ML042310440

Reply to Request for Additional Information on Proposed Technical Specifications (TS) Amendments to Sections 3.8.4, DC Sources - Operating; 3.8.5 - DC Sources - Shutdown & 3.8.6, Battery Cell Parameters & Associated TS Bases

ML042310440
Person / Time
Site:	Catawba
Issue date:	08/05/2004
From:	Jamil D Duke Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC2618, TAC MC2619
Download: ML042310440 (19)

Text

- PbDuke D.M. JAMIL IVPowers Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. I CNOI VP York, SC 29745-9635 803 831 4251 803 831 3221 fax August 5, 2004 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station, Units I and 2 Docket Numbers 50-413 and 50-414 Reply to Request for Addition Information on Proposed Technical Specifications (TS)

Amendments to Sections 3.8.4, "DC Sources

- Operating"; 3.8.5 - "DC Sources -

-Shutdown"; and 3.8.6, "Battery Cell Parameters' and Associated TS Bases (TAC Numbers MC2618 and MC2619)

Please find Catawba's reply to a Request for Additional Information discussed via a teleconference with the NRC on June 22, 2004. The format of the reply is to restate the NRC question followed by Catawba's response.

There are no regulatory commitments contained in this letter or its attachment.

If you have any questions concerning this material, please call A.P. Jackson at (803) 831-3084.

Very truly yours, Dhiaa M. Jami APJ/apj A oi www. dukepower. corn

4 U.S. Nuclear Regulatory Commission Page 2 August 5, 2004 Dhiaa M. Jamil affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.

Dhiaa M. Jamil, Vice President, Catawba Nuclear Station Subscribed and sworn to me:

Date Notary ublic J My commission expires: 7-lo- a-o01?

Date N

_N SEAL

. 0 Attachments U.S. Nuclear Regulatory Commission Page 3 August 5, 2004 xc (with attachments):

W.D. Travers U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie Senior Resident Inspector (CNS)

U.S. Nuclear Regulatory Commission Catawba Nuclear Station S. E. Peters NRC Project Manager (CNS)

U. S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, DC 20555-0001 H. J. Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201

Attachment A REQUEST FOR ADDITIONAL INFORMATION DUKE ENERGY CORPORATION CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NUMBERS 50-413 AND 50-414 The Nuclear Regulatory Commibbi- A(RC) staff reviewed the licensee's license amendment submittal dated April 6, 2004 regarding diesel generator battery cell parameters and identified that additional information was required to enable the continuation of the review. The questions and licensee responses are listed below:

1. Attachment 5 to the "Technical Specifications (TS)

Amendment Request" provides Diesel Generator (DG) battery sizing calculations for various load profiles. The worst case is observed to be lDGBA LOCA-BO with first minute loading as 178.61A. However, per section SR 3.8.4 (marked as SR 3.8.4.7) of TS bases B3.8.4, the DG batteries are tested for 218.5A for the first minute. Also, according to Figure 8-27 of UFSAR, the load for DG batteries is 214.6A for the first minute. Similar differences are observed for the remainder of the load profile between the DG batteries sizing calculation, TS bases, and UFSAR. Please explain why there are differences between the load profiles considered in the calculations for sizing the batteries, TS bases, and the load profile considered for testing of the batteries.

Duke Energy Corporation Responses The UFSAR Figure 8-27 load value of 214.6A is from the October 1993 revision of the UFSAR. Figure 8-27 has since been revised, and the current October 2001 revision shows a value of 273.1A for the first minute.

The load profile (duty cycle) described in TS bases B3.8.4.8 conservatively envelopes the load profile shown for all four DG batteries, 1DGBA, 1DGBB, 2DGBA and 2DGBB, in the battery sizing calculation. The design basis load profile for each battery is slightly different due to minor load differences between trains A and B and units 1 and 2.

