ML17264B045

Rev 3 to 86-1234820-03, Low Temp Overpressure Analyses Summary.

ML17264B045
Person / Time
Site:	Ginna
Issue date:	09/19/1997
From:	Merritt Baker FRAMATOME
To:
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ML17264B042	List: ML17264B041 ML17264B043 ML17264B044 ML17264B045
References
86-1234820-03, 86-1234820-03-R03, 86-1234820-3, 86-1234820-3-R3, NUDOCS 9710020178
Download: ML17264B045 (83)

Text

Attachment VII LTOP Enable Temperature Calculation (First use of LTOP enable temperature methodology) 97i0020i78 970929 05000244 ADGCK PDR P PDR \~i

4 20697-3 (1 2/95)

CALCULATIONAL

SUMMARY

SHEET (CSS)

DOCUMENT IDENTIFIER 86-123482043 TITLE LOW TEMPERATURE OVERPRESSURE ANALYSES

SUMMARY

REPORT PREPARED BY: REVIEWED BY:

NAME MB Baker NAME GJ Wissinger SIGNATURE slGNATURE r/7(in7'.

j TITLE Engineer IV GATE I/II TITLE Engineer !V GATE fI!TI$1 COST CENTER 41Q1Q REF PAGE($ ) 32b TM STATEMENT: REVIEWER INDEPENDENCE PURPOSE AND

SUMMARY

OF RESULTS:

Framatome Technologies Inc., performed the low temperature overpressure event analyses for the Rochester Gas and Electric (RGE) R,E.Ginna Nuclear Power Station; after the steam generators were replaced with BWI<esigned generators. In this effort, a spectrum of LTOP events to bound all possible operational configurations is analyzed and the results compared to Appendix G limits and the RHR pressure limit:

RGE has received approval to utilize ASME Code Case N-514, which among other things raises the allowable p ssure to 110% of the Aj3pendix G limit.

ost limiting mass addition case Is a case with three charging puigs turned on when the primary system is at 60'F with two RC pumps running. This case resulted in a peak reactor vessel pressure of 587A4 psia which is below the limit at this temperature.

The most limiting heat addition case is with the primary system at 60'F, with an initial pressure of 329.7 psia. One RC pump is turned on with the secondary system at a temperature of 50'F higher than the primary. The peak reactor vessel pressure in this transient is 551.3 psia which is below the limit.

The limiting event for the RHR system occurs at 280'F, when two RHR pumps pm total. In this heat addition case, the peak RHR system pressure reac llowable of 674.7 psia.

This revision is a complete replacement of Revision 02.

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OR PI HAS DER RCOUIRE>ACIITS ROCIIESTER GAS 8 ELECTRIC CORP.

CODE I VERSION I REV CODE I VERSION I REV THIS BOCUMEI!ar(EGNTAINS AS VERIFIED PRIOR TO USE ON SAFETY-RELATED WORK YES( ) NO( )

PAGE 1 OF 88 AND 32a & 32b

ROCHESTER GAS AND ELECTRIC CORPORATION Inter-Office Correspondence Ginna Station September 23, 1997 SUB JECT: Approval of Vendor Technical Document "Low Temperature Overpressure Analyses for RGEE Ginna Plant" 86-1234820-03, "Low Temperature Overpressure Analyses Summary Report" TO: File FTI No. 86-1234820-03 In accordance with Engineering Procedure EP-3-P-154, rev. 0, the purpose of this memorandum is to identify that the subject documents have been reviewed and are acceptable for use as the analysis of record for the Low Temperature Overpressure Protection System (LTOPS) for Ginna. Specifically:

The assumptions used in the calculation are appropriate for the Ginna Station with either Westinghouse Model 44 steam generators or BWI RSGs.

2. The transients selected are the correct limiting transients for the Ginna LTOPS design. Several cases were run which demonstrate bounding conditions'pecifically:

a. Case 2A bounds all credible mass addition transients for which protection is provided by the pressurizer PORVs.

b. Cases 3 and 4 bound all credible mass addition transients for which protection is provided by a RCS vent > 1.1 in'.

c. Case 5 bounds all credible heat addition cases.

d. Cases 7 and 9 demonstrate adec{uate protection for the RHR system.

3. Since peak pressure for all transients is less than 800 psig, PORV tailpipe waterhammer is not a concern.

4. The analysis is done for an LTOPS actuation setpoint of 430 psig. This allows sufficient margin from a nominal setpoint of 410 psig to account for instrument error.

Memo: Page 2 Date: September 23, 1997

Subject:

File FTI No. 86-1234820-03

5. A low pressure limit, to protect an RCP seal, cannot be accommodated by a single LTOPS setpoint without unacceptable high pressure results. Therefore, this criteria is waived.

The following comments are applicable to the approval of this document and have been so marked in the document:

1. Page 20, Table 7 The'peak pressure in the reactor vessel should be 554.42 psia. ~

2. Page 21, Table 8 The peak pressure in the reactor vessel should be 413.48 psia.

3. Page 22, Table 9 - The peak pressure in the reactor vessel should be 396.72 psia.

Section 7.0 pp 28 Several values for peak pressures are incorrectly summarized. These values have been marked and corrected in the text.

These corrections are considered minor typographical errors which do not warrant a vendor revision.

