL INTERNAL: REG FILM4W/EN NRC PDR+~W/ENCL OELD>>LTR ONLY HANAUER+4FW/ENCL CHECK++W/ENCL E I SENHUT+4~W/ENCL SHAO++W/ENCL BAER<4W/ENCL'R BUTLER4<W/ENCL I NES++W/ENCL J COLLINS++M/ENCL J. NCGOUGH44W/ENCL EXTERNAL: I PDR~S ROCHESTER'Y++W/ENCL T I C++W/ENCL NSIC++W/ENCL ACRS CAT B~~W/i6 ENCL DISTRIBUTION: LTR 40 ENCL 39 CONTROL NBR: 78i0i 0022 S I ZE: iP+2P END

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/i E!/1iiE/II/ lllllllliS' HO P'pril llIIIIII/IIIIIl Irlrd ROCHESTER GAS AND ELECTRIC CORPORATION o S9 EAST AVENtIE, ROCHESTER, N.Y. 14649 LEON 0, WHITE, JR. TELEPHONE VICE PRESIDENT AREA COOE 7ld 546-2700 g r.

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n Vl Director 'of Nuclear Reactor Regulation Attn: Mr. D. L. Ziemann,'hic'f Operating Reactor Branch g2 U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Ziemann:

The additional inforjnation regarding the Cycle 8 fuel reload at R. E.,Ginna requested by your March 10, 1978 letter was supplied by letter dated March 27, 1978.'n response to requests by members of your staff, this letter modifies the tests described in our March 27 submittal.

Attached are the revisions to our responses to questions 6.1.e and 6.1.g.

Very truly yours, L. D. Whi , Jr.

o' 7Pgoi0022

Question 6.1.e Provide the details of the regulating control rod group reactivity worth tests. Give the predicted worth of each group to be measured, the stuck rod worth and the predicted total worth for all rods.

What is the acceptance criteria for these tests?

What are the procedures is not met?

if the acceptance criteria Response: The differential worth of banks D, C, B, and A will be measured. From these measurements the integral bank worths can be obtained.

The differential bank worth is measured by first obtaining a critical configuration with the bank of interest, approximately full withdrawn. Then boron dilution is initiated. The bank of interest is then inserted a given number of steps with the reactivity computer monitoring flux and reactivity response. The reactivity response calculated by the reactivity computer is then recorded for the associated change in bank position. This sequence is repeated until the bank is fully inserted. From the resulting data a plot of differential bank worth versus bank position is developed. The integral bank worth will be developed from these data.

The acceptance criteria for these tests are that, the measured individual bank integral worth be within 15% of the predicted values and that the total worth of all four banks be within 10% of the predicted value.

bank worth is not If the criterion on individual met, an evaluation will be per-formed to determine the cause and any potential impacts. If the criterion in total worth of the four banks is not met, additional banks will be measured until the measurement is within 10% of the prediction. This will be continued, if necessary, to measurement at an N-1 rod inserted condition.

The result of an N-1 measurement, with appropriate allowance for measurement uncertainty, will be compared to the value assumed in the Safety Analyses.

The predicted values for the regulating control rod group reactivity worth tests have not yet been calculated but will be presented, as required, in the Summary Report of the Physics Startup Tests.

36

i Question. 6.l.g Provide details of the power coefficient measurement near full power. What methods are used to compare What is the accep-measured value with predictions?

tance criteria for this test and what procedures are followed if acceptance criteria is not met.

Response: The power coefficient measurement is done at a power level greater than 65% after the fuel preconditioning requirements have been satisfied. A power oscillation is created by ramping the turbine.-approximately"-+10%

and -10% rated power. The core T is then kept equal to T f by inserting and wi8h8rawing control rods. The reactivity computer is used to obtain the reactivity associated with each control rod move.

From these data the power coefficient can be cal-culated.

If the difference between within the measured and calculated 30%, the results of this power coefficient is test will be considered acceptable. If this cri-teria can not be met the test will be, repeated and if the average'easured value is within the envelope of power coefficients used in the accident analysis, there is no safety concern and the results of these tests will be considered acceptable.

If the average'alue of the tests is outside the envelope of power coefficients used in the accident analysis, operating restrictions will be imposed which will result in safe operation of the reactor until the accident analysis is re-evaluated using the measured data and safe operation of the cycle can be shown.

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