For this reason, the battery sizing calculation determines the required capacity for each battery on an individual basis. From an overall size requirement standpoint, DG battery IDGBA is the worst-case battery. To avoid becoming overly complex, one load profile, which envelopes the load Page 1 of 4

Attachment A profile for ali four DG batteries, was developed and incorporated into the TS bases. The load profile represents the total design basis load adjusted for a design basis minimum cell temperature of 60 OF and a 15%

Design Margin. The load profile in the TS bases is the profile used to perform the battery service test; therefore, the load profile does not include correction for battery aging. The load profile shown in the October 2001 revision of UFSAR Figure 8-27 is consistent with the load profile in the TS basis except that the load profile in Figure 8-27 includes an Aging Factor adjustment of 1.25 to account for normal age-related battery capacity degradation (to a minimum of 80% of the rated capacity).

2. Please provide the following calculations for staff review:

• Worst case DG battery load profile calculation (load profile should agree with load profiles considered in other documents)

• DG battery sizing calculation for the worst case load profile with no cell reversal Duke Energy Corporation Responses Please refer to Attachment B for a preliminary copy of the battery load profile and sizing calculations for 1DGBA, assuming no cell reversal. The copy is preliminary due to periodic revisions unrelated to the question above. The portions included in the attachment deal with the worst-case DG battery, which is 1DGBA. These portions of the calculation have been checked and are included on Attachment B. The revision did not change the battery load profile. No significant changes are expected to be made to this portion of the calculation. The calculation revision is expected to be fully checked and approved by the September 9, 2004. A final copy of the calculation for DG Battery IDGBA can be provided at that time, if desired.

The battery sizing calculation previously provided for the cell-reversal scenario did not change as a result of the revision described above.

Page 2 of 4

Attachment A

3. It is stated on Page 1 of Attachment 3, that the proposed TS amendment does not involve a significant reduction in margin of safety. The staff believes that the proposed change would reduce the margin of safety by allowing one cell to be in a condition where cell reversal is likely.

This condition would not occur with the current TS. Please clarify.

Duke Energy Corporation Responses Catawba's batteries are sized in accordance with IEEE Std. 485-1983 where the batteries are sized based on a design minimum temperature of 60 'F and a 1.25 aging factor in addition to design margin. The design margin is over and above the design basis requirements. Catawba's DG batteries (94 cells, 277 Ah) are sized with a significant design margin. Assuming the battery is at an end-of-life capacity of 80%, the electrolyte temperature is at the design minimum of 60F, and that no cells are jumpered out, the design margin is 37%. With the worst-case assumption that one cell is in full reversal (-1.8 volts), the design margin is still 34%.

4.. It is not clear to the staff how long the plant will he operated with the battery in the degraded condition with one cell in reverse polarity. Please clarify.

Duke Energy Corporation Response:

Based on the discussions in Attachment 2 of the April 6, 2004 submittal, pages 7 and 8 and the results of the battery sizing calculations in Attachment 5 of the same submittal, a DG battery can remain operable and fully capable of satisfying its design requirements indefinitely with one cell <1.36 V. Catawba will increase awareness when the cell is <1.36V and administratively plan replacement of the cell during the next respective DG Work Day. On-line work is scheduled by trains to minimize equipment unavailability time and thus the replacement of the cell would be scheduled accordingly.

Page 3 of 4

Attachment A

5. Provide justification for moving SR 3.8.4.2 to new SR 3.8.6.5 location.

Duke Energy Corporation Response:

This change was simply relocating this surveillance from TS 3.8.4, "DC Sources-Operating" to a more appropriate Technical Specification. TS 3.8.6, "Battery Cell Parametersf. Upon further review, this change may cause more confusion since it will vary from the standard TS and we currently have another TS amendment which affects these same Technical Specifications in progress. Thus, Duke is agreeable with not moving the SR 3.8.4.2 to SR 3.8.6.5.

Page 4 of 4

Attachment B Figure 1: 125VDC Diesel Auxiliary Power Battery IDGBA Load Profile During a LOCA/ Blackout Pae1 f1

- - - - - - LOCA/Blaek' Duty Csd Time Period - - - - - -

0. 1 - 3.. 5 10. I11. 12W4 5 6 17- 20- 21- 22. 25-Bs/ConspL Load Mile IO lsee. 2 see. 3 sec. 8.Se. lsee. sec.Il lme 2 see. l3see. 1Sse. 16 see. 17 see. 20 sec 21 see. 22sc 2 see. 26 sec.