Brian Flynn Primary Systems Robert E.

Engineer, is NS&L rZuyey Georg Wrobel Manager, NSEL xc: Document Control

FTI Non-Proprietary 86-1234820-03 LOW TEMPERATURE OVERPRESSURE ANALYSES

SUMMARY

REPORT Prepared for Rochester Gas 5 Etectric Corporation Prepared by: Da~e: /~ 0 M Baker, Engineer IV Reviewed by: Date: f

'~ 'Il G J'Wissinger, Engineer IV Approved by:

J.J.Cudlin, Manager, Analysis Services Unit FRAMATOME TECHNOLOGIES INC.,

LYNCHBURG, VA.

FTl Non-Proprietary 86-123482043 .

RECORD OF REVISIONS REVISION NO. DESCRIPTION DATE 00 Original issue March 1995 01 Complete revision to integrate additional runs and conclusions based on the additional runs

-all pages revised June 1997 02 Minor changes in mass addition case results-revised pages 1,3, 19,20,21,30 and 31 July 1997 03 This revision incorporates the fact September 1997 that RGE received approval for ASME Code Case N-514, which allows the peak pressure to be 110% of the Appendix G limit. This Revision completely replaces revision 02, Revision bars are in the margin.

FTI Non-Proprietary 86-1 234820-03 TABLE OF CONTENTS

1.0 INTRODUCTION

... ...5 2.0 DISCUSSION OF LTOP EVENTS .5 2.1 LTOP EVENTS INITIATEDBY MASS ADDITION. ~ 5 2.2 LTOP EVENTS INITIATEDBY HEAT ADDITION ..... 6 3.0 EVENTS ANALYZED. ............. ... 7

~

4.0 ACCEPTANCE CRITERIA ....

5.0 METHODOLOGY 15 6.0 ANALYSIS .... 1 8 6.1 MASS ADDITION CASES ... 18 6.2 HEAT ADDITION CASES 23 7.0

SUMMARY

AND CONCLUSIONS ....29

8.0 REFERENCES

- 32b PLOTS OF THE RESULTS 33

FTI Non-Proprietary 86-123482043

1.0 INTRODUCTION

Framatome Technologies Inc. (FTI) (formerly B&W Nuclear Technologies) updated the analysis of the low tempeiature overpressure (LTOP) events for the Rochester Gas and Electric (RGE) R.E. Ginna Nuclear Power Station (hereafter referred to as the Ginna plant).

The analyses shown in this document become the new analyses of record for the Ginna Station. RGE has received approval to utilize ASME Code Case N-514, which among other things raises the allowable pressure to 110% of the Appendix G limit.

The results of the analyses of the limiting LTOP events were compared with 110% of the 10CFR50 Appendix G and residual heat removal system(RHR) overpressure limits. In all cases, the peak reactor vessel and RHR system pressures were within the applicable limits.

The purpose of this revision is to present the results of additional cases that show the effects of various combinations of reactor coolant (RC) pump and RHR pump operation.

2.0 DISCUSSION OF LTOP EVENTS The United States Nuclear Regulatory Commission (USNRC) Regulatory Guide 1.99, Revision 2, dated May 1988 (Reference 1) discusses the effects of neutron irradiation embrittlement of low alloy steels used in the reactor vessel. Appendix G of Chapter 10, Part 50 of the Code of Federal Regulations giv'es the fracture toughness requirements for the reactor vessel under low temperature conditions. During LTOP events, the reactor vessel temperatures and pressures approach the Appendix G limits. The LTOP system is designed to ensure that the reactor vessel embrittlement limits are not exceeded.

LTOP events can occur during cold shutdown, heatup or cooldown. To provide protection against exceeding the Appendix G limits, the Power Operated Relief Valves (PORV) on the pressurizer are reset to a low setpoint, whenever the reactor coolant system temperature is less than,322'F. Two types of overpressurization events are considered. The first type of event is a mass addition event and the second type of event is a heat addition event.

2.1 LTOP EVENTS INITIATEDBY MASS ADDITION The mass addition events are characterized by addition of mass to a water-solid primary system. This can occur during a shutdown situation, if the charging pumps or if the safety injection(SI) pumps are started inadvertently. Technical Specification I'

'CI FTI Non-Proprietary 86-1 23482043 limits on Sl pump operability and discharge valve position eliminate the mass injection case due to a high head Sl pump start, unless protection is provided by a vent path of at least 1.1 square inches. With no vent; with three Sl pumps inoperable by Technical Specification limits, an inadvertent Sl signal will not cause an Sl pump start. Since the possibility of the startup of three charging pumps with letdown isolated can be postulated, this case is analyzed as a mass-addition event, when protection is provided by only the PORVs.

The lower limit of the primary temperature for mass addition by charging pump operation is 60'F. Above this temperature, the possibility exists that two RC pumps may be running and three charging pumps may be inadvertently started. This case also has been analyzed, with a conservative primary temperature of 60'F and compared with the ASME Code Case N-514 limit at 60'F, to show acceptability.

This is the most limiting mass addition case for Appendix G criterion.

With a primary vent of size 1.1 square inches open to the atmosphere, startup of one Sl pump is allowed. This mass addition event is analyzed at primary temperatures of 60'F and 212'F to bound the range of possible RC conditions in this configuration with no RC pumps running. When the vent is open, the PORVs are not credited as pressure limiting devices.

