ML022680603

Response to Request for Additional Information Regarding License Amendment Request for Revised Pressure and Temperature Limit Curves

ML022680603
Person / Time
Site:	Monticello
Issue date:	09/16/2002
From:	Forbes J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MB4976
Download: ML022680603 (21)

Text

Monticello Nuclear Generating Plan Committed to Nuclear xceljence Operated by Nuclear Management Company, LLC September 16, 2002 10 CFR Part 50, Section 50.90 US Nuclear Regulatory Commission Document Control Desk Washington DC, 20555-0001 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Response to Request for Additional Information Regarding License Amendment Request for Revised Pressure and Temperature Limit Curves, (TAC # MB4976)

Reference 1: Nuclear Management Company, LLC Submittal of License Amendment Request for Monticello Nuclear Generating Plant Regarding Revised Pressure and Temperature Curves, dated April 22, 2002.

Reference 2: NRC Request For Additional Information Related To License Amendment Request (TAC No. MB4976) dated August 13, 2002.

Pursuant to and in accordance with the requirements of 10 CFR Part 50, Section 50.90, Nuclear Management Company, LLC (NMC) herein provides its response to the NRCs request for additional information regarding the License Amendment Request for Revised Pressure and Temperature Limit Curves, for the Monticello Nuclear Generating Plant.

Reference 1 proposed Technical Specifications changes to Appendix A of Operating License DPR-22, for the Monticello Nuclear Generating Plant. The purpose of the License Amendment Request was to revise the Monticello Technical Specifications (TS)

Section 3.6, Figures 3.6.2, 3.6.3 and 3.6.4, to revise the Pressure and Temperature Limit Curves. The proposed Pressure and Temperature Limit Curves were developed in accordance with the 1989 Edition, American Society of Mechanical Engineers (ASME) Code Section Xl, Appendix G; 10 CFR 50, Appendix G; and ASME Code Case N-640. This Code Case allows use of the Kic fracture toughness curve shown in ASME Code, Section Xl, Appendix A, Figure A-4200-1, as the lower bound for fracture toughness in place of the Kia fracture toughness curve of ASME Code, Section Xl, Appendix G, Figure G-2210-1.

Reference 2 requested Nuclear Management Company to provide additional information in support of the license amendment request submitted by Reference 1.

2807 West County Road 75 a Monticello, Minnesota 55362-9637 fr\

Telephone: 763.295.5151

• Fax: 763.295.1454 P

USNRC Nuclear Management Company, LLC Page 2 Exhibit A provides the NMC response to the NRC's request for additional information for the previously submitted License Amendment Request.

Ifyou have any questions regarding this response to Request for Additional Information please contact Doug Neve, Licensing Manager, at (763) 295-1353.

Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Subscribed to and swom before me this /4ý ...d*-af-*

)KAT1I-IYN 1. KLi.,

NOTARY PUBLIC - MJN'NELSJTA

-My Comnm. Excp. Jan. 31, 20M5 Notary /

• Attachments: Exhibit A - Response to Request for Additional Information Regarding License Amendment Revised Pressure and Temperature Limit Curves (TAC # MB 4976)

Attachment I Cover Sheet and Relevant Pages from Calculation CA-02-093, Revision 1, "Pressure Temperature Curve Adjustment for Water Elevation."

Attachment 2 Cover Sheet and Relevant Page from Calculation CA 02-083, "P-T Curve Limits Using K1c Methodology."

Attachment 3 Figure 2 from Operations Manual C-1 and Figure 1 from Operations Manual C-3 Attachment 4 - P-T Limit Data Points For The Irradiated Beltline Curve cc: Regional Administrator-Ill, NRC NRR Project Manager, NRC Sr. Resident Inspector, NRC Minnesota Department of Commerce J. Silberg, Esq 2807 West County Road 75 e Monticello, Minnesota 55362-9637 Telephone: 763.295.5151

• Fax: 763.295.1454

Exhibit A Response to Request for Additional Information Regarding License Amendment Request for Revised Pressure and Temperature Limit Curves (TAC # MB4976)

Exhibit A Response to Request for Additional Information Regarding License Amendment Request for Revised Pressure and Temperature Limit Curves (TAC # MB4976)

