ML20148N404
| ML20148N404 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/16/1978 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7811270091 | |
| Download: ML20148N404 (23) | |
Text
{{#Wiki_filter:- , 22 C:mm:nw=lth Edis:n One First National Plaza. Chicago, Illinois O Address Reply to: Post Office Box 767 Chicago, Illinois 60690 November 16, 1978 E THIS DQcyMENT CO Mr. Harold R. Denton, Director
~ POOR QUAUTY PAGE8j Office of Nuclear Reactor Regulation -
U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Zion Station Unit 1 Additional Information on Zion Unit 1 Startup Physics Testing Report NRC Docket No. 50-295 Reference (a): October 3, 1978 letter from A. Schwencer to Cordell Reed
Dear Mr. Denton:
l Per Reference (a), the NRC Staff requested Commonwealth Edison Company to submit a previously discussed supplement to the Zion Unit 1 Cycle 3 Startup Physics Testing Report dated March 15, 1978 and to provide the additional information requested in the enclosure to Reference (a). The requested information is provided as attachments to this letter. Attachment 1 contains the Supplemental Report and Attachment 2 contains responses to the Staff's questions on the Zion Unit 1 Cycle 3 Startup Test Report. For your information, Zion Unit 1 completed Cycle 3 < operation on September 14, 1978 and is currently in Cycle 4. Please address any additional questions that you j may have to this office. l One (1) signed original and thirty-nine (39) copies of this letter are provided for your use. Very truly yours, c Pd Cordell Reed Assistant Vice-President Q attachments 78112700$l
-T Commonwealth Edison NRC Docket No. 50-295 ATTACHMENT 1 SUPPLEMENTAL REPORT Supplemental Information to Reference A for Further Demonstration of Adequate Shutdown Margin for Unit 1 Cycle 3 References A. Letter to J. G. Keppler (NRC) from N. E. Wandke (CECO.) dated March 15,.
1978 containing Unit 1 Cycle 3 Startup Report B. Proposed " Branch Technical Position DOR-1 Guidance for Reloads Submittals" Purpose l The purpose is to satisfy concerns from the Imc in April 1978 for further justification of adequate shutdown margin for Unit 1 Cycle 3. It was specified that an uncertainty of 10% should be applied to evaluations invciving the use of reactivity computer data.
Background
Reference A demonstrated adequate shutdown margin using data from the conventional boration-dilution technique for measuring control rod bank worths with the reactivity computer and an uncertainty 4A Although rod swap data and boron endpoint data were discussed, they were not used to demonstrate adequate shutdown margin. Evaluation With the aid of several techniques, the rod swap data and boron' endpoint data was reevaluated in greater detail to demonstrate that adequate shutdown margin existed. 9 ., - . , . . . . , ,e---,w,v-w-,--e-,'w,,.-ww.3,,.-,c,.-.-.,..., , , , , . - . , , , - . .r . , - - , - ~ ,-,e ow..,, vw,,,n, - -,..v v-, . - , -,
Commonwealth Edison NRC Docket No. 50-295 ATTACHKENT 1 Page 2
- 1. Rod Swap Technique - The rod swap technique uses one of the eight banks of rods as a reference bank for which the worth is explicitly inferred from measurement. The worth of the other banks is individually inferred from the critical position of one bank relative to the reference bank. Control Bank c (CBC) was selected as the reference bank.
- a. Boron Endpoint Method - The worth of CBC was inferred from measured boron endpoints and design values of the boron worth. The results are shown in Table 1.
(1) Shutdown Margin Calculation (Reference A Method) (a) Beginning-of-Life (BOL): {(1 + .034)* (5370 pcm)] = 5552 pcm) 3270 pcm, where 1. The value of .034 represents the , difference from the predicted value as illustrated in Table 1;
- 2. The value of 5370 pcm is the predicted N-1 rod worth (Ref. A);
and 3 The value of 3270 pcm is the re-quired BOL shutdown margin (Ref. A) . (b) End-of-Life (EOL): {(1 + .034) . (5550 pcm)] = 5739 pcm) 4500 pcm, where 1. The value of 5550 pcm is the predicted N-1 rod worth (Ref. A) ; and
- 2. The value of 4500 pcm is the re-quired EOL shutdown margin (Ref. A) .
(2) Shutdown Margin Calculation (Reference B Method) From Reference B, the requirement dealing with rod worth and shutdown margin is as follows: , J
- . . _ = _ . _ . _._ _ _ . .
Commonw2Elth Edit:n NRC Docket No. 50-295 ATTACHMENT 1 Page 3
"... Control Rod Bank Worth (for all the regulating / control banks individually.