2.2 LTOP EVENTS INITIATEDBY HEAT ADDITION The heat addition events are characterized by an addition of heat to a water-solid primary system. Heat can be added to the primary system by the actuation of pressurizer heaters, loss of the residual heat removal system (RHR) cooling, or two types of reactor coolant (RC) pump startups while a temperature asymmetry exists in the RC loops.

The inadvertent actuation of the pressurizer heaters when the pressurizer is water solid will cause a slow rise in the water temperature and inciease in pressure, if the installed automatic pressure control equipment is not in service. Since this pressure transient is very slow, the operator should recognize and terminate the transient before an unacceptable pressure is reached. If the operator does not terminate the

'ransient, the pressure will increase and will be terminated by the PORV with little or no overshoot above the PORV setpoint. This case is not significant to the design of the LTOP system.

The loss of RHR cooling when the reactor coolant system(RCS) is water solid could be caused by a loss of flow malfunction in the component cooling water or service water systems, or the closure of the RHRs inlet isolation valves. This would cause a slow rise in temperature and pressure since there would be a continual release of core residual heat into the reactor coolant with no heat removal. This transient is also very slow and the operator has sufficient time to mitigate the event.

The first type of temperature asymmetry can occur if the reactor coolant is at a relatively warm temperature with little or no natural circulation and cold reactor coolant pump seal injection water continues to enter the system. The cooler injection

FTI Non-Proprietary 86-123482043 water will settle in a pool in the loop seal. The pressure transient is initiated by starting one reactor coolant pump. As the pump comes up to speed, the reactor coolant flowrate slowly increases in the active loop and the pool of cold water will be drawn up into the pump and discharged out the cold leg piping. Simultaneously, the pool of cold water in the inactive loop will flow backward through the steam generator at a flowrate significantly less than that of the active loop. As this pool of cold water flows through the steam generator, the temperature will increase due to heat transfer from the'secondary side of the steam generator. This causes expansion of the primary side water and an increasing pressure transient.

The second type of temperature asymmetry occurs when the RCS has been cooled without sufficient circulation. This could occur when the RHR system is used to cool the RCS without use of any reactor coolant pumps. Under these conditions, the water in the steam generator secondary side and the primary side will be in thermal equilibrium at a temperature higher than that of the reactor coolant. If one RC pump is inadvertently started under these conditions, the RCS flowrate increases and the cold water from the RCS enters the SG tubes. This results in the transfer of heat from the secondary to the primary system, causing the primary system liquid to expand and the primary system to pressurize. This is a relatively fast event and, because of the transfer of heat from the secondary system to the primary system, this event is the most limiting heat addition transient.

In the heat addition events, both RHR pumps or only one may be operating.

Therefore events with one and two RHR pumps are analyzed at various initial primary temperatures, to bound the limits of operation.

3.0 EVENTS ANALYZED A spectrum of mass addition cases were analyzed. The mass addition cases have a range of initial primary temperatures and mass additions, simulating charging and safety injection pump operation at various possible initial temperature conditions, with assumptions on RC pump operation, and operation of RCS vent.

The limiting mass addition case, the inadvertent startup of three charging pumps, was analyzed at a primary temperature of 60'F with two RC pumps operating.

In addition, two cases with Sl pump startup were analyzed, one with the primary system at 60'F and one with a temperature of 212'F. In these cases, the PORV is not credited for preventing overpressurization. Instead, a 1.1 square inch vent was modeled on top of the pressurizer, because Sl pump operability is controlled by procedure when the vent is open. The upper temperature limit of 212'F is based on saturation temperature at atmospheric conditions. Sixty degrees is the lower limit of the Appendix G curves.

The limiting heat addition case is the inadvertent start of a reactor coolant pump following RCS cooldown solely with the RHR system. This event was analyzed at

FTI Non-Proprietary 86-1 234820-03 RCS temperatures of 60'F, 85 'F, 280'F and 320 'F with the SG liquid temperature 50 degrees hotter than the RCS. The various combinations of RHR system were modeled. The transient is analyzed at 60 'F since it is the lower limit of the Appendix G limits and has the lowest pressure limit for the acceptance criterion. The event is analyzed at 320'F because this is the maximum credible temperature at which a secondary-to-primary temperature difference of 50'F can be achieved.

Specifically, the reactor coolant pumps may be tripped at 350'F. With instrument uncertainties, the temperature could be as high as 370'F. If the RCS is subsequently cooled to obtain the maximum allowed temperature difference (50'F),

the RC pump start could occur at 320'F. This heat addition event is the most limiting for the RHR overpressurization.

The various cases run are shown in Table 1 for easy reference.

4.0 ACCEPTANCE CRITERIA

-

The acceptance criteria for the LTOP events are:

1. The pressure and temperature of the reactor vessel can not exceed 110% of the steady-state Appendix G limits (ASME Code Case N-514). The Appendix G limits are given in Table 2. This table is obtained from Reference 2.