By letter dated April 22, 2002 Nuclear Management Company, LLC (NMC) submitted a License Amendment Request to revise Appendix A, Technical Specifications, to Operating License DPR-22, for the Monticello Nuclear Generating Plant. The purpose of the License Amendment Request was to provide justification for revising Monticello Technical Specification Figures 3.6.2, 3.6.3 and 3.6.4, Pressure and Temperature Limit Curves. The proposed Pressure and Temperature Limit Curves were developed in accordance with the 1989 Edition, American Society of Mechanical Engineers (ASME)

Code Section Xl, Appendix G; 10 CFR 50, Appendix G; and ASME Code Case N-640.

This Code Case allows use of the K,c fracture toughness curve shown in ASME Code, Section Xl, Appendix A, Figure A-4200-1, as the lower bound for fracture toughness in place of the Ka fracture toughness curve of ASME Code, Section Xl, Appendix G, Figure G-2210-1.

By letter dated August 13, 2002 the NRC requested additional information related to the license amendment request.

The Nuclear Regulatory Commission staff requires the following information to complete its review of the license amendment request for the Monticello pressure-temperature (P-T) limit curves, dated April 22, 2002, that was proposed based on the methods of Code Case N-640, "Alternative Reference Fracture Toughness for Development of P-T Limit Curves, Section Xl, Division 1." Below are the NRC questions and the NMC responses:

NRC Question

1. Submit all P-T limit point inputs used to generate the proposed unirradiated core beltline curves and reactor vessel (RV) non-beltline curves for pressure testing conditions, normal operating conditions with the core-not-critical (including times during heatups and cooldowns of the reactor and transient operating conditions),

and normal operating conditions with the core-critical. Include in the submittal the following parameter inputs that contributed to the calculation of the P-T limit data points:

a. KIT values and temperature gradient values (i.e., the AT values between the temperatures for RCS coolant and those at the 1/4T thickness location of the RV) used for calculation of the P-T limit data points.

b. Identification of the limiting unirradiated RTNDT values and limiting materials for the beltline and non-beltline curves. With respect to submittal of this information, confirm that the Monticello RV beltline region is plate-limited and that Heat No. C2220 (used for fabrication of RV plates 1-14 and 1-15) is the limiting material for the beltline region of the RV.

A-1

Exhibit A NMC Response

1. Calculation CA-02-093, Revision 1, "Pressure Temperature Curve Adjustment for Water Elevation," was used to determine points for the unirradiated P-T curves, the cover sheet and relevant pages are included as Attachment I to this submittal. The data points, for the unirradiated P T curves included in Attachment 1 are from Page 6 and 7 for the feedwater nozzles, Page 7 and 8 for the beltline, and page 9 and 10 for the bottom head.

a. KIT value is zero for the pressure test as the test occurs at steady state conditions. Other values of KIT were developed using the "Pipe-TS2" code by Structural Integrity Associates in Calculation CA-02-083, "PT Curve Limits Using Kic Methodology" (Relevant pages included in Attachment 2). For the Core Critical and Core Non-critical operation, the values of KIT at YAT are determined on page 7 of Attachment 2. The temperature difference between the primary fluid and the YAT are 20.40F for the vessel beltline and, 24.1 OF for the vessel bottom head. This value was determined using the most limiting allowable cooldown rate, 100 degree per hour, at the end of the cool down transient (after 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of cool down at 100 degree per hour). The temperature change limit is as described in Appendix H of the Monticello USAR.

b. The limiting material for the Monticello reactor vessel (RV) beltline region is confirmed to be Heat No. C2220 (used for fabrication of RV plates 1-14 and 1-15) as documented in plant SIA NSP-21Q 303. The most limiting material for the Monticello RV non-beltline region are flange material forgings 1-8 and 1-9.

NRC Question

2. Submit the P-T limit data points for the irradiated beltline curves that will be used by the Monticello control room operators during pressure testing conditions, normal operating conditions with the core-not-critical (including times during heatups and cooldowns of the reactor and transient operating conditions), and normal operating conditions with the core-critical.