If any one bank worth differs from the predicted value by more than 15%, or the sum of the worths of the regulating banks differs from the predicted value by more than 10%, the first shutdown bank should be measured. If the sum of the worths of the regulating banks and the first shutdown bank differs from the predicted value by more than 10%, additional shutdown bank measurements should be performed to verify technical specification shutdown margin.)" From Table 1, the difference for all banks is
+3.4% which is within the.10% requirements of Reference B. Thus, adequate shutdown margin is demonstrated for all times in core life,
- b. ' Reactivity Computer Method - The worth of CBC was in-ferred from reactivity computer measurements. The results are shown in Table 1. !
(1) Shutdown Margin Calculation (Reference A Method) (BOL): (a) }Beginning-of-Life (.90) . (1.071). (5370 pcy4490 pcm) where 1. The value of 0.90 includes a f reactivity camputer uncertainty of 10%r and
- 2. The value of (-0.071) from Table 1 represents the difference from prediction.
(b) End-of-Life (EOL) :
~(.90), (1.071). (5500 pcm] = 4640 pcmf 4500 pcm l
Commonwealth Edison . NRC Docket No. 50-295
~
ATTACHMENT 1 Page 4 (2) Shutdown Margin Calculation (Reference B Method) From Table 1, the difference for all banks is -7.1% which is'within the 10% requirement of Reference B. Thus, adequate shutdown margin is demonstrated at all times in core life. It should be noted that Reference B does not require application of measurement uncertainty.
- 2. Boron Endpoint Technique - The measured incremental boron concentration from a group of rod banks, inserted to withdrawn, represents the worth of those rod banks. The boron endpoint technique for evaluating rod bank worth '
multiplies the measured incremental boron concentration times the applicable average design boron worth to obtain the rod bank worth. From Reference A (Table 4.5.1), the measured incremental boron concentration of 292 ppm represents the boron concentra-tion change from all rod banks withdrawn to all control banks inserted. Multiplying-292 ppm times the average design boron , worth yields a total control bank worth of 2927.3 pcm. This gives a difference as follows: Difference = 2927.3 pcm-3110 pcm =-5.9%, 3110 pcm where 3110 pcm is the predicted value from Table 4.4.1 of Reference A.
- a. Shutdown Margin Calculations (Reference A Method)
(1) BOL: {(1.059). (5370 pcm)] = 5053 pcm) 3270 pem (2) EOL . }1.059). (5550 pcm) = 5222 pcm) 4500 pem
- b. Shutdown Margin Calcualtion (Reference B Method)
Since'the difference of -5.9% is within the 10% ; requirement of Reference B,. adequate shutdown margin is demonstrated at all times in core life. l
'l l
Commonwealth Edison NRC Dockst No. 50-295 ATTACHMENT 1 Page 5 Conclusion Adequate shutdown margin has been demonstrated by several methods with the 10% reactivity computer uncertainty being applied where appropriate. In addition, the rod swap technique appears to be a sound technique and not responsible for the discrepancies between measured and predicted results. The Boron Endpoint Method and the Reactivity Computer Method show similar trends with the magnitude of their differences due most probably to the inherent characteristics of the methods themselves. I l l l I 1
ATTACHMENT 1 * * ! Pagn 6 Table 1 -
~
Unit 1 Cycle 3 Rod Swap Dank Worth Results l , I i Boron Endooint Method Reactivity Computer (Westinghouse Evaluation) Method (Ceco Evaluation) Rod Predicted Bank Dank Measured . Measured
- Worth Bank Worth Difference Bank Uorth Difference, (pen) (pen) (%) (ncm) (%)
i CBC 798.9 786.5 -1.6 682.0 -14.6 CBD 795.5 795.9 +0.1 693.0 -12.9 CBB 763.3 815.9 +6.9 732.9 -4.0 . CBA 234.0 193.0 -17.5 123.0 -47.4 SBD 466.0 506.4 +8.7 492.9 +5.8 - l SBC _4GG.0 502.4 +7.8 493.0 -F5. 8 l SBB 635.9 585.5 -7.9 542.7- -14.7 SBA 539.5 672.6 +24.7 604.2 +12.0 All Cn 2591.7 2591.3 0.0 2230.9 -13.9 . f- All SB 2107.4 226G.9 +7.6 2132.8 +1.2 ! All Banks 4699.1 4858.2 +3.4 43G3.7 -7.1
- Difference = Measured Dredicted Predicted-4
? 1 I l a
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l Commonwealth Edison NRC Docket No. 50-295 ATTACHMENT 2 RESPONSES TO NRC QUESTIONS ON THE EION 1 CYCLE 3 STARTUP TEST REPORT QUESTION 1 The measured rod worths (Table 4.4.1) were much lower (12%-40%) than predicted. Explain the differences and what has been done to resolve them. The boron worth predictions and measurements also differed substantially. Provide the basis for these differences and explain what has been done to prevent large differences from recurring in future cycles. RESPONSE 1 The reactivity computer measured rod worths (Table 4.4.1) were much lower (11%-36%) than predicted rod worths with a difference for total control banks of 13.9%. These differences resulted from prediction and measurement inaccuracies as dis-cussed in Responses 3 and 4 below. The boron worth differences are substantial due to the fact that measured boron worths are reactivity computer measured rod worths divided by measured boron concentration increments. Thus, differences in rod worths are also reflected in boron worths. The recurrence of large differences will be avoided in future measurements by implement-ing the Laprovements in the measurement technique and the > predictions as discussed in Responses 3 and 4 below. QUESTION 2 The physics test report demonstrated adequate shutdown margin using data from the conventional boron worths in con-junction with the reactivity computer and an assumed measurement uncertainty of 4%. Since these measurements have an uncertainty of at least 10%, adequate shutdown margin for EOC cannot be demonstrated when the 10% uncertainty is used. State how you have verified shutdown margin for EOC. It should be noted that the rod swap technique should not be used to demonstrate adequate
- shutdown margin as this technique has not received NRC approval.