2. The pressure in the RHR system can not exceed 110 percent of the design pressure of 600 psig, or 660 psig.

Tl Non-Proprietary 23482043 TABLE 1 LIST OF CASES Case no. Description Primary RHR flow RC pump Secondary Charging Sl pump RCS vent temp. rate status temp. pump status status

'F gpm 0/1/2 OF 0/1/2/3 0/1/2; open/close

1. Mass addition case 85.0 1700.00 n/a closed Primary Press.

329.7 psia

(

2. Mass addition case 60.0 2000.0 n/a closed Primary Press.

329.7 psia 3 gpm RC pump seal return

(

2a. Mass addition case 60.0 2000.0 n/a closed Primary pressure 329.7 psia

)

3. Mass addition case 60.0 2000.0 n/a open Primary pressure 14.7 psia. No seal return.

4. Mass additiqn case 212.0 2000.0 n/a open Primary pressure 14.7 psia. No seal return.

( continued)

l Non-Proprietary 234820-03 TABLE 1(continued)

LIST OF CASES Case no. Description Primary RHR flow RC pump Secondary Charging Sl pump RCS vent temp. rate status temp. pump status status

'F gpm 0/1/2 'F 0/1/2/3 0/1/2 open/close

5. Heat addition case - 60.0 2000.0 110.0 closed Primary pressure 329.7 psia No seal return.

6. Heat addition case 85.0 2000.0 135.0 closed Primary pressure 329.7 psia No seal return.

7. Heat addition case 280.0 2000.0 330.0 closed Primary pressure 329.7 psia.

8. Heat addition case 85.0 1700.0 135.0 0 closed Primary pressure 329.7 psia.

9. Heat addition case 320.0 1700.0 370.0 0 closed Primary pressure 329.7 psia.

Note: In the mass addition cases, the RHR system is not modeled explicitly. The pressure in the RHR system is evaluated by adding a conservative hP to the suction pressure at the hot leg.

8 6-] $ 348QQ 0 F Ti Non-Proprietary TABLE 2 R.E.Ginna 24 EFPY Cooldo]ln Curve Data Points Cooldow n Caves Stcafy 8 Qlo 20F 40F lOOF T P T T P P T P 60 540 60 51$ 60 4&9 60 462 60 408 6$ 542 65 5]6 65 490 6$ ~ 463 409 70 544 70 518 70 492 70 ']65 '70 410 75 54$ 75 519 7$ 493 '75 466 4]2 80 $ 47 80 521 80 495 &0 468 80 4]g

'85 549 85 523 8$ 497 8$ 470 4]5 90 SSL 90 $ 2S 90 499 90 472 90 418 95 $ 54 9$ 528 95 Sol 95 474 9$ 42Q IOO 556 loo 530 100 $ 04 100 ~

<77 LOO 422 105 559 105 $ 33 105 S06 105. 480 ]OS 425 I IO 562 I IO 536 110 509 110 483 110 428 I Is 565 115 539 115 512 I IS 486 Ils 43]

]20 568 120 542 120 516 120 489 12O 435 125 572 12$ S]6 125 519 125 493 12$ 438 L30 576 L30 5$ 0 ]30 523 ]30 130 135 580 135 554 135 528 135 Sol, 135 447 140 $ 84 140 5$ 8 140 532 140 506 a52 145 589 145 563 ]45 537 145 St 1 I~S 457 150 594 150 568 150 542 150 S]6 ]SO 463 155 599 ]5$ 574 155 548 155 522 155 469 160 605 160 580 160 554 160 $ 29 160 476 165 612 165 587 16$ 561 165 536 165 483 170 619 170 594 170 568 170 543 17O 49]

17$ 626 I'75 601 175 576 175 55 1 175 500 180 634 180 609 180 5&5 180 560 ]&O 509 185 642 18$ 618 ]&5. 594 185 569 185 519 190 652 190 628 190 603 190 190 530 195 661 195 638 195 614 L95 590 195 200 672 200 649 200 625 200 6O2 2OO 554 20$ 683 205 661 205 637 205 61$ 568 2]0 205'28 210 696 673 210 6$ 1 210 210 583 2]$ 709 215 687 215 665 215 643 21S 599 220 723 220 701 220 '680 220 659 22O 616 225 738 225 7]7 225 696 225 676 225 634 230 754 230 734 230 714 '230 694 230 23$ 772 235 752 235 733 235 714 235 676 2CO 791 240 772 240 753 24Q 735 699 245 811 245 793 245 '775 245 758 245 724 2$ 0 &33 2$ 0 816 250 '799 250 783 250 751 255 856 255 255 825 25$ 809 255 '780 260 881 260 866 260 852 838 260 811 26$ 90& 265 895 265

'81 265 869 26$

270 937 270 92$ 270 913 270 270 8& 1 275 968 275 9$ 7 275 947 275 937 275 920 280 1002 280 993 280 983 280 975 280 285 1038 285 1030 285 1023 285 1016 285 1007 290 1077 290 107Q 290 1065 290 1061 290 1056 295 III& 29$ ]1]4 295 1110 295 1108 295 110&

300 1163 300 1160 300 1159 1159 305 1211 305 ' 1211 310 ]262 315 1318 320 ]377 325 1440 330 ]509 335 Is&i 340 1660 345 1744 350 1834 355 1931 360 203']44 365 370 2262 375 2388 11

GINNA RELAPS MODEL FIGURE 1 11 STEAM ilNE Mssv v O

670 865 dCO dss 650 0

'$3 rD 0$

r To thi" model, added 765  !