IEDEAF)I C IETA Switchgear Control Power 6.00 21.00 6.00 6.00 6.00 56.00 6.00 76.00 86.00 16.00 76.00 16.00 6.00 76.00 16.00 6.00 76.00 1EDE/Rem. lBalance of I EDE Loads 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.621 26.62 1VADA Low Voltage Detection Isol. on I VADA 0.02 0.02 0.02 0.02 0.021 0.02 0,02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.-02 Direct Feed Diesel Engine Control Panel I DECPA and 0.71 17.61 17.611 17.61 20.69 5.53 5,53 6.98 5.97 5,97 5.97 5.97 5.97 5.97 5.97 5.97 5.97

_____Diesel Generator Control Panel I DGCPA- -----

Direct Feed Diesel Generator 2A Field Flash 0.00 0.00 0.00 0.00 45.00 45.00 45.00 0.00 0.00 0.00 0.00 0.00 0.00 0.001 0.00 0.00 0.0 IDGDA Various loads on P01B, P0IC, POIDFOIE I 0.00, 0.00 0.00 0.001 0.001 0.00 0.00 0.00 0.00 0.001 0.001 0.00 0.001 0.0 0.00 0.00 0.00 Total 33.35I 65.25 50.25 50.25] 98.331 133.161 8.161 109.621 118.611 48.611 108.61 48.61 38.611 108.61 48.61 38.61 108.61

__ _ __ __ _ __ __ _LOCA/Blaeot

__ Duty Cycle Time Period 26- 27- 30. 31- 32- 35. 36- 37- 40- 41- 42- 1- linslal 2- 10- 11- limln~nls Hus,/CoinLt Load T1tle 27 see. 30 sec. 31lsee. 32 sec. 35 sec. 36 see. 37 sec. 40 sec. 41 sec. 42 sec. l min. lmnln.+ls 2 inn. 10 mlin. 11 mmn. llmin+lo 11mln+2s IEDE/POIC I ETA Switchgear Control Power 16.00 6.00 146.00 26.00 6.00 76.00 16.00 6.00 76.00 16.00 6.00 6.00 6.00 6.00 6.00 76.00 16.00 IEDEIRem. Balance of I EDE Loads 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 26.62 15.11 15.11 15.1 1 15.54 15.54 15.54 I VADA Low Voltagte Detection Isol. on I VADA 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 Direct Feed Diesel Engtine Control Panel I DECPA and 5.97 5.97 5.97 5.97 5.9'7 5.97 5.97 5.97 5.97 5.97 5.97 7.31 6.09 6.09 6.00 6.09 6.09

____Diesel Generator Control Panel I DGCPA IDirect Peed Diesel Generator IA Field Flash 0.00 0.0 0.00 0.001 0.001 0.00 0.00 0.001 0.00 0.001 0.00 0.00 0.001 0.001 0.00 0.0 0.00 JIDGDA lVatious loads on FlB, FDIC,PO D, OIEI 0.001 0.001 0.001 0.001- 0.001 0.00i 0.00 0.(00 0.001 0.001 0.00 02 0.23 0.231 0.231 0.231 0.23 TOWa 48.61 38.611 178.611 58.611 38.611 108.611 48.611 38.611 108.61 48.611 38.61 28.67 27A41 27A41 27.871 97.871 37.87 Catawba Nuclear Station Units I and 2 CNC-1381.05410-0050

Attachment B Figure 1: 125VDC Diesel Auxiliary Power Battery 1DGBA Load Profile During a LOCA/ Blackout Page 2 of 12

_ l_LOCA/Blackout Du Cycle Time Period llmnr+2412 1min, 2d+1s 12ndn+2b 13 20- 60. 61 adn.r Bus/Comip. Load Title 12 rntn. 112nin+l 12mhn+2l 13 mrin 20 mlni. 60 min. 61 imin. 120 min.