RESPONSE 2 The physics test report demonstrated adequate shutdown margin'using data from the reactivity computer and the measurement uncertainty of 4% which was the approved uncertainty at the time t
. .- . . . - -=
1 1 Commonwealth Edison NRC Docket No. 50-295 ATTACHMENT 2 l Page 2 RESPONSE 2 (Cont'd) the testing was done. The physics test report also demonstrated the adequacy of the design rod worths from the incremental boron concentrations, and a boron endpoint technique was proposed for determining shutdown margin. After a 10% reactivity computer uncertainty was adopted, a Supplemental Report (Attachment 1) was written to further demonstrate shutdowm margin. .As discussed in the Supplemental Report, the boron endpoint measurement technique yielded control rod worths which were in good agreement with the predictions. End-of-Cyc',e shutdown margin was verified by two methods using these boion measurements. The results from the Rod Swap Test served to confirm the End-of-Cyc?# Shutdown Margin as verified by the boron endpoint technique. I QUESTION 3 On Page 19 you stated that "possible difficulties with the reactivity computer technique are being investigated. " Pro-vide the results of this investigation. RESPONSE 3 Proper setup of the reactivity computer was reverified. In addition, the adequacy of the selected testing range was investigated. Prior to this investigation, the acceptable testing range was to maintain the' flux level a decade or more i below nuclear heat. Currently, Westinghouse recommends a testing ! range that maintains the flux level a factor of three below the level for nuclear heat and a factor of one hundred above the level for detector noise and gamma background. A re-examination of the Unit 1 Cycle 3 testing conditions incorporating these Westinghouse recommendations indicated that for the measurement during dilution the total control bank ; worth measurements were low by about 3.0% due to detector noise and gamma background. Nuclear heating was not a problem since all Unit 1 Cycle 3 testing was performed within the criteria of the Westinghouse recommendations. l-
. _ . . - . , _ , . _ _ - . ~ . . . . . . . . - , _ . . , _ _ _ . _ _ - _ . . , _ _ _ . . , - . - . . _ _ . _ _ _ _ _ _ . _ _ . . _
Ccmm:nw2sith Edis::n NRC Dockat No. 50-295 ATTACHMENT 2 Page.3 RESPONSE 3 (Cont'd) Further investigations revealed that a reactivity bias existed in the reactivity computer output for low input signals. This reactivity bias results in somewhat lower measured rod worths. Additional reviews of the testing data revealed'that a more constant dilution /boration rate would be beneficial and that a longer wait period between rod movements would help identify spatial effects. All these observations will be considered in future e testing and should reduce discrepancies. QUESTION 4 , On Page 19 you state that "Possible errors in the predicted reactivity worths are being investigated." Report the results of these investigations. RESPONSE 4 Investigations into possible errors in the predicted control rod worths are presently being performed. The final results of these investigations, expected to be available'in 1979, will include prediction improvements as discussed in WCAP-9217 "Results of the Control Rod Worth Program," dated - October 1977 and core baffle cross section modifications a's discussed in Response 7 below. QUESTION 5 The boron endpoint data and the reactivity computer data come from the same test (Page 19). Explain the i discrepancy.between the inferred rod worths obtained using these two data manipulation techniques. RESPONSE 5 Boron endpoint data and reactivity computer data were collected during the same test, but the measurement techniques are quite different. WCAP-9217 (see Response 4) discusses most of the characteristics and uncertainty problems of these two
;n . S w-v , n, - - . , , - . , . , - . .- , , - - , n,x., . , ,,- - . ~ - - , + - . . , , . -
