ML18142A706
| 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 NRC ORG:
WHITE L D ROCHESTER GAS 8( ELEC DOCDATE: 04/06/78 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 REVIE}PER INITIAL:
XJN DISTRIBUTOR INITIAL:~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOOl)
FOR ACTION:
INTERNAL:
BR
+4W/7 ENCL REG FILM4W/EN HANAUER+4FW/ENCL EISENHUT+4~W/ENCL BAER<4W/ENCL'RINES++W/ENCL J.
NCGOUGH44W/ENCL NRC PDR+~W/ENCL OELD>>LTR ONLY CHECK++W/ENCL SHAO++W/ENCL BUTLER4<W/ENCL J COLLINS++M/ENCL EXTERNAL:
I PDR~S ROCHESTER'Y++W/ENCL TIC++W/ENCL NSIC++W/ENCL ACRS CAT B~~W/i6 ENCL DISTRIBUTION:
LTR 40 ENCL 39 S IZE:
iP+2P END CONTROL NBR:
78i0i0022
PCI t
/i E!/1iiE/II/ lllllllliS' HO llIIIIII/IIIIIlIrlrd ROCHESTER GAS AND ELECTRIC CORPORATION o
S9 EAST AVENtIE, ROCHESTER, N.Y. 14649 LEON 0, WHITE, JR.
VICE PRESIDENT TELEPHONE AREA COOE 7ld 546-2700 P'pril 6,
1978 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:
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CPf ~I IVER'7@
+~<ri cn 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.
7Pgoi0022 o'
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 if the acceptance criteria is not met?
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.
If the criterion on individual bank worth is not 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
Response
Provide details of the power coefficient measurement near full power.
What methods are used to compare measured value with predictions?
What is the accep-tance criteria for this test and what procedures are followed if acceptance criteria is not met.
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 the measured and calculated power coefficient is within 30%, the results of this 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.
C 5)
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