t. AHA model

2. POAV model

0. Charging pump model Moto that AFW and MFW models aro dclctcd, hero for tho LTOPS 625 73307 ~$ 6XH$

10 7 10 7330$ 11 7XH6 CDOO O5 11 C$ 305 73305 12 35 73305 4100$

2 6XH5 C$ 3OI 05 12 C$ 3OS 7XHN =.ta 7XHN 13 C$ 304 73M3 Ii 7XHQ Ol 63M3 f4 6XH$7 7XH$2 15 3t2 7XN2 ~ 633OZ 15 CX92 73341 16 $ 250 1 7330$ KI$0$ 2250$ Id CIMI 121 115 113 110 105 100 200 205 210 2$ 3 215 235 170 17S $ 80 200 27S 270 265 REACTOR VESSEL ICI AC RC 2eo Pump 8 Pump A LEFT LOOP RIGHT LOOP

$ 48

$ 50 155

FlGURE 2 GINNA REACTOR VESSEL AND CORE MODEL 364 hot leg hot leg 360 nozzle nozzle lookogo path C5 C) upper ptonum 350 Co 351 354 302 36S 352 upporpfonum 326 338 C9 cold leg 324 336 cold leg nozzle nozzle 322 334 320 332 330 Ccr 316 328 fU 44 co 375 Nota: Tgs b a twecerachannot mafol- hrh avoroga ceres CD 310 380 I CD

FIGURE 3 RHR SYSTEM MODEL n

z 0

Primary Loop Primary 0 (LTOP Active Loop) (Inactive Loop) O Hot Leg 'U Cold Leg

$ 00 280 450 469 RHR pump 8 sink 462 Heat exchanger B 453 RHR Relief Valve 468 463 473 460 45~

457 472 461 452 455 454 Heat exchanger A 475 RHR pump A 456

FTI Non-Proprietary 86-123482043 5.0 METHODOLOGY The LTOP transient analyses were performed using the RELAP5/MOD2-B8W Version 20 (Reference 5) computer code, which has received full certification at Framatome Technologies Incorporated(FTI). RELAP5/MOD2 B8W is a two-fluid, six equation', nonhomogeneous, nonequilibrium thermal-hydraulic code developed for best-estimate transient analysis of pressurized water reactors and associated systems. The code has options to consider equilibrium, homogeneous hydrodynamic control volumes and a limited ability to calculate conditions for co-existing noncondensibles. The numerical solution technique is semi-implicit finite differencing. RELAP5 is a highly flexible code that, in addition to calculating NSS behavior, can be used for simulation of a wide variety of thermal-hydraulic transients'.

RELAP5/MOD2-BBW has special process models that are not available in the

'ndustry version of the code (Reference 3). The only such process model used in these LTOP analyses is the Henry-Fauske extended subcooled critical flow model. For those instances when the pressurizer PORV experienced critical flow, the extended Henry-Fauske critical flow model is used rather than the Ransom-Trapp model. The extended Henry-Fauske model was used because it is widely accepted for use over the range of conditions experienced in these analyses and because the Ransom-Trapp model overpredicts the test data using a discharge coefficient of 1.0

~

(Reference 3). Use of the Henry-Fauske model is therefore, conservative.

The plant model that was employed for the LTOP analyses included two complete reactor coolant loops including RC pumps and steam generators.

The secondary side included steam lines, main steam safety valves (MSSVs),

main steam isolation valves (MSIVs), and turbine stop valves. A noding diagram of the RELAP5/MOD2 model is shown in Figure1. The steam generator model used for the analyses is a simulation of the U-tube replacement steam generator designed by BWI. The feedwater systems and the auxiliary feedwater systems were not modeled since these are not functioning during the LTOP events.

The primary system has a reactor vessel model with two equal and parallel core paths for adjusting the mixing of loop flows in the lower plenum. This feature was not used in the LTOP analyses as this is not required. The core had six axial nodes and a core bypass with three nodes. The upper and the lower plenum volumes were common to both the loops, whereas the downcomer was split into two parallel set of volumes. A noding diagram of the reactor vessel is shown in Figure 2.

The pressurizer was modeled as a ten node vertical pipe component and was initialized liquid solid. One PORV was attached to the top node of the pressurizer. Only one PORV was modeled because the other PORV was 15

FTI Non-Proprietary 86-1 23482043 assumed to fail closed. The PORV was set to lift when the pump suction pressure on the loop with the pressurizer exceeded 430 psig, consistent with the location of the pressure transmitters and instrument error. The PORV was sized to deliver 49.722 Ibm/s saturated steam at 2335 psig. The opening stroke time was 1.0 second using the Cv characteristics in Table 3. The model contained the piping from the PORV to the pressurizer relief tank (PRT) as well as the PRT with a rupture disc. The nitrogen blanket on the PRT was modeled.

The RC pumps were modeled as centrifugal pumps with the homologous curves representing the performance under various conditions. The pump performance curves shown in the UFSAR were used as the basis for the active octants in this pump model.

The passive metal of the whole system was modeled for the LTOP analyses.

The passive metal includes the reactor vessel walls, the reactor internals, the fuel end fittings, the hot and cold leg pipe walls, pressurizer walls, the steam generator primary side metal and the steam generator secondary side metal.

The steam generator tube metal was modeled as part of the active heat structures. The steam line metal and the RHR system passive metal were not modeled.