IEDE/FOIC IETA Switchgear Control Power 6.00 6.00 6.00 6.00 6.00 6.00 6.00 6.00 IEDE/Rem. Balance of IEDE Loads 15.54 15.54 15.54 15.54 15.54 13.98 13.98 13.98 I VADA Low Voltage Detection Isol. on I VADA 0.02 0.02 0.02 0.02 0.02 0.02 0.02 0.02 Direct Feed Diesel Engine Control Panel I DECPA and 6.09 6.09 6.09 6.09 6.09 6.09 5.69 5.53 Diesel Generator Control Panel I DGCPA Direct Feed Diesel Generator IA Field Flash 0.00 0.00 0.00 000 0.00( 0.00 0.00 0.00 IDWDA Various loads on FOIB, FOIC, FOID. FOIE 0.231 O.2 0.23 0.23 0.23 0.23 0.23 0.23 Toial 27.87 27. 27.87 27.87 27.87 26.31 25.91 25.75 200.00 -

180.00 -

160.00 -

140.00 -

120.00 -

l100.00 -

80.00 -

60.00 -

40.00-20.00 0.00 0 Im 2m lOmn lrn 12m 13m 20m 60m 61m 120m Time Catawba Nuclear Station Units l and 2 CNC-1381.05-00-0050

Attachment B Page 3 of 12 Figure 5: 125VDC Diesel Auxiliary Power Battery 1DGBA Load Profile Adjustments for Aging LOCA/Blackout Dut Cycle Time Period -

0- 1- 2- 3- 8.5- 10- 11- 12- 14- 15- 16- 17- 20. 21- 22- 25-Description sec. 2 sec. 3sec. 8.5ssec. l0sec. 11 sec. 12 sec. 13 sec. 15 sec. 16 sec. 17 sec. 20 sec. 21 sec. 22 sec. 25 sec. 26 sec.

Unadj. Load 65.25 50.25 50.25 98.33 133.16 83.16 109.62 118.61 48.61 108.61 48.61 38.61 108.61 48.61 38.61 108.61 Current (ADC) I - -

80% Aging 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.2S 1.25 Factor Adj. Load 81.56 62.81 62.81 122.91 16645 103.95 137.02 148.26 60.76 135.76 60.76 4826 135.76 60.76 48.26 135.76 Current (ADC)

- LOCA/Blackout Duty Cycle Time Period 26- 27- 30- 31- 32- 35- 36- 37- 40- 41- 42,- 1- lmun+1s 2- 10- 11-Description 27 sec. 30 sec. 31 sec. 32 sec. 35 sec. 36 sec. 37 sec. 40 sec. 41 sec. 42 sec. 1 min. lmin.+ls 2 min. 10 min. l11 min. llmin+ls Unadj. Load 48.61 38.61 178.61 58.61 38.61 108.61 48.61 38.61 108.61 48.61 38.61 28.67 27.4 27.44 27.87 97.87 Current (ADC) - - a - -

80% Aging 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25i 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 I_______

Factor Adj. Load 60.76 48.26 223.26 73.26 48.26 135.76 60.76 48.261 135.76 60.76 48.26 35.83 34301 34.30 34.84 122.34 Current (ADC) l__ _

_LOCA/Blackout Duty Cycle Time Period llmin+ls llmin+2s 12miL- 1n2mln+Is 12m1n+2s 13- 20- 60- 61-lDescriplion llln+2s 12 min. 12min+ls 12min+2s 13 min 20 min. 60 min. 61 min. 120 min.

