ML20216H402

Rev 5 to 98-106, Evaluation for LOCA Aging at 1880 Mwt

ML20216H402
Person / Time
Site:	Monticello
Issue date:	04/07/1998
From:	Antony M, Linde B, Wojchowski A NORTHERN STATES POWER CO.
To:
Shared Package
ML20216H378	List: ML20216H372 ML20216H402
References
98-106, 98-106-R05, 98-106-R5, NUDOCS 9804210127
Download: ML20216H402 (28)

Text

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l Attachment 1 Evaluation for LOCA Aging at 1880 MWt l

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l 9804210127 98040s PDR ADOCK 05000263 PDR

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!, MONTICELLO NUCLEAR GENERATING PLANT 3494 l TITLE: CALCULATION COVER SHEET Revision 5 l Page 1 of 1 Page 1 of 6 l CALCULATION COVER SHEET l

Title Evaluation For LOCA Aging At 1880 Mwt C A - 106 Add.

Vendor No.

Associated Reference l Assigned Personnel a i Name (Print) Signature Title initials Van Linde h&Yb, Sr. Production Engr. $

Matt Antony ffbl/b,Nlth Production Engr. $).5k Nun ):lt o ui, M ./ ssse Al3

/ /

7 Record of issues Total No. Last Approval Rev Desenption of Sheets Sheet No. Preparer Verifier Venfier Approval Date 1 Revision f, sddtion of date to table 1 :,.s %<i N leb h hN Y ]-

0 Vendor Verification / Approval in Document I l

Verification Method (s) '

C Review 0 Alternate Calculation O Test C Other References / Filing Locations 1.

2.

Associated Subjects / Component - EQ l

3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

FOR ADMINISTRATIVE. '

Reso Suov: GSE-NGS l Assoc Ref- AWi-05 0125 l SR: N Frea- O vrs

+

' USE ONLY L ARMS- 3494 I Doc Type- 3042 l Adrnin initials- Date-APPROVED (Signatures available in Master File)

CALCULATION C A-98-106 REV0 EVALUATION FOR LOCA AGING AT 1880 MWT PAGE 2 OF 6 i

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, PURPOSE 1

The purpose of this calculation is to evaluate specific environmentally qualified (EQ) equipment

! located in the Drywell for DBA LOCA accident aging at the Rerate power level of 1880 MWt in '

l response to an NRC request for additional information to demonstrate margin. This will be l accomplished by comparing the 1880 MWt DBA LOCA test profile to the test profile for the DG O'Brien containment penetrations and General Atomic Radiation monitors. These components were selected by the NRC for review based on meetings held at NRC headquarters in White Flint, MD on March 30,1998. J BACKGROUND

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EQ components located in the containment are qualified for their required operating time, plus ,

margin as required by 10 CFR 50.49. For those components with a short operating time, the test l

profile bounds the required operating time of the component and qualification is demonstrated.

In the case of equipment with a longer operating time requirement, the qualification test duration I may not envelope the required operating time. In some cases due to the methodology used during the testing of equipment, portions of the test profile may not bound the accident profile (see figures in attachment 2) .

When required, component evaluations are made using the Arrhenius Methodology as provided in Reference 3. The Arrhenius Model establishes a correlation between thermal aging of different temperature time histories through consideration of material properties of the constituent components in an equipment item.

For this calculation, the following discussion is based on data appropriate for 1880 MWt with the use of the ANS 5.1 decay power time history as defined for the Power Rerate Program. For the DBA LOCA, at about 17 days it is expected that the drywell temperature will drop below 135 F

[Ref. 6].

The limiting drywell parameters for the DBA LOCA for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are available in Reference 9, File 1880_DBA. Drywell parameters for the DBA LOCA from 1 day through 180 days are provided in Reference 6. These curves provide the basis for the composite profile at the 1880 MWt conditions The function of the General Atomic Radiation monitor and associated DG O'Brien electrical penetration is to provide high range monitoring of the dose rates inside containment post accident. This function is not required for breaks evaluated in SBA and IBA since under these conditions there is no fuel danure assumed and therefore no high radiation doses that would require monitoring. The monitoring function is required for the DBA LOCA since this accident provides the source for high dose rates.

NSP CONFIDENTI AL

CALCULATION CA-98-106 REV0 EVALUATION FOR LOCA AGING. AT 1880 MWT PAGE 3 OF 6 l

' To provide an evaluation of margin the test profiles for these devices will be compared to the 1880 MWt DBA LOCA profile and margin quantified and compared to the margin calculated in CA-98-105 " Qualified Life Evaluation For Containment EQ Cornponents" Rev 1 Dated 3/28/98 [10].