The RHR system was modeled as two parallel trains with two separate pumps and cross connects. Two heat exchangers were modeled as control volumes with no heat removal since the heat exchangers were assumed to maintain a constant temperature in the RCS during the LTOP analyses. The RHR relief valve was attached to the RHR system near the cold leg connection. The RHR relief valve was benchmarked for flow under the design conditions. A noding diagram of the RHR system is shown in Figure 3.

For the mass addition cases, the primary system was initialized at 60, 85, 8 212

'F, and at a pressure of 315 psig. The primary and secondary systems are decoupled since there is no heat transfer in this case. The event was initiated by starting one or three charging pumps, or one Sl pump. The flow capacity of each charging pump is 60 gpm. In the Sl pump cases, the flow rate used for one ~

Sl pump is shown in Table 4. In cases with the 1 1 sq.in. vent open, RC pumps

~

were not run, because the RCS is at near atmospheric pressure and there is insufficient NPSH to operate the pumps. Sl injection is used as the initiating event in the vent cases. The analysis was terminated after the PORV opens or an equilibrium pressure was obtained. The peak RCS pressure was compared with the acceptance criteria. Different cases have different assumptions. See Table 1 for details.

FTI Non-Proprietary '6-123482043 TABLE 3 Cversus position Copes Vulcan Valve - Model Number D-100-160 Stroke % C normalized 0.0 0.0 1.9 0.016 7.9 0.067 14.0 0.143 20.0 0.231 26.1 0.346 32.2 0.474 38.2 0.626 44.3 0.734 50.3 0.823 56.4 0.87,8 62.5 0.924 68.5 0.957 73.6 0.970 78.3 0.977 84.5 0.985 91.6 0.992 98.6 0.999 100.00 1.0 For the heat addition cases, the primary system was initialized to isothermal conditions at the required temperature with no reactor coolant pump operating.

The secondary and primary fluid in the steam generators were initialized at a temperature 50 degrees above the primary system; The RHR system was assumed to be operating with a capacity of 1700 gpm with one pump running

( 320'F case as specified in Attachment C of Reference 4 ) or 2000 gpm with two pumps running ( 60'F and the 85'F cases, consistent with minimum flow rates under these conditions). The transient was initiated by starting a reactor coolant pump in the loop that contains the pressurizer. The pump startup characteristics of Table 5 were used to bring the pump to full speed in 17.4 seconds. The analysis was run until the peak pressure was obtained. The peak pressures in the reactor vessel and the RHR system were compared with the acceptance criteria.

0 FTI Non-Proprietary 86-1 23482043 TABLE 4 FLOW VERSUS RCS PRESSURE FOR ONE SI PUMP AT THE R.E.GINNA STATION RCS Pressure, si Sl Flow, m 600 413 500 440 400 466 300 490 200 514 100 536 558 TABLE 5 RC PUMP STARTUP PROFILE Time, sec S eed,r m 0.0 3.50 240 6.60 480 9.7 720 13.3 960 15.8 1080 17.4 1189 full s eed 6.0 ANALYSIS The following sections describe the initial and boundary conditions as well as the results for each of the events analyzed. All values were taken from References 4, 6 8 7. The case numbers correspond to those shown in Table 1.

6.1 Mass Addition Cases 6.1.1 Case 1 The mass addition case identified as Case 1 is initialized at a primary temperature of 85'F and a primary pressure of 315 psig. Using the initial pressure of 315 psig assures that the transient is well defined by the time the PORV is actuated. The reactor coolant pumps are not running and the pressurizer is water solid. It is assumed that the RHR system is removing decay 18

FTl Non-Proprietary 86-1 234820-03 heat, so it is not modelled. The event is initiated by starting three pump charging flow (180 gpm or 25 Ib/s). The analysis is run for ten minutes. The sequence of events for this case is shown in Table 6. Plots of the reactor vessel pressure and pressure at RHR system suction point in the hot leg are shown on Figures 4 8 5, respectively (Reference 4).

The peak reactor vessel pressure was 480.2 psia. The allowable pressure, according to the Appendix G limit (Code Case N-514) at 85' is 618.7 psia.

Therefore, there is 138A psi margin to the Appendix G acceptance criterion.

To compare the peak pressure in the RHR system with the acceptance criterion, the pressure drop from the hot leg to the RHR pump discharge (128.1 psi, from Reference 4) was added to the peak hot leg pressure. This case yielded a peak RHR pressure of 598.4 psia. The peak allowable pressure in the RHR system is 674.7 psia. This results in a 76.3 psi margin to the acceptance criterion. The RHR flow is assumed to be 1700 gpm in this case, for the calculation of peak RHR pressure.

TABLE 6 SEQUENCE OF EVENTS- MASS ADDITION CASE WITH THREE CHARGING PUMPS, 85'F PRIMARY TEMPERATURE EVENT TIME IN SECONDS 3 Char in um s started 0.0 Char in um s reach full flow 1.0 Peak pressure of 480.2 psia reache'd 534.0 in the bottom of the reactor vessel Peak pressure of 470.3 psia reached 534.0 in the hot le connection to RHR 6.1.2 Case 2 Case 2 is a mass addition case with the primary pressure at 329.7 psia and with a primary temperature of 60 'F. One RC pump is running at steady-state in this transient. There is 3 gpm RC pump seal return flow.'he transient is initiated with starting of one charging pump. No pressurizer vent is open and no SI pump is started. This case also has the secondary system disconnected from the primary in the model as in all mass addition cases. No RHR system is modeled .