NMC Response

2. During normal operating conditions with the core critical, or with the core not-critical, the control room operators will use the P-T curve adjusted for a 157 OF adjusted reference temperature (ART). That curve is located in the Monticello Operations Manuals C-1 (Startup Procedures) and C-3 (Shutdown Procedures) and is included as Attachment 3 to this submittal.

A-2

Exhibit A The P-T limit data points for the revised curve to replace the curve in the Monticello Operations Manuals C-1 and C-3 are included as Attachment 4 to this submittal. Using the same 1570 F shift for the end of license fluence (0.51E19 n/cm 2 ), as submitted by NMC letter dated October 10, 2000 and supplemented May 3 and May 30, 2001, and approved by the NRC in the Safety Evaluation dated July 27, 2001, for Monticello Relief Request Number 12, the revised curve is as follows:

Core Critical Operation 400 250 001111 E

00 E BE 50 perorina te

..- esel-ydo +-- roedre Pressure Limit In Vessel Top Head (PSlG.)

The operations department does not violate this curve unless Monticello is performing the vessel hydro procedure.

The procedure for achieving pressure testing conditions is a known deviation of the Operations Manuals C1 and C3 curve. The test conditions are achieved by satisfying the curve in the C1 and C3 manuals while the vessel is being heated. Once the proper test temperature is achieved, reactor pressure is increased to satisfy the point on the fluence adjusted pressure test curve that corresponds to the test conditions. This condition is determined by engineering and supplied to operations via procedure. At the conclusion of the test, pressure is reduced isothermally until the operating condition satisfies the curve presented in the C1 and C3 manuals. At that point operations is free to adjust pressure and temperature in accordance with the C1 and C3 manuals (the curve presented above). The operations curve is developed by applying the ART shift to the vessel beltline curve. Then the most conservative value for temperature for a given pressure is taken from either the adjusted beltline curve or the non-adjusted remote from beltline curve.

Additionally, NMC does not intend to provide the NRC with updates to the calculations provided in the attachments in support of the license amendment request.

A-3

Attachment 1 Cover Sheet and Relevant Pages from Calculation CA-02-093, Revision 1 Pressure Temperature Curve Adjustment for Water Elevation

MONTICELLO NUCLEAR GENERA TING PLANT '3494 TITLE: CALCULATION COVER SHEET Revision 8 Page 1 of 2 Page 1 6f 14 1 CALCULATION COVER SHEET Title Pressure TemperatureCurveAdjustment for CA 093 Add. NA Water Elevation Vendor No. NA Associated Ref. NA Assigned Personnel Name (Print) Sigr*ure Title Initials David J. Potter Engineer David Musolf Principal Engineer Gary Park SMIR Record of Issues Total No. of Last Approval Rev Description Sheets Sheet No. Preparer Verifier Verifier Approval Date 0 Original 16 Att 2 P1 DJP DM RF 4/20/02 1 Correct Typo to 16 Att 2P1 II-f1 page 9 U__

i-i Vendor Verification/Approval in Document Verification Method(s)

Z Review - Alternate Calculation - Test E] Other 3087 (DOCUMENT CHANGE, HOLD AND COMMENT FORM) incorporated:

FOR ADMINISTRATIVE J Resn Suv" CNSTP IAssoc Ref: AWI-05.01.25 SR: N Free: 0 vrs USE ONLY ARMS: 3494 Doc Tvoee 3042 1 Admin initials: Date:

APPROVED (Signatures available in Master File)

Pressure Temperature Curve Adjustment CA-02-093 For Water Elevation Revision 1 Page 6 of 14 For the feedwater nozzles, 10.53 lpsi should be subtracted from each pressure value corresponding to a given temperature. The following table presents that arithmetic.