Unadj. Load 37.87 27.87 27.87 27.87 27.87 27.87 26.31 25.91 25.75 Current (ADC) 1 80% Aging 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 1.25 Factor Adj. Load 47.34 34.84 34.841 34.841 34.841 34.84 32.89 32.39 32.19 Current (ADC)

Catawba Nuclear Station Units I and 2 CNC- 1381.05-00-0050

Attachment B Page 4 of 12 Figure 5: 125VDC Diesel Auxiliary Power Battery 1DGBA Load Profile Adjustments for Aging 250.00 -

200.00 -_

150.00 -

0 Im 2m tOin tIm 12m 13m 20in 60m 61m 120in Time Catawba Nuclear Station Units I and 2 CNC- 1381.05-00-0050 1.

Affachment B Table I Page 5 of 12 SAFI Nife, Inc. SBM277-2 Capacity Factors Tine to End Uncorrected Disch. Capacity Factor 5-hour of Section Current Kt Rt Capacity (Min.) (ADC) (Ah/A) (A/mp) (Ah)

I sec. 505.00 0.55 42.08 277 5 sec. 490.00 0.57 40.83 277 30 sec. 425.00 0.65 35.42 277 1.00 382.00 0.73 31.83 277 1.50 273.00 1.01 22.75 277 2.00 273.00 1.01 22.75 277 3.00 273.00 1.01 22.75 277 4.00 273.00 1.01 22.75 277 5.00 273.00 1.01 22.75 277 6.00 228.00 1.21 19.00 277 7.00 228.00 1.21 19.00 277 8.00 228.00 1.21 19.00 277 9.00 228.00 1.21 19.00 277 10.00 228.00 1.21 19.00 277 11.00 200.00 1.39 16.67 277 12.00 200.00 1.39 16.67 277 13.00 200.00 1.39 16.67 277 14.00 200.00 1.39 16.67 277 15.00 200.00 1.39 16.67 277 16.00 185.00 1.50 15.42 277 17.00 185.00 1.50 15.42 277 18.00 185.00 1.50 15.42 277 19.00 185.00 1.50 15.42 277 20.00 185.00 1.50 15.42 277 21.00 161.00 1.72 13.42 277 22.00 161.00 1.72 13.42 277 23.00 161.00 1.72 13.42 277 24.00 161.00 1.72 13.42 277 25.00 161.00 1.72 13.42 277 27.00 161.00 1.72 13.42 277 29.00 161.00 1.72 13.42 277 30.00 161.00 1.72 13.42 277 31.00 126.00 2.20 10.50 277 35.00 126.00 2.20 10.50 277 36.00 126.00 2.20 10.50 277 37.00 126.00 2.20 10.50 277 38.00 126.00 2.20 10.50 277 39.00 126.00 2.20 10.50 277 40.00 126.00 2.20 10.50 277 41.00 126.00 2.20 10.50 277 45.00 126.00 2.20 10.50 277 47.00 126.00 2.20 10.50 277 48.00 126.00 2.20 10.50 277 49.00 126.00 2.20 10.50 277 50.00 126.00 2.20 10.50 277 51.00 126.00 2.20 10.50 277 54.00 126.00 2.20 10.50 277 Catawba Nuclear Station Units 1 and 2 CNC-1381.05-00-0050 By: A. Benge

Attachment B Table 1 Page 6 of 12 SAFT Nife, Inc. SBM277-2 Capacity Factors 55.00 126.00 2.20 10.50 277 56.00 126.00 2.20 10.50 277 57.00 126.00 2.20 10.50 277 58.00 126.00 2.20 10.50 277 59.00 126.00 2.20 10.50 277 60.00 126.00 2.20 10.50 277 61.00 115.33 2.40 9.61 277 90.00 107.00 2.59 8.92 277 100.00 89.60 3.09 7.47 277 107.00 89.60 3.09 7.47 277 108.00 89.60 3.09 7.47 277 109.00 89.60 3.09 7.47 277 110.00 89.60 3.09 7.47 277 117.00 89.60 3.09 7.47 277 118.00 89.60 3.09 7.47 277 119.00 89.60 3.09 7.47 277 120.00 89.60 3.09 7.47 277 Catawba Nuclear Station Units I and 2 CNC-1381.05-00-0050 By: A.Benge

Attachment B Page 7 of 12 Table 1 SAFI Nife, Inc. SBM 277-2 Capacity Factors The uncorrected discharge current values for time periods which were not explicitly listed in Attachment 2 (page 13) were conservatively assumed to be the next largest time interval listed. For example, the time period of 6 minutes is not listed in Attachment 2 and would fall between the value for 5 minutes and 10 minutes. Since the discharge current value for 10 minutes represents a lower battery capacity than the 5 minutes discharge value, it is assumed that this value also holds for the 6 minute discharge current. In this manner, the discharge currents used in the table are assured of enveloping the actual discharge curve, provided the curve always has a downward slope (obviously a valid assumption).