With the starting of one charging pump, the primary system pressurizes rapidly and the PORVs open to relieve the pressure. The reactor vessel reaches a peak pressure of 554.42 psia. The allowable pressure at this temperature is 608.7 psia. The peak pressure in the RHR system is calculated by adding 138.03 psi l9

FTI Non-Proprietary 86-1 23482043 to the highest pressure reached in the hot leg connection of the RHR system.

This value is based on a total of 2000 gpm RHR flow rate. The peak RHR system pressure thus calculated is 656 psia as compared with the structural allowable peak pressure of 674.70 psia.

Figures 6 8 7 show the pressure in the reactor vessel, and the pressure in the hot leg RHR connection point, respectively.

This case passes the Appendix G limit (Code Case N-514) and the RHR system

'as margin to the acceptance limit. The sequence of events is shown in Table 7.

TABLE 7

-

SEQUENCE OF EVENTS MASS ADDITION CASE WITH ONE CHARGING PUMP, 60'F PRIMARYTEMPERATURE EVENT TIME,SECS One char in um started 0.0 Char in um reaches full flow 1.0 Peak pressure of 517.97 psia reached 19.1 at RHR suction oint Peak pressure of e+.'. sia reached 19.1 in reactor vesse 'wncomer 6.1.3 Case 3 Case 3 is a mass addition case with the primary pressure and temperature at 14.7 psia and 60 'F respectively. No RC pump is running in this transient. The transient is initiated by starting one Sl pump. A pressurizer vent of 1.1 square inches is open. The primary and secondary systems are oin thermal equilibrium.

No RHR system is modeled. Instead, the pressure difference between the RHR pump discharge and the RHR system inlet was added to obtain the calculated results.

With the starting of one Sl pump, the primary system pressurizes. The primary pressure reaches a steady-state pressure at a level where the SI flow and the flow through the vent are equal. The PORVs do not have to open to relieve the pressure. The PORVs are not credited in the analysis. The reactor vessel reaches a peak pressure of 413.48 psia. The allowable pressure at this temperature is 608.7 psia. The peak pressure in the RHR systeiTr is calculated by adding 138.03 psi to the highest pressure reached in the hot leg connection of the RHR system. This value is based on a total of 2000 gpm RHR flow rate.

The peak RHR system pressure thus calculated is 542.34 psia as compared with the structural allowable peak pressure of 674.70 psia.

20

FTI Non-Proprietary 86-1 234820-03 Figures 8 8 9 show the pressure in the reactor vessel and the hot leg RHR connection point, respectively.

This case passes the Appendix G (Code Case N-514) limit for acceptance with a sizeable margin. The RHR system has margin to acceptance limit. The sequence of events is shown in Table 8.

TABLE 8 SEQUENCE OF EVENTS - MASS ADDITION CASE WITH 1.1 SQ.INCH VENT AND ONE Sl PUMP INJECTION, PRIMARY TEMP. 60'F EVENT TIME,SEC One safet in'ection um started 0.0 Safe inection um reaches fullffow 1.0 Peak pressure of 404.93 psia reached 166.00 at RHR inlet l3 48 $

Peak pressure of . sia reached 175.00 in reactor vessel 6.1.4 Case 4 Case 4 is a mass addition case with the primary pressure at 14.7 psia and with a primary temperature of 212 'F. No RC pump is running in this transient. The transient is initiated by starting one Sl pump. A pressurizer vent of 1.1 square inches area is open. This case also has the secondary system disconnected from the primary in the model. No RHR system is modeled .

Since the primary system is at atmospheric pressure at the top of the pressurizer, the steam generator top-most region inside the tubes will experience pressures lower than atmosphere and hence, steam bubbles can form in this region at 212'F. Steam voids in the system could yield non-conservative results by increasing the compressibility of the reactor coolant. To prevent void formation, the steam generator was initialized separate from the primary system and at a temperature below the saturation temperature.

The transient is initiated by connecting the steam generators to the RCS and by starting an Sl pump. With the starting of one SI pump, the primary system pressurizes until the flow out of the vent balances the flow from the Sl pump.

The peak pressure reached is below the PORV setpoint. The PORVs are not credited in this case.

The reactor vessel reaches a peak pressure of 396.72 psia. The allowable pressure at this temperature is approximately 780.3 psia. The peak pressure in the RHR system is calculated by adding 138.03 psi to the highest pressure reached in the hot leg connection of the RHR system. This value is based on a 21

FTl Non-Proprietary 86-1 23482043 total of 2000 gpm RHR flow rate. The peak RHR system pressure thus calculated is 525.91 psia as compared with the structural allowable peak pressure of 674.70 psia.

Figures 10 & 11 show the pressure in the reactor vessel, and the pressure in the hot leg RHR connection point, respectively.

The peak reactor vessel pressure is less than the Appendix G limit (Code Case N-514) and the RHR system has margin to the acceptance limit. The sequence of events is shown in Table 9.