Non Head Corrected Head Corrected Hydro Non-Critical Core Non-Cntical Core Test Core Critical Hydro Test Core Critical Condition Operation Operation Condition Operation Operation Degree Pressure Pressure Pressure Pressure Pressure Pressure Fahrenheit (psiL) (psig) (psig) - (psig) (psig) (psi) 70 0 0 0 -10.531 -10.531 -10.531 70 312.5 312.5 312.5 301.969 301.969 301.969 100 312.5 312.5 312.5 301.969 301.969 301.969 100 1465 312.5 312.5 1454.469 301.969 301.969 104.7 1562 312.5 312.5 1551.469 301.969 301.969 105 1569 312.5 312.5 1558.469 301.969 301.969 110 1683 312.5 312.5 1672.469 301.969 301.969 115 1810 312.5 312.5 1799.469 301.969 301.969 120 1951 312.5 312.5 1940.469 301.969 301.969 125 2106 312.5 312.5 2095.469 301.969 301.969 130 2277 312.5 312.5 2266.469 301.969 301.969 130 2277 1639 312.5 2266.469 1628.469 301.969 135 2466 1781 312.5 2455.469 1770.469 301.969 140 2676 1938 312.5 2665.469 1927.469 301.969 145 2907 2111 312.5 2896.469 2100.469 301.969 150 3162 2303 312.5 3151.469 2292.469 301.969 155 3445 2515 312.5 3434.469 2504.469 301.969 160 3757 2749 312.5 3746.469 2738.469 301.969 165 4102 3008 312.5 4091.469 2997.469 301.969 170 4483 3294 312.5 4472.469 3283.469 301.969 170 4483 3294 1639 4472.469 3283.469 1628.469 175 4905 3610 1781 4894.469 3599.469 1770.469 180 5370.5 3959 1938 5359.969 3948.469 1927.469 185 5885 4345 2111 5874.469 4334.469 2100.469 190 6454 4772 2303 6443.469 4761.469 2292.469 195 7083 5243 2515 7072.469 5232.469 2504.469 200 7777 5764 2749 7766.469 5753.469 2738.469 205 8545 6340.1 3008 8534.469 6329.569 2997.469 210 9394 6977 3294 9383.469 6966.469 3283.469 215 10332 7680 3610 10321.47 7669.469 3599.469 220 11368 8457 3959 11357.47 8446.469 3948.469 225 12514 9316 4345 12503.47 9305.469 4334.469 230 13780 10266 4772 13769.47 10255.47 4761.469 235 11315 5243 11304.47 5232.469 240 12475 5764 12464.47 5753.469 245 13757 6340 13746.47 6329.469 250 15173 6977 15162.47 6966.469 255 1 16738 7680 16727.47 7669.469 260 1 8457 8446.469

Pressure Temperature Curve Adjustment CA-02-093 For Water Elevation Revision 1 Page 7 of 14 265 9316 9305.469 270 10266 10255.47 275 11315 11304.47 280 12475 12464.47 285 1 13757 13746.47 290 15173 15162.47 From input 5, the elevation of the inside diameter of the upper RPV head is 1012'-6Y2" or 1012.542'. The elevation of the shroud baffle plate 957'-8 5/8" or 957.71875'(input 3).

-The static head of fluid is calculated as the density of the fluid multiplied by its height..

From assumption 1 and input 6, the density of water to be used is 62.422 ibm/ft3 . The correction for the static head of water for the feedwater nozzles is determined as follows:

Pp*h=p*(h k)=62.422 Lb*(1012.542fti- 957.71875fi)=3422.2 Ih P = Pressure (Pounds Per Square Foot) h = Fluid Height (Feet) hl = Elevation of Top Head ID (Feet) h2 = Elevation of the Feedwater Nozzles (Feet)

Converting into pounds 2

per square inch (PSI) ibm, ft 3422.2 -

2

• 2 = 23.77PSI ft 144in For the beltline region, 23.77 psi should be subtracted from each pressure value corresponding to a given temperature. The following table presents the arithmetic.