This calculation used a pro 61e which included conservative steps for thermal aging as shown in the figure in attachment 3. An evaluation will be performed to compare the results of the test profiles to the actual curve of the 1880 MWt profile and the stepped profile, to demonstrate the margin in this approach.

METHODOLOGY The bounding DBA LOCA accident profile for the 1880 MWt Rerate power level (Ref. 2] will be evaluated for the equivalent aging using the Arrhenius methodology [Ref. 3]. The equivalent aging for the 1880 MWt case will be compared to the test profile for the General Atomic Radiation monitor and associated DG O'Brien electrical penetration using the Arrhenius ,

methodology . To demonstrate margin, the Arrhenius methodology will be applied to the DBA )

LOCA profile (Profile {2} in Table 1) using similar time steps to those used in calculation CA- l I

98-105 [Ref.10] and this will be compared to the results using the actual data time steps from the DBA profile (Profile { 1) in Table 1) . This will result in a more realistic value of aging based o- the 1880 MWt DB A LOCA curve for comparison to the aging data from CA 98-105.

ACCEPTANCE CRITERIA l The comparison of the 1880 MWt DBA LOCA pro 61e to the test profiles must demonstrate that I the test profile provides adequate margin between the accident profile and the test profile. This I evaluation will be performed using an EXCEL spreadsheet in attachment 1. The margin l calculated for the DBA LOCA curve at 1880 MWt must demonstrate an increase in margin over the value determined in CA-98-105 [Ref.10].

INPUTS Inputs to this calculation are listed below:

1. Output data from NSP calculation CA-97-176 " Equivalent Temperature Evaluation for EQ Equipment in Containment" Rev 2. [Ref. 2]

2. DBA LOCA test data for the General Atomic Radiation monitor and associated DG O'Brien electrical penetration located in the MNGP containment as listed in the MNGP EQ Central File [Ref. 5].

3. Arrhenius methodology as defined in EWI 08.11.01 " Equipment Qualification User's Manual"

[Ref. 3]

4. Output of Calculation CA-97-197, Evaluation of Drywell Response to DBA LOCA for EQ, Rev. 0 [Ref. 6]

l NSP CONFIDENTIAL

CALCULATION CA-98-106 REV0 l'

l EVALUATION FOR LOCA AGING AT 1880 MWT PAGE 4 OF 6 l

l 5. Output of Calculation CA-98-105 " Qualified Life Evaluation For Containment EQ l Components" [Ref.10]

ASSUMPTIONS

1. Qualified life for EQ components is typically evaluated based on an average drywell temperature of 135 F over the life of the component prior to the accident. The mixed drywell temperature of 135*F is used as an initial assumption for primary containment accident response evaluations. Computer alarms along with administrative controls are established to insure appropriate actions are taken if this temperature is ever reached during normal plant operation. Therefore the use of 135 to evaluate aging of components while in service for the purposes of this calculation is an appropriate and conservative assumption.

ANALYSIS The Arrhenius Methodology was used for all calculations in Attachment 1 (Reference 3 and Reference 1). Activation energies used in the analysis are from Reference 5. The equation used for calculations in Attachment 1 is based on the Arrhenius equation from Appendix 14.2 of Reference 3. The Arrhenius equation is:

t, = t exp ((eV) X 1.16 X 10'(1/r,- 1/ri)}

where:

t, is thermal aging life derived from the Arrhenius equation, exposure time limit at one specified temperature (T.)

eV is the activation energy ti is the test exposure time, or in this case the time spent at the accident temperature associated with thia time step T iis the test temperature, or in this case the accident temperature T. is the specified temperature to which the Arrhenius equation is doing the comparison The first column of each spreadsheet calculation shows time after the start of the LOCA test in seconds. The second column shows the temperature of the containment at the time shown for each associated test or accident time history. The third column shows the equivalent thermal life based on a reference temperature of 135 F for that time interval. The equation used for the tested accident profile rvaluation with an activation energy given in the top cell in the third column is shown below:

=(B4 B3)*EXP((0.8*11600)*((1/330.372)-(1/(((C3 32)/1.8)+273.15))))

l Where:

l (B4 B3)is the time from the previous time step to the current time step l

• is indication of multiplication j EXP is indication of e raised to the power shown by the remaining equation 1 0.8 is the activation energy, i.e. 0.8 eV, which varies with component type l l

NSP CONFIDENTIAL i

CALCULATION CA-98-106 REV0 EVALUATION FOR LOCA AGING AT 1880 MWT PAGE 5 OF G 1 l 11600 is a conversion factor to convert eV to 'K (Inverse of Boltzman's constant)

( 1/330.372 is I divided by 330.372*K or 135'F which is to determine the thermal aging life at this temperature 1/(((C3 32)/1.8)+273.15 is the test. or accident, temperature based on the value provided for the l previous time step as shown in colu.no 2 l This results in evaluating accident aging by always maintaining the temperature at the higher temperature from the previous time step over the time from the previous time step to the current

. time step. This provides a conservative value for accident aging since the evaluation is I

essentially always done at values equal to or higher than the accident time history curve.