The one exception to the above philosophy is the 61 minute discharge value. Here, linear regression was used to determine a curve fit for the discharge current function. In particular, the discharge current was assumed to be a function of the log of time period. A linear curve fit was performed using the discharge currents corresponding to 20, 30, 60, 90, and 120 minutes, with log(time) used as the independent variable. The LINEST function in Microsoft Excel was used to perform the regression. The results are as follows:

y=m*log(x)+b wherem=-120.13 b = 340.09 The regression statistics are as follows:

R-sqr = 0.9987 Standard Error = 1.6014 F-statistic = 2373.39 Degrees of Freedom = 3 Regression SS = 6086.3 Residual SS = 7.693 p-value = 0.0000109 This can be interpreted as follows:

1) The R-sqr statistic indicates that 99.87% of the variation between the predicted value and actual value is captured by the regression equation.

2) The p-value statistic indicates the there is a 0.00147% chance the regression analysis results are due to the random variation of the actual values instead of representing a true relationship to the actual values. Or, put another way, there is a 99.9987% probability the regression equation represents the true behavior of the dicharge current values.

Time to End Log of Time to Actual Predicted Residual of Section End of Section Disc. Curr. Disc. Curr. (Actual minus (Min.) (Mi.) (ADC) (ADC) Predicted) 20.00 1.30 185.00 183.80 1.20 30.00 IA8 161.00 162.65 -1.65 60.00 1.78 126.00 126.49 -0.49 90.00 1.95 107.00 105.33 1.67 120.00 2.08 89.60 90.33 -0.73 N.

Catawba Nuclear Station Units I and 2 CNC-1381.05-00-0050 Rev. V9 By: A. Benge

Attachment B Page 8 of 12 Table 1 SAFI Nife, Inc. SBM 277-2 Capacity Factors Since this is obviously an excellent fit, the next step is to construct a prediction interval for the 61 minute value which the equation will be used to predict. This is done using the following equation from Attachment 7, page 1:

confidence interval = predicted value +/- t*(predse) where t = t-distribution value corresponding to n degrees of freedom and x desired percentile predse = prediction standard error (see Attachment 7. page 1)

From the regression statistics above, there are three degrees of freedom associated with the data set used in the analysis. If a prediction interval of 99.5% is desired, then from Attachment 7, page 2, the corresponding t-value is 5.841. Using this value of t, and an s value of 1.6104 (the standard error of estimate from the regression statistics above), the following prediction interval upper and lower bounds are computed for each predicted value of discharge

,rrment 99.5% 99.5%

Time to End Actual Predicted Prediction Interval Prediction Interval of Section Disc. Curr. Disc. Curr. Lower Bound Upper Bound (Min.) (ADC) (ADC) (ADC (ADC) 20.00 185.00 183.80 171.93 195.68 30.00 161.00 162.65 151.83 173.47 60.00 126.00 126.49 116.20 136.77

____ 6X4 7 ~.;.1-"'XX25 av 4 >;

-. 115.33 .: A  ;

90.00 107.00 105.33 94.54 116.13 120.00 89.60 90.33 78.83 101.82 From the above table, the lower bound for the 61 minute discharge current is 115.33 ADC. This means there is a 99.5% probability the actual discharge current will be higher than this value. It should be noted that the confidence intervals used in loop accuracy calculations is typically 95%. Additionally, the resolution of the discharge current values used in the regression is a maximum of 1/1 85, or 99.5%. Based on these two observations, a 99.5% prediction interval is considered conservative. Consequently, the lower bound of 115.33 ADC for the uncorrected discharge current for 61 minutes will be used in the appropriate entry in the Table.