Non Head Corrected Head Corrected Non-Critical Non-Critical Core Hydro Test Core Critical Core Hydro Test Core Critical Condition Operation Operation Condition Operation Operation Degree Pressure Pressure Pressure Pressure Pressure Fahrenheit Pressure (psig) (psig) (psig) (psig) (psig) (psig)

-150 473 280 449.23 256.23

-140 281 257.23

-130 283 259.23

-125 479 284 455.23 260.23

-110 280 256.23

-100 488 291 281 464.23 267.23 257.23

-90 - 283 259.23

-85 284 260.23

-75 503 302 479.23 278.23

-60 291 267.23

-50 527 320 503.23 296.23

-35 302 -- 278.23

-25 568 351 544.23 327.23

-10 320 296.23 0 634 400 610.23 376.23

Pressure Temperature Curve Adjustment CA-02-093 For Water Elevation Revision 1 A Page 8 of 14 15 351 327.23 25 744 483 720.23 459.23 40 400 376.23 50 925 619 901.23 595.23 65 483 459.23 70 1151 788 1127.23 764.23 90 619 595.23 100 1716 1211 1692.23 1187.23 105 1847 1310 1823.23 1286.23 110 1992 1419 788 1968.23 1395.23 764.23 115 2153 1540 2129.23 1516.23 120 2331 1673 2307.23 1649.23 125 2527 1820 2503.23 1796.23 130 2744 1982 2720.23 1958.23 135 2983 2162 2959.23 2138.23 140 3248 2361 1211 3224.23 2337.23 1187.23 145 3541 2580 1310 3517.23 2556.23 1286.23 150 3864 2823 1419 3840.23 2799.23 1395.23 155 4222 3091 1540 4198.23 3067.23 1516.23 160 4617 3387 1673 4593.23 3363.23 1649.23 165 5054 3715 1820 5030.23 3691.23 1796.23 170 5536 4077 1982 5512.23 4053.23 1958.23 170.54 4118.1 4094.33 175 6069 4477 2162 6045.23 4453.23 2138.23 180 6659 4919 2361 6635.23 4895.23 2337.23 185 2580 2556.23 190 2823 12799.23 195 3091 3067.23 200 9705 3387 9681.23 3363.23 205 3715 3691.23 210 4077 4053.23 215 4477 4453.23 220 4919 4895.23 225 15699 15675.23 250 25582 25558.23 275 41876 41852.23 300 68741 68717.23 From input 5, the elevation of the inside diameter of the upper RPV head is 1012'-61/2/2" or 1012.542'. The elevation of the inside diameter of the bottom head is 949'-5" or 949.42' (input 2). The static head of fluid is calculated as the density of the fluid multiplied by its height. From assumption 1 and input 6, .the density of water to be used is 62.422 ibm/ft3.

The correction for the static head of water for the feedwater nozzles is determined as follows:

Pressure Temperature Curve Adjustment CA-02-093 For Water Elevation Revision 1 Page 9 of 14 Pph p -p* i

=k62.422 _*(1012:542ft - 949.42ft>) 3940.20 Ž-.

P = Pressure (Pounds Per Square Foot) h = Fluid Height (Feet) hI = Elevation of Top Head ID (Feet) h2 =Elevation of Bottom Head ID (Feet)

Converting into pounds per square inch (PSI) 3940.201b.m2

• f!-22= 27.36PSI 2

2 ft 144in For the bottom head region, 27.36 psI should be subtracted from each pressure value I corresponding to a given temperature. The following table presents the arithmetic.

Non Head Corrected Head Corrected Hydro Test Non-Critical Critical Core Hydro Test Non-Critical Core Critical Condition Core Operation Operation Condition Core Operation Operation Degree Pressure Pressure Pressure Fahrenheit (psig) Pressure (psig) (psig) Pressure (psig) Pressure (psig) (psig)

-150 342 176 314.64 148.64

-125 346 179 318.64 151.64

-110 176 148.64

-100 353 184 325.64 156.64

-85 179 151.64

-75 364 192 336.64 164.64

-60 184 156.64

-50 382 206 354.64 178.64

-35 192 164.64

-25 412 228 384.64 200.64

-10 206 178.64 0 461 265 433.64 237.64 15 228 200.64 25 542 326 514.64 298.64 40 265 237.64 50 675 426 647.64 398.64 65 326 298.64 70 842 551 814.64 523.64 90 426 398.64 100 1258 863 1230.64 835.64 105 1355 936 1327.64 908.64 110 1463 1016 551 1435.64 988.64 523.64 115 1581 1105 1553.64 1077.64 120 1712 1203 1684.64 1175.64 125 1857 1312 1829.64 1284.64 130 2017 1432 1989.64 1404.64 135 2193 1564 2165.64 1536.64