The test profile is evaluated by averaging the temperature of the previous aid current time steps. ,

This results in a conservatively lower value for temperature and therefore a more conservative j evaluation of the test profile aging . This provides a conservative value for test aging since the evaluation is essentially do.te at values equal to or less than the aging time history curve.

CONCLUSION The following table provides a summary of the results of the comparison of the component specific test profile to the DBA LOCA accident profile for the 1880 MWt case, as well as the 1670 MWt and 1880 MWt composite profiles from Ref.10.

Table 1 Aging Comparison 1

Accident Profile General Atomic DG O'Brien Ctmt Case Radiation Monitor Penetration Aging /

Aging / % Margin  % Margin 1670 MWt Composite [Ref 10] 0.42 Yr 0.13 Yr 1880 MWt Composite [Ref.10] 1,17 Yr 0.24 Yr Qualification Test Aging [Ref.10] 1.4 Yr 0.3 Yr Test Profile 1880 MWt DBA LOCA (2} 1.11 Yr n9.3% 0.238 Yr / 79.3%

(with step curve function) l 1880 MWt DBA LOCA { l) 0.34 Yr / 24.3% 0.14 Yr / 46.7%

(Actual profile) l The % Margin values given in the table above reflect the percent of total test profile aging that the accident profile represents. This value is derived by dividing the accident aging by the Qualification Test Aging.

above the test profile as demonstrated on figures in attachment 2. This does not impact the environmental qualification evaluation since the additional margin demonstrated in table I clearly shows that the test profile aging bounds the accident profile aging with significant margin.

The spreadsheet calculation as described in the Analysis section is provided as Attachment 1. A review of the aging results in table I shows that there is significant margin between the aging NSP CONFIDENTIAL

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CALCULATION CA-98-106 REV0 EVALUATION FOR LOCA AGING. AT 1880 MWT PAGE 6 OF 6 '

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defined for the test profile and the required accident aging for the 1880 MWt profile (2} above I used for evaluation. Additionally, significant margin is demonstrated by a comparison of the

! test profile aging to the Arrhenius methodology applied to the actual DBA curve (1 } above.

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FUTURE NEEDS None identified. l l

ATTACHMENTS

1. EXCEL Spreadsheet for Aging Analysis

2. Graphs showing linear and Log plots of accident and test temperature profiles l

3. Graph showing Comparison on DBA LOCA profile at 1880 MW to the Step function profile

4. Verification Check List form 3495

REFERENCES:

1. Nuclear Power Plant Equipment Qualification Reference Manual, published by Electric Power Research Institute, Copyright 1992

2. CA-97 176 " Equivalent Temperature' Evaluation for EQ Equipment in Containment" Rev 2 l

3. EW108.11.01 " Equipment Qualification Users Manual" Rev. 0

4. Letter from NRC to R.O. Anderson, NSP, "Monticello Nuclear Generating Plant - Request for l Additional Information on License Amendment Request Entitled ' Supporting the Monticello Nuclear l Generating Plant (MNGP) Power Rerate Program' (TAC No. M96238)" February 11,1998

5. Monticello Nuclear Generating Plant (MNGP) EQ Central File l

6. CA-97-197," Evaluation of Drywell Response to DBA LOCA for EQ", Rev. 0

7. Containment Response Evaluation, August 1997, GE NE-T2300731-1, DRF T23-00731 .

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8. AE-083-0983,"Monticello Nuclear Power Plant Extended Drywe.:1 Temperature Analysis", October 1983 l 9. GE letter from P. T. Tran to S. J. Hammer, GLN-97-031, Suppression Pool Temperature Time Histories i

for 400 Days (Task 6.0), dated September 3,1997

10. CA-98-105 " Qualified Life Evaluation For Containment EQ Components" Rev 1 Dated 3/28/98 NSP CONFIDENTIAL

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CA-98-106 Page1 of7 Rev~1 Attachment I l

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Spread Sheets for Evaluation of Test Data 4