Commonw=lth Edison NRC Dock 2t No. 50-295 ATTACHMENT 2 Page-4 RESPONSE 5 (Cont'd) I distinctly different methods and identifies that differences f as large as 8% have been observed between reactivity computer and boron endpoint rod worth results. Thus, the Unit 1 Cycle 3 physics test report differences (Pages 18 and 25) are not unprecedented. QUESTION 6 l Provide the assembly-by-assembly flux maps that were j taken during startup which were summarized in Table 5.1.2. A. RESPONSE 6 The measurad FA H and percent difference between measured and predicted FN H for each assembly are provided for Flux Maps 1-3-01 through 1-3-09 in Attachment A. QUESTION 7 On Page 29 you state "The code generally overpredicted , power near the center of the core, and power was mostly under-predicted near the periphery of the core...The core designers are presently working on calculational improvements to achieve ' a better agreement." Explain the observed / predicted "in-out" power tilts and the results of investigations on this subject. l l RESPONSE 7 l The measured to predicted "in-out" power mismatch discussed on Page 29 of the report resulted from under-prediction of the normalized assembly power near the periphery of the core. This under-prediction, which caused the power in the central region assemblies to be over-predicted, is shown in the power distribution figures provided in Response 6 It was determined that this power mismatch was caused, at least in part, by the breakdotin of diffusion theory in the core baffle. A diffusion theory equivalent baffle cross section was obtained from one-dimensional transport calculations through I the baffle region.
-- . . _ . . . . ~ _ - .. _. -.
. . 1 Commonwealth Edison NRC Docket No. 50-295 ATTACHMENT 2 Page 5 RESPONSE 7 (Cont ' d).
A detailed study was performed on seventeen Zion 1, Cycle 3 Flux Maps analyzed with both the " standard" and " baffle corrected" predictions. The results, summarized in Table 1, show significantly better agreement with measurement for the corrected baffle cross section power predictions than for the standard predictions employed in the Startup Test Report. The baffle corrected predictions substantially reduced the previously observed "in-out" power mismatch as illustrated in I Figure 1. e -,---m-- -- w-, , _, , , , , , . . - . . .w.. . ., , , ,__--9.,. arm _.., . , _ , , y - ., ,, y._,,_ , ~ , , _, , e ,,,....r.-.v- , r-- . - -
.J' Table 1. . .-
Comparis'.a of Baffle Corrected Predictions with Standard Predications for Zion Unit 1, Cycle 3 Flux Maps. . Map Power Burn up) AverarelTIDiff.(1) Maximum T Diff. (2) Radial Zone T Diff-(3) Number (%) _( M'a'D/MT Standard Baffle Standard Baffle Standard Baffle 1-3-01 5 0 11.4 6.3 23.0 13.4 90 3.7 1-3-02 75 70 5.8 2.8 17.5 9.7 4.2 1.6 1-3-03 88.1 163 57 2.7 15.5 9.0 5.0 2.0 1-3-04 90.0 168 6.7 3.6 16.9 10.1 5.0 2.3 1-3-05 90. 188 5.5 25. 14.2 7.7 4.7 1.8 1-3-06 100 420 6.5 35 15.4 90 4.8 2.0 l 1-3-07 99 444 5.1 2.2 14.1 7.8 4.2 1.5 1-3-08 97 732 55 . 2.7 13.8 79 4.5 1.9 1-3-09 99 9 1785 52 27 13.4 7.8 4.2 19 ! 1-3-10 99 5 2555 50 2.7 15.7 10.2 - - 1-3-11 97.8- 3773 2.2 1.2 8.5 3.8 1.4 5 1-3-12 89 5 4179 19 1.2 7.1 4.3 - - 1-3-13 98.4 4630 19 1.2 7.1 3.1 1.1 7 1-3-14 98.4 5213 1.5 1.3 6.4 -4.3 - - 1-3-15 89.7 5302 1.6 1.1 6.5 -3.7 9 .7 1-3-16 89.4 5310 1.6 1.2 6.3 -4.1 - - 1-3-17 90.2 5333 1.9 1.0 7.1 3.2 .8 .8 (1) Average of absolute value of % difference between measured and predicted reaction raIt integral (RRI) for all flux thimbles. (2) The maximum percent difference between measured and predicted RRI, (M-P)/P. l (3) The overall average of the absolute value of % difference between measured and predicted ! RRI for 5 radial core zones.
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. 8.702. t . t86. I 9.8. .867. t4.7. .253.4.7. 0.963.l .5. 0.867. 0.797.
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. -2.t. .856. 15.2.
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