Pressure Temperature Curve Adjustment CA-02-093 For Water Elevation Revision 1 Page 10 of 14 140 2389 1711 863 2361.64 1683.64 835.64 145 2605 1873 936 2577.64 1845.64 908.64 150 2843 2052 1016 2815.64 2024.64 988.64 155 3107 2250 1105 3079.64 2222.64 1077.64 160 3398 2468 1203 3370.64 2440.64 1175.64 165 3720 2710 1312 3692.64 2682.64 1284.64 170 4076 2977 1432 4048.64 2949.64 1404.64 175 4469 3272 1564 4441.64 3244.64 1536.64 180 4904 3598 1711 4876.64 3570.64 1683.64 185 1873 1845.64 190 2052 2024.64 195 2250 2222.64 200 7151 5283 2468 7123.64 5255.64 2440.64 205 2710 2682.64 210 2977 2949.64 215 3272 3244.64

-220 3598 3570.64 Conclusions The tables above present (in tabular form) the PT curves for the RPV. The curves presented in CA-02-083 were offset by 10.531 psi, 23.77 psi, and 27.36 psi for the feedwater nozzles, vessel beltline region, and bottom head, respectively. This offset accounts for the static head of water between the area of concern and the location of the instrument tap where the pressure is measured. The following charts are not presented in the manner which the information will be presented in the Technical Specification when the license amendment request is complete and accepted by regulatory authorities. They are presented to show all the data included in the calculation.

Attachment 2 Cover Sheet and Relevant Pages from Calculation CA-02-083 P-T Curve Limits Using Kic Methodology I

/ J0~40,121 M o0 /1o MONTICELLOMNUCLEAR GENERATINGPLANT 13494 TI CALCULATION COVER SHEET Revision 7

.= . .Page 1 of 1 Page 1 of CALCULATION COVER SHEET Title PT Curve Limits Using Kic Methodology CA-_. - L Add.

2 Vendor No. NSf. 1Q.3oeq Associated Reference Assigned Personnel Name (Print) Signature Title Initials David Potter Engineer Record of Issues Total No Last Approval Rev, Description of Sheets Sheet No Preparer Verifier Venfier Approval_ Date 0 OnqnaI F veAd.4o U Vendor Verification/Approval in Document Verification Method(s)

Z Review E] Alternate Calculation fl Test [] Other References/Filing Locations Does this calculation supercede Yes E No E] (If YES, identify superceded calculation an existing calculation? number below) 1 Associated Subjects/Component 3087 (DOCUMENT CHANGE. HOLD AND COMMENT FORM) incorporated FOR ADMINISTRATIVE RP-n ,,,ty CNSTp Aýnt. RPf AWl.-n 01 25 -,R N Fren 0 vr USE ONLY ARMS 3494 Doc Tvoe" 3042 1 Admin initials* Date, APPROVED (Signatures available in Master File) 112,V,

Inside surface temperature at 18,000 seconds, T,,,, = 56.2IF O,,side surface temperature a. 18,000 keronds, Tt,,t = S3.31F Fluid-to- I/4T temperature drop = Tt4T - Tnld = 70.4 - 50 = 20.4°F Fluid-to-surface temperature drop = Twaii -Tnui'd = 56.2 - 50 = 6.21F 0

Through-wall temperature drop = Tout - T,,,1 = 83.3 - 56.2 = 27.1 F 2

h = 235 (AT)" 3 = 235 (6.2)'3 = 431.7 Btu/hr-ft -OF With respect to the thermal stress intensity factor, Krr. Figure G-2214-2 of Reference (2] is consulted For a wall thickness of 5.0625'. MK = 0.26. Accounting for differences in E and c.,

the following is obtained:

Krr = M, At~w. (Eaa. :,S1s/E*.u,-,,) = 0.26x27.lx (27.7x0.75)/(29.2x0 7) =7.162 ksi/in From Appendix B, the following temperature results for bottom head were obtained:

Fluid temperature at 18,000 seconds, Tfi d 500F Ti.rr = 74.12102F (@ R=104.48438")