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f NorthIrn Stat:s Attachm:nt 1 to Pagm2 of 7 Pcw:r C3. CA-08106 Confidential

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l The data below is for the Accident aging for the

! Composite Accident profile developed in Calculation CA-97-176. This is the 1880 MWt bounding curve.

l DG OBRIEN l lGA RAD MON j l Time, sec ICA-97176 Accident Aging, sec Time, SecICA 97-176 Accident Aging, Sec l 0.1 j 3351 0.1 l 335 l 3001 335l 2.49E+04 300j 335 3.52E+051 300l 3301 8.30E+00 3001 330 1.18E+02 6001 330I 2.29E+04 6001 330 3.09E+05 l

6001 2b510.00E+00 6001 285 0.00E+00 1500l 285l 3.09E+04l l 15001 285 2.58E+05 55000 2301 1.84E+061 l 550001 2301 1.53E+07 _

432000 163 4.23E+061 i 4320001 1631 1.81 E+07 i 1140480 163 1.56E+061 l 1140480 163 2.51E+061 l l Sum, sec 7.71 E+061 1 Sum, sec 3.68E+071 ISum, hr 2141l Sum, hr I 10228)

ISum, yr 0.24 j Sum, yr j 1.171 I l l I l l I l l  ! I DG OBRIEN lev =0.5 l lGA RAD MON eV=0.8 l AGING FOR DBA @1880 IAGING FOR DBA @1880 l Time,Sec Temp Accident Aging,Sec Time, SeclTemp Accident Aging,Sec 0.1 285 10299 0.11 285 859551 3001 285 0 3001 285 OI 3001 285l 10302 3001 285 859841 6001 285l 30907 600I 285 2579521 15001 2851 1837233 15001 235 153338281 550001 2851 0 550001 285 01 -

550001 2281 4050161 55000i 228 168325851 4320001 2281 0 4320001 228 01 4320001 1631 1560222 4320001 163 25055421

_11404801 163 .

11404801 163 l l SUM,SEC 7499124 SUM,SEC i35101847 SUM, YR l . 0.237796 ISUM, YR l l 1.113072i l I I I l

, , i i The data above is for the DBA LOCA 1880 MWt profile using the steps as evaluated in Calculations CA 97-197 and CA 97-176. This method of step function is used to evaluate the DBA LOCA profile in a conservative manner.

This is presented visually in the graph in attachment 3.

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N:rth:rn Statis Attachment 1 to Page3of 7 P:wer Cc. CA 98-106 Confidential D.G. OBnen lAct Enrgy = 0.5 GENERAU Act Entgy = 0.8 time, Sec Test Temp Aging,sec ATOMIC 0.01 135 time, Sec Test Temp Aging,sec 10 225 3. A4 E+01 0.1 75 20 280 1.81 E+02 38 295 3.35E+02 30 315 4.33E+02 90 355 4.68E+04 40 330 6.73E+02 300 355 4.14E+05 60 330 1.53E+03 300 365 0.00E+00 120 331 4.62E+03 10800 365 2.65E+07 180 340 5.02E+03 10800 345 0.00E+00 240 340 5.40E+03 21600 345 1.65E+07 360 338 1.06E+04 21600 270 0.00E+00 I 540 340 1.59E+04 32400 270 1.95E+06 570 340 2.70E+03 32400 78 0.00E+00 600 300 1.93E+03 Aging Sum, See = 4.54E+07 720 260 3.75E+03 Aging Sum. Yr = 1.4

.. 780 200 6.74E+02 l l 960 165 6.60E+02 REQ'D OP TIME I 1080 158 2.54E+02 1140480 l

1200 150 2.07E+02 l

1365 150 2.54E+02 Accident Aging = 1.17 1410 340 6.97E+02 l 1440 335 2.59E+03 This data is a compilation of the aging for the 1680 340 2.07E+04 Test profiles for the DG OBrien and General 1920 335 2.07E+04 Atomic Rad monitor. This data is compiled in 2100 300 1.11 E+04 calculation CA-98-105 [Ref 10].