Catawba Nuclear Station Units I and 2 CNC-1381.05400-0050 Rev. V9 By: A. Benge

Attachment B Page 9 of 12 Table 2 SAFT Nife, Inc. SBM277-2 Temperature Correction Factors Time to End of Section Temp (Min.) Correction*

1 1.07 2 1.07 3 1.06 4 1.06 6 1.06 7 1.06 8 1.06 9 1.06 10 1.06 1 1.06 12 1.06 13 1.06 14 1.06 17 1.06 18 1.06 19 1.06 20 1.06 21 1.06 22 1.06 23 1.06 24 1.06 27 1.06 29 1.06 30 1.06 31 1.06 36 1.06 37 1.06 38 1.06 39 1.06 40 1.06 41 1.06 47 1.06 48 1.06 49 1.06 50 1.06 51 1.05 57 1.05 58 1.05 59 1.05 60 1.05 61 1.05 100 1.04 107 1.04 108 1.04 Catawba Nuclear Station Units I and 2 CNC-1381.05-00-0050 By: A. Benge

Attachment B Table 2 Page 10 of 12 SAFT Nife, Inc. SBM277-2 Temperature Correction Factors 109 1.04 110 1.04 118 1.04 119 1.04 120 1.04 169 1.04 170 1.04 178 1.04 179 1.04 180 1.04 200 1.04 206 1.04 208 1.04 209 _2 1.04 210 __ _ _ _ _ _1.04 215 1.04 216 1.04 217 1.04 218 1.04 219 1.04 220 1.04 227 1.03 229 1.03 230 1.03 236 1.03 237 1.03 238 1.03 239 1.03 240 1.03

• Data from SAFr Calc (Attachment 9) & Jim McDowall (Attachment 10)

Catawba Nuclear Station Units 1 and 2 CNC-1381.05-00-0050 By. A. Benge

Attachment B PageII of12 Figure 9 125VDC Diesel Auxiliary Power Battery IDGBA Cell Sizing Work Sheet Using Kt Capacity Factor

= CHANGE DURATION TIME TO CAPACITY AT TEMPERATURE REQUIRED IN LOAD OF PERIOD END OF T MIN RATE DERATING SECTION PERIOD LOAD (AMPS) (AMPS) (MIN) SECT (MIN) K Factor (Kt) FACTOR (MIN) SIZE Section 1- First Period Only - If A2 is greater than Al, go to Section 2.

-1 223.26 ) 223.26 1 0.73 1.070 j 173.23 SECT I TOTAL L 173.

Section 2 - First Two Periods Only - If A3 is greater than A2, go to section 3.

I 223.26 223.26 I1 I 2 1.01 1.070 242.39 2 35.83 -187.43 1 1 0.73 1.070 -145.42 SECT SUB TOT SECT 2 TOTAL 96.97 Section 3- First Three Periods - If A4isreater than A3,oto Secon 4. _

1 223.26 223.26 1 10 1.21 1.060 287.52 2 35.83 -187.43 1 1 9 1.21 1.060 -241.37 3 34.30 -1.53 j 8 8 1.21 1.060 -1.97 SECT SUB TOT SECT 3 TOTAL 44.17 Section 4-F irst Four Periods nly -If aterthan A4, go to section 5.

2 I 223.26 35.83 Ais 223.26

-187.43 1

1 j 11 10 1.39 1.060 327.77 1.21 1.060 -241.37 3 34.30 -1.53 8 9 1.21 1.060 -1.97 4 34.84 0.54 1 1 0.73 1.070 0.42 SECT SUB TOT SECT 4 TOTAL 84.84 Section 5 - First Five Periods Only - If A6 is gter than A5, Roto Section 6.