0 Inside surface temperature at 18,000 seconds, T,,j, = 56.9 F Outside surface temperature at 18,000 seconds, Tout = 93.4IF Fluid-to-1/4T temperature drop = Tirr- Tnfld = 74.12102 - 50 = 24.12102°F 1

Fluid-to-surface temperature drop = Twall - Tnrud = 56.9 - 50 = 6.90 'F Through-wall temperature drop = T.,, - T,,,,, = 93.4 - 56.9 = 36.5 F 2

h = 235 (AT)"n = 235 (6.9)"'3 = 447.3879 Btu/hr-ft -OF With respect to the thermal stress intensity factor, Krr. Figure G-2214-2 of Reference [21 is consulted. For a wall thickness of 5.9375", M, = 0.286. Accounting for differences in E and a.,

the following is obtained Krr = Mi Atai1 (E. 2anajy>,jEacure) = 0.286x36.5x (27.7x0.75)/(29.2x0.7) =10.61 ksinm Thermal -tres intensitv factor for feedwater nozzle under heatutp and cooldown operation For Krr of the feedwater nozzle. Figure 4-5 of Reference 10 is used. Since there is no cooling 0

rate for 100"F/hr, the Krr for 100 F/hr is obtained by:

0 Krr(@ 100 0F/hr) = 2 x Krr(@5 'F/hr) = 2 x 3.2 = 6.4 ksi',in Revision I 2 Preparer/Date Gary L. Stevens Chris Kobilan 3116/98 6112/01 Checker/Date H. L. Gustin Kcith Evon 416/98 6/120I File No. NSP-21Q-304 Page No. 7 of 24 8

- 2 5:>6 M

Attachment 3 Figure 2 from Operations Manual C-1 and Figure 1 from Operations Manual C-3

/*

Z, 0

P-T Curve for Critical Core Operation r.0 400 -I 350 -n 300 CD I ro CD 250 I.-\,

3 200 CD 0150 5:CD

=CD'CD Z5100 I.E 50 0 W CD

-50 0 0 rWCD

-100 (0 ,<. (I,,

(Dj

'0)05V.

0 CD pn

-150 0 500 1000 1500 2000 0 0) 4r*.

Pressure (psi)

NOTE: Compliance requires operation above curve. This curve Is based on Calculation CA-98-176 "Review of, the Test Results of Two Surv. Capsules, and Recommendations for the Materials PRoperties and PT Curves."

(

t-)

0.

P-T Curve for Critical Core Operation 400 350 -n CD 0n 300 CD 0j 250

.3 CD Zi 200 H CD~

• 150 CDQ) a)

~i100 CD CD E

50 II Cn 0~-U 0

CD

-~o c~oCD,

(°

-50 0 -4 0

-100 0 ~CD, W (DU

~1) 01 0* =3'

-150 0 500 0 1000 1500 2000 0) U)

CD

.Pressure (psi)

NOTE: Compliance requires operation above curve. This curve is based on Calculation CA-98-176 "Review of the Test Results of Two Surv. Capsules, and Recommendations for the Materials PRoperties and PT Curves."

Attachment 4 P-T Limit Data Points For The Irradiated Beltline Curve

Pressure (PSIG) Temperature (Degree F)

-27.34 70.00 47 70.00 57 70.00 67 70.00 72 70.00 97 70.00 122 70.00 147 70.00 148.66 70.00 151.66 70.00 156.66 70.00 164.66 70.00 172 70.00 178.66 70.00 197 70.00 200.66 70.00 222 70.00 237.66 70.00 247 70.00 267 96.07 285.16 170.00 285.16 170.00 297 170.00 298.66 170.00 302 170.00 307 170.00 312 170.00 317 170.00 322 170.00 327 171.79 332 174.42 398.66 203.75 523.66 233.84 835.66 272.06 908.66 277.24 988.66 282.91 1077.66 289.23 1175.66 296.18 1284.66 301.92 1404.66 307.39 1536.66 312.77 1611.66 315.59 Ms 1683.66 318.17 1753.66 320.55 1845.66 323.52 1910.66 325.53 2024.66 328.84