2700 300 2.72E+04 3120 300 1.90E+04 3480 298 1.60E+04 3660 297 7.79E+03 3960 293 1.24E+04 4260 290 1.16E+04 4500 283 8.48E+03 4680 280 5.79E+03 4920 277 7.28E+03 5220 274 8.60E+03

• 5400 271 4.87E+03 5580 269 4.63E+03 5760 265 4.37E+03 6060 262 6.79E+03 6300 260 5.17E+03 6480 258 3.72E+03 6540 250 1.12E+03 6720 248 3.03E+03 6900 246 2.91 E+03 l 7080 246 2.85E+03 l' 7500 247 6.72E+03 7620 247 1.94 E+03 7920 240 4.50E+03 8460 239 7.45E+03 8640 232 2.28E+03

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. NsrthIm Stat:s Attachmint 1 to Pags4.of 7 l Pcw:r Co. CA-98-106 i Confidential _

9660 231 .18E+04 i 10320 229 7.41E+03 1 l 10860 223 5.55E+03 i l 11580 217 6.47E+03 l 11820 215 1.97E+03 l 12480 211 5.05E+03 13020 221 4.43E+ 03 16800 211 3.10E+L,4 18660 213 1.39E+04 25020 212 4.81 E+04 86400 209 4.44E+05 172800 205 5.75E+05 l 259200 208 5.69E+05 l l 345600 210 6.03E+05 432000 212 6.32E+05 i 518000 212 6.44E+05 -

,, 604000 212 6.44E+05 .

691200 212 6.53E+05 777600 210 6.32E+05 864000 208 6.03E+05 l 950400 200 5.36E+05 l 1036800 200 4.87E+05 l 1123200 202 4.99E+05 l

1209600 202 5.11E+05 1296000 206 5.36E+05 l 1 l

1468800 82 2.25E+05 l Aging Sum,Sec = 9.22E+06 l Aging Sum.Yr = 0.31 l l e

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• N[rth:rn Stat:s Attachm:nt 1 to Paga5 of 7 l

Pgwer Co. CA-98106 l Confidential l l l  !

See Text box at end of Data below DG OBRIEN eV=0.5 l GA RAD MON eV=0.8 l Time, Sec DBA Tem Accident Aging,Sec Time, Sec DBA TemlAccident Aging. Sec

! 0 l

0.1 135 13 0.1 135 13 13 284.9 411 13 284.9 3429 l

25 278.2 211 25 278.2 1632 32 278.2 151 32 -

278.2 1165 37 278.2 181 37 278.2 1399 43 278.8 183 43 278.8 1424 49 277.2 207 49 277.2 1582 56 277.6 209 56 277.6. 1602 l 63 277.6 209 631 277.6 1602 l

,, 70 277.4 178 70 277.4 1365 76 277.3 237 76 277.3 1814 84 277.3l 178 84 277.3 1360 90 277.2l 207 90 277.2 1582 97 277.2l 1273! 971 27,7.2 9720 140 277.6l 2058 140! 277.6 15789 209 277.31 2136 2091 277.3 18325 281 276.8 1998 ~ 281 276.8 15182 349 276.4 1982 349 276.4 14996 417 276.2 1830 417 276.2 13808 i l 480 276.3 18331 480 276.3 13851 1 543 276.4 2216 543 276.4 16761 619 276.5 7039 619 276.5 53313 860 276.6 7228 860 276.6 54809 i 1107 276.8 7344 1107 276.8 55817 l 1357 276.6 7316 1357 276.6 53475 1607 276.4 7288 1607 276.4 55134 1857 276.1 7246 1857 276.1 54626 2107 275.7 6931 2107 275.7 52013 2348 274.6 5913 2348 274.6 43806 2558 272.8 8456 2558 272.8 61348 2869 269.9 8221 2869 269.9 57653 3189 265.6 7104 3189 265.6 47346 3490 261.5 7525 3490 261.5 47745 3836 257.8 8436 3836 257.8 51186 l 4254 254.6 8736 4254 254.6 50970 4716 252.4 7772 4716 252.4 44133 5146 251.2 8058 5146 251.2 45083 5603 250.6 7697 5603 250.6 42746 l 6045 249.9 7741 6045l 249.9 42617 6496 248.3 7704 64961 248.3 41573 6960 2461 6820 6960 2461 35758 7391 243.8 7509 7391 243.8 38292 7888 241.4 7324 7888 241.4 36226 8398 239.4- 6049 8398 239.4 33507 l

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• Nbrth:m StatIs Attachment 1 to Paga(o of 7 l Pcwer Co. CA-98-106 I Confidential )

8903 237.7 7298 I 8903- 237.7 34428 9453 236.4 7910 9453 236.4 36692 10066 235.3 13243 10066 235.3 60565 ,

11117 234.2 13424 11117 234.2 60520 j 12208 233.9 13019 12208 233.9 58465 l 13273 234 13500 13273 234 60707 l 14375 234.2 13337 14375 234.2 60131 15459 234.5 13585 15459 234.5 61489 16556 234.7 13321 16556 234.7 60449 17627 234.8 13562 17627 234.8 61622 18715 234.9 13304 18715 234.9 60528 19780 234.9 13916 19780 234.9 63313 20894 234.9 13641 20894 234.9 62063 21986 234.9 13566 21986 234.9 61722 23072 234.9 13541 23072 234.9 61608 24156 234.9 13554 24156 234.9 61665