2 3

1 1

1 223.26 35.83 34.30

[j 223.26

-187.43

-1.53 j 11 1

8 12 11 10 1

1.39 1.39 1.21 1

1 1.060 1.060 1.060 327.77

-275.16

-1.97 4 j 34.84 j 0.54 j 1 2 _ _ 1.01 1.070 0.58

_____ 1 122.34 1 87.50 j 1 1 0____73__ 1 1.070 67.89 SECT SUB TOT _ _ _

SECT5TOTAL 119.11 Section 6- First Six Periods Only - If A7 is greater than A6, go to section 7.

1 223.26 223.26 ~ 1 13 ~ 1.39 1.060 327.77 2 35.83 -18743 l 1 12 1.39 1.060 -275.16 4 34.84 0.54 1 3 1.01 1.060 0.58 5 122.34 87.50 1 2 1.01 1.070 95.00 6 34.84 r -87.50 1 0.73 1.070 -67.89 SECT SUB TOT l l SECT 6 TOTAL l 78.04 Section 7-First Seven Periods Only - If A8 is ster than A7, go to Section 8.

1 223.26 223.26 1 20 1.50 1.060 354.35 2 35.83 -187.43 1 19 1.50 1.060 -297.47 3 34.30 -1.53 8 18 1.50 1.060 -2.43 4 34.84 0.54 1 10 1.21 1.060 0.69 5 122.34 87.50 1 9 1.21 1.060 112.68 6 34.84 -87.50 1 8 1.21 1.060 -112.68 7 34.84 0.00 7 7 1.21 1.060 0.00 Catawba Nuclear Station Units I and 2 CNC-1381.05-O0-0050 By: A. Benge

Attachment B

- Page 12 of 12 Figure 9 125VDC Diesel Auxiliary Power Battery 1DGBA Cell Sizing Work Sheet Using Kt Capacity Factor SECT SUB TOT I I SECT 7 TOTAL 1 55.13 I Section 8 - First Eight Periods Only - If A9 is gter than A8, to Section 9._

1 223.26 223.26 1 60 2.20 1.050 515.36 2 35.83 -187.43 1 59 2.20 1.050 -432.65 3 34.30 -1.53 8 58 2.20 1.050 -3.54 4 34.84 0.54 1 50 2.20 1.060 1.25 5 122.34 87.50 1 49 2.20 1.060 203.90 6 34.84 -87.50 1 48 2.20 1.060 -203.90 7 34.84 0.00 7 47 2.20 1.060 0.00 8 32.89 -1.95 40 40 2.20 1.060 -4.54 SECT SUB TOT SECT 8 TOTAL 75.88 Section 9 - First Nine Periods Oly - If AIO is gater than A9, go to Section 10.

1 223.26 223.26 1 61 2.40 1.050 563.03 2 35.83 -187.43 1 60 2.20 1.050 -432.65 3 34.30 -1.53 8 59 2.20 1.050 -3.54 4 34.84 0.54 1 51 2.20 1.050 1.24 5 12234 87.50 1 50 2.20 1.060 203.90 6 34.84 -87.50 1 49 2.20 1.060 -203.90 7 34.84 0.00 7 48 2.20 1.060 0.00 8 32.89 -1.95 40 41 2.20 1.060 -4.54 9 32.39 -0.50 1 1 0.73 1.070 -0.39 SECT SUB TOT SECT 9 TOTAL 123.15 Section 10 - Final Section 1 223.26 223.26 1 120 3.09 1.040 717.82 2 35.83 -187.43 1 119 3.09 1.040 -602.62 3 34.30 -1.53 8 118 3.09 1.040 -4.93 4 34.84 0.54 1 110 3.09 1.040 1.73 5 122.34 87.50 1 109 3.09 1.040 281.33 6 34.84 -87.50 1 108 3.09 1.040 -281.33 7 34.84 0.00 7 107 3.09 1.040 0.00 8 32.89 -1.95 40 100 3.09 1.040 -6.27 9 32.39 -0.50 1 60 2.20 1.050 -1.15 10 32.19 -0.20 59 59 2.20 1.050 -0.46 SECT SUB TOT SECT 9 TOTAL 104.12 Catawba Nuclear Station Units I and 2 CNC-1381.05-00-0050 By: A. Benge