,, 25241 234.9 13691 25241 234.9 62290 26337 234.7 13296 26337 234.7 60336 27406I 234.6 13516 27406 234.6 61252 28495 234.5 13734 28495 234.5 62162 l 29604 234.3 13317 29604 234.3 60118 30684 234.1 13554 30684 234.1 61029 31788 233.9 13679 31788 233.9 61430 ,

32907 233.6 13019 32907 233.6 58240  ;

33979 233.4 13459 33979 233.4 60048 35092 233.1 13707 35092 233.1 60920 36233 232.8 12640 36233 232.8 55954 37292 232.5 13280 37292 232.5 58561 38412 232.3 13010 38412 232.3 57220 39514 232 12949 39514 232 56727 40618 231.7 12433 40618 231.7 54254 41685 231.4 13012 41685 231.4 56556 42809 231.1 12490 42809 231.1 54073 43895 230.8 12591 43895 230.8 54296 44997 230.5 12349 44997 230.5 53046 46085 230.1 12286 46085 230.1 52499 47177 229.8 12720 47177 229.8 54137 48315 229.4 12298 48315 229.4 52067 49425 229 11631 49425 229 48981 50484 228.7 12121 50484 228.7 50845 51595 228.3 12015 51595 228.3 50133 52706 227.8 12001 52706 227.8 49743 53828 227.4 11715 53828 227.4 48301 54933 227 11612 54933 227 47622 56038 220.5 11681 56038 226.5 47590 57162 226.1 11712 57162 226.1 47462 58299 225.6 11419 58299 225.6 45969 59420 225.1 11041 59420 225.1 44151 60516 224.6 11128 6C316 224.6 44202 61633 224.2 10921 61633 224.2 43147 627391 223.7' 11141 627391 223.7 43724

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' N::rth:rn Stat;s Attachm:nt 113 Pag 37 of 7 Pcwer Co. CA 98-106 Confidential 63880 223.3 10732 63880 223.3 41893l l 64989 222.9 10339 64989 222.9 40143 i 66067 222.5 10523 66067 222.5 40635 l

67174 222.1 10570 67174 222.1 40598 68296 221.7 10186 68296 221.7 38913 69387 221.2 10127 69387 221.2 38429 j 70484 220.8 10018 70484 220.8 378101 71579 220.4 10109 71579 220.4 379481 i 72694 220 9965 72694 220 372021 73803 219.6 9455 73803 219.6 35147 74806 219.2 9742 74866 219.2 35977 75970 218.7 9571 75970 218.7 35107 i 77067 218.3 9208 77067 218.3 33591 78132 217.9 9733 78132 217.9 35313 79268 217.5 9653 79268 217.5 34833 80405 217.1 9363 80405 217.1 33605

.. 81518 216.6 9266 81518 216.6 33027 ~

82632 216.2 9255 82632 216.2 32810 l 83755 215.8 9269 83755 215.8 32679

~

84890 215.4 8659 84890 215.4 30359 85960 215 3544 85960 215 12358 86402 214.8 159282 8640.' 214.8 553889 106358 207 200231 106358 207 624594 136425 198.8 219206 136425 198.8 608276 l 176429 188.2 169115 176429 188.2 .

401638 I 216432 181.5 285812 216432 181.5 613559 l 296438 171.6 138200 296438 171.6 254532 346378 167.3 1483_53 346378 167.3 255256 406426 162.5 108504 406426 162.5 172843 456365 159.1 812309 456365 159.1 1225087 866592 143.6 1106383 866592 143.6 1285652 1728000 131.4 1728000 131.4 AGING SUM,Sec

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4378342 AGING SUM,Sec 10776330 l l AGING YRS 0.139 AGING YRS 0.342 The Data above is for the DBA LOCA at 1880 MWt with the methodology applied to each data point utilizing results from CA-97-176. This results in an evaluation with small time steps which closely match the DBA profile. This provides a much more realistic model of the actual curve.

l CA-98-106 Page1of5 i Rev l l Attachment 2 l

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I List of Figures :

l Figure 1 DG O'Brien vs DBA LOCA @ 1880 Mwt Figure 2 DG O'Brien vs DBA LOCA @ 1880 Mwt i l

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Figure 3 GA Rad Monitor vs DBA LOCA @l880 Mwt l

l Figure 4 GA Rad Monitor vs DBA LOCA @l880 MWt l

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CA-98-106 Page 1 of 2 Rev l Attachment 3 l

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List of Figures :

1 Figure 1 Comparison of DBA LOCA @ 1880 MWt to Evaluation Profile I

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MONTICELLO NUCLEAR GENERATING PLANT 3495 TITLE: CALCULATION / ANALYSIS VERIFICATION Revision 5 l CHECKLIST Page 1 of 1 Place initial by items verified. CA- 98 - 106 Attachment 4 Page 1 of 7F]*

REVIEW Verified

1. Inputs correctly selected. //!M

2. Assumptions described and reasonable. /K(/r-

3. Applicable codes, standards and regulations identified and met. /&y

! 4. Appropriate method used. /)J#

5. Applicable construction and operating experience considered. f & f-

6. Applicable structure (s), system (s), and component (s) listed. /k.p/F

7. Formulas and equations documented, unusual symbols defined. /%/K.

8. Detailed to allow verification without recourse to preparer. /f44

9. Neat and legible, pages all correctly numbered. Asw if:. Signed by preparer. h-

11. Interface requirements identified and satisfied. //e

12. Acceptance criteria identified, adequate and satisfied. /4k-l 13. Result reasonable compared to inputs. /k/w l

14. Basis of all assumptions, acceptance criteria and inputs are identified. /7#/f-

15. Conclusions not in conflict with previous analysis, USAR, Technical Specifications or NRC Safety Evaluations. #d#

ALTERNATE CALCULATION

16. Attemate calc results consistent with ongm :. //4-#/ut

17. Items 1-4 above verified. (Required by ANSI N.45.2.11) A/4 -#w l TESTING

18. Testing requirements fully described and adequate. M-#/J#-

19. Shows adequacy of tested feature at worst case conditions. M -//f. #

20. If test is for overall design adequacy, all operating modes considered in determining test conditions. A/4 -MF  !

1

21. If model test, scaling law: . ad error analysis established. N4 -Mut - 1

22. Results meet acceptance criteria, or documentation of acceptable resolution is attached.

N/f -#W  !

1 OTHER (Explain) l FINAL DOCUMENTATION (Verify applicable items included)

23. Altemate or check cales $N M

24. Summary of test results. A4 hMl"'

25. Comments.(errors, discrepancies, recommendations). /k1/r

26. Method of resolutio co nts. #M Completed By: / / Date: h/N V

3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

2 FORADMINISTRATNEM Rese Suev- GSE-NGS l Assee Ref- AWi-05 0125 i SR- N Freo- O vrs DCEE~USE'6NEi M O ARMS' 3495  ! Doc Tver 3042 l Admin initials- Date APPROVED (Signatures available in Master File)

c ..-

6 I

Comments to CA-98-106 l

i 1. The purpose should address why these two components were used to l

4 demonstrate mstgin. It appears that the referenced components provided l the slimmest margin in the CA-98105 calculation. Is this information Nl4fh requested based on the CA-93-105 calculation?

l d 2. The activation energy stated in the analysis Arrhenius definition is j g) inconsistent with that used in the sample equation. It may be better to not i q use an example activation energy (just use eV). This may be less confusing.

l

3. Attachment No.1 1880 MW DBA-calculation for aging should indicate

! Reference 9 in addition to Calculation CA-97-197. They are botfi required to 1

' I ja p build the curve presented. Calculation CA-97-176 could also be referenced Q$ in lieu of CA-97-197 and Referenca 9.

4. Add VerIication Checklist as Attachment 4.

1 \

j i  !

1 l

[

~ -

~

1

, \

MONTICELLO NUCLEAR GENERATING PLENT 3495 TITLE: CALCULATION / ANALYSIS VERIFICATION Revision 5 1 -

CHECKLIST Page 1 of 1

_ 1 Place initial by items verined. CA- W /cir,L f&. /f Attachment 4 l Page y cf 's 3

REVIEW hr Verified 1.

2.

Inputs correctly selected.

Assumptions described and reasonable.

/2/r l

l

_ /fj,/p

3. Applicabb codes, standards and regulations identified and met. #,1;/t

4. AppropnF method used. /$/r

5. Applicr'., , construction and operating experience considered. y,y %fy/ m#t

6. Applicable structure (s), system (s), and component (s) ilsted. . ppm >,1-

.y

7. Formulas and equations documented, unusual symbols defined. r JW-av/r

8. Detailed to allow verification without recourse to preparer. /,1/pt-

9. Neat and legible, pages all correctly numbered. /hSr

10. Signed by preparer. An-i 11. Interface requirements identified and satisfied. /ke l 12. Acceptance criteria identified, adequate and satisfied. /W l 13. Result reasonable compared to inputs. Au/w j 14. Basis of all assumptions, acceptance criteria and inputs are identified. Asn- l l

15. Conclusions not in conflict with previcus analysis, USAR, Technical Specifications or NRC l Safety Evaluations. /!4c ALTERNATE CALCULATICN

16. Alternate calc results consistent with original. A/I W11

17. Items 1-4 above venfied. (Required by ANSI N.45.2.11) # 44 TESTIN,G,

18. Testing requirements fully dese,ibed and adequate. A/8 -/!!.W

19. Shows adequacy of tested feature at worst case conditions. A eta M

20. If test is for overall design adequacy, al! operating modes considered in determining test conditions. /&a v

21. If model test, scaling laws and error analysis established. i jLHn+

22. Results meet acceptance enteria, or documentation of acceptable resolut:en is attached. jvete OTHER (Erplain)

FINAL DOCUMENTATION (Verify applicable tems included) r 23. Altemate or check cales /& /n W

24. Summary of test resutte. M -/f >

25. Comments (errors, discrepancies, recommendations). NS mF

26. Method of resolution of c.omments. AlkmW Completed By: /((NQhI w 9 .

Date: M6/f?

_' /

Su87 (DOCUMENT CHANGE, HOLD A:C CEMMENT FMf) incorporated: C" /UM ZFOR ADMINISTRATIVE / Pese Suev- GSE-NGWAAssoc Aef- AWi 05.0125 l SA AN Frea: !O , vrs

/; WUSE ONj.Y I-AAMS- 3495 /'T Doc Tvea- 3042 i Adrnin initialr l/Y- Date 7 / lO N)

M/jrs

l l

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( i Attachment 2 l l MOV information l

l 1

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l 1

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1 l

1. What are NSP's improvement plans to address possible motor damage for MO-2034 l and MO-4229 at relate conditions?

NSP Response Prior to operat:on at rerate conditions, NSP will initiate a condition report to evaluate whether the subject valves are capable of allowing a subsequent operation after the I

required isolation safety functions are completed. This evaluation may include an examination of assumptions and methodologies, additional administrative controls, and modifications. The evaluation will be completed in order to institute the corrective l actions, if any, by the end of the next scheduled refueling oistage.

2. What are NSP's improvement plans regarding MOVs with relatively low capacity margin at rerate conditions?

l NSP Response Of the five valves discussed with the staff, three valves now have acceptable excess capacity. These valves and the approximate margin values are listed below.

1 \

l MO-2373 (initial Ulargin 5%)

l ActuatorNalve replaced this outage, now 32% margin. ]

l l

MO-2015 (Initial Margin 6%)

Adjusted this outage to 0% based on rate of loading and full dp test.

MO-2006 (Initial Margin 6%)

Adjusted this outage to 17%.

The remaining valves include MO-2398 (3%) and MO-2034 (6%). These margins wiil be evaluated by a method similar to that described for issue 1. above. Prior to operation at rerate conditions, NSP willinitiate a condition report to evaluate the capacity margin of  !

MO-2398 and MO-2034. This evaluation may include an examination of assumptions I and methodologies, additional administrative controls, and modifications. The evaluation will be completed in order to institute the corrective actions, if any, by the end of the next scheduled refue!ing outage.

s a

f l

1 Attachment 3 NSP Commitments for the Monticello Power Rerate i

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l o

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c The following commitments apply to the implementation of the Menticello power rerate program.

s All plant changes described in Exhibit D of NSP's power rerate license amendment request dated December 4,1997 will be completed prior to implementation of power ,

terate, l l

All commitments contained in Exhibit H of NSP's power rerate license amendment

submittal dated December 4,1997 will be completed as described therein.

Feedwater and Condensate System area ambient temperatures will be monitored at l rerate conditions to confirm that design temperatures are not exceeded.

l Feedwater and Condensate System testing will be conducted as described by NSP's 1 l response to Question 17 contained in NSP's power rerate submittat dated March 26, 1998.

j The rerate star.up test program will include a requirement to monitor moistum

separator drair

system stability.

l l

The adequacy of the service water system will be confirmed by monitoring the

! system and its loads during the rerate startup testing program.

The final empirical relation between turbine 1st stage pressure and peicent reactor i power will be determined during the rerate startup testing program, i

1 l

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l

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