TABLE 9 MASS ADDITION CASE- VENT OF 1.1 SQ.INCHES AREA OPEN, ONE Sl PUMP START, PRIMARYTEMPERATURE 212'F EVENT TIME,SECS One safe in'ection um started 0.0 Safe in ection um reaches full flow 1.0 Peak pressure of 387.88 psia reached 200.0 at RHR s stem suction oint Peak pressure of . sia reached 200.0 in reactI v ssel.

6.1.5 Case 2a Case 2a is a mass addition case with the primary pressure at 329.7 psia and with a primary temperature of 60 'F. Two RC pumps are running at steady-state inthistransient. There is no RC pumpsealreturnflowmodeled. Thetransient is initiated by starting three charging pumps. No pressurizer vent is open and no Sl pump is started. No RHR system is modeled .

With the starting of three charging pumps, the primary system pressurizes and the PORVs open to relieve the pressure. The reactor vessel reaches a peak pressure of 587.44 psia. The Appendix G (Code Case N-514) allowable pressure at this temperature is 608.7 psia. The peak pressure in the RHR system is calculated by adding 138.03 psi to the highest pressure reached in the hot leg connection of the RHR system. This value is based on a total of 2000 gpm RHR fiow rate. The peak RHR system pressure thus calculated is 663.49 psia as compared with the structural allowable peak pressure of 674.70 psia.

Figures 57 & 58 show the pressure in the reactor vessel, and the pressure in the hot leg RHR connection point, respectively.

'

FTI Non-Proprietary 86-1 234820-03 The peak reactor vessel pressure is less than the Appendix G limit and the RHR system also has margin to the acceptance limit. The sequence of events is shown in Table 7a.

TABLE 9a SEQUENCE OF EVENTS - MASS ADDITION CASE WITH THREE CHARGING PUMPS, 60'F PRIMARY TEMPERATURE EVENT TIME,SECS Three char in um s started 0.0 Char in um s reache full flow 1.0 Peak pressure of 525.46 psia reached 7.45 at RHR suction oint Peak pressure of 587.44 psia reached 7.45 in reactor vessel downcomer 6.2 Heat Addition Cases 6.2.1 Case 5 Case 5 is a heat addition case with the primary system initialized to 60'F and 329.7 psia. The secondary system is at a temperature 50'F higher than system. The RHR system is running at a capacity of 2000 gpm total.

the'rimary The RHR system is modeled explicitly for the heat addition cases. No pressurizer vent or seal return flow is modeled.

The transient is initiated by starting the reactor coolant pump in the loop in which the pressurizer is attached. The reactor coolant pump forces flow through the loops, thus allowing the secondary side to heat the primary side. This results in an expansion of the primary system fluid. Since the pressurizer is water-solid, the pressure rises until the PORV opens to relieve the pressure. This case is run until the PORV cycles a few times to assure that the peak pressure is declining with every cycle.

The peak pressure reached in the reactor vessel, is 551.26 psia. The allowable pressure for this temperature is 608.7 psia. Hence, this case passes the Appendix G (Code Case N-514) limit.

The peak RHR system pressure reached in this case is 650.05 psia. The allowable value for this system is 674.70 psia. Hence, the RHR system also passes the pressure acceptance criterion.

FTI Non-Proprietary 86-1 234820-03 Figures 12 through 20 show the reactor vessel pressure, RHR system pressure, the primary system temperatures in the two loops, flow rates in the two loops, the secondary system temperatures in the two loops, and the PORV flow rate. Table 10 shows the sequence of events for this case.

TABLE 10 HEAT ADDITION CASE-PRIMARY TEMPERATURE 60'F, 2000 GPM RHR, ONE RC PUMP STARTED EVENT TIME,SECS One RC um started 0.0 RC um reaches full flow 17.4 PORV o ens for the first. time 46.00 Peak pressure of 551.26 psia reached 46.00 in the reactor vessel Peak pressure of 650.05 psia reached 46.00 inthe RHRs stem 6.2.2 Case 6 Case 6 is a heat addition case with the primary system initialized to 85'F and 329.7 psia. The secondary system is at a temperature 50'F higher than the primary system. The RHR system is running at a capacity of 2000 gpm total.

The RHR system is modeled explicitly for the heat addition cases. No pressurizer vent or seal leakage is modeled.

The transient is initiated by starting the reactor coolant pump in the loop in which the pressurizer is attached. The reactor coolant pump forces flow through the loops, thus allowing the secondary side to heat the primary side. This results in an expansion of the primary system fluid. Since the pressurizer is water-solid, the pressure rises until the PORV opens to relieve the pressure. This case is run until the PORV cycles a few times to assure that the peak pressure is declining with every cycle.

peak pressure reached in the reactor vessel is 558.04 psia. The Appendix I'he G (Code Case N-514) allowable for this temperature is 618.6 psia. Hence, this case passes the Appendix G limit.

The peak RHR system pressure reached in this case is 656.34 psia. The allowable value for this system is 674.70 psia. Hence, the RHR system also passes the pressure acceptance criterion.

Figures 21 through 29 show the reactor vessel pressure, RHR system pressure, the primary system temperatures in the two loops, flow rates in the two loops, 24

FTI Non-Proprietary 86-12348204I3 and the secondary system temperatures in the two loops. Table 11 shows the sequence of events for this case.

TABLE 11 HEAT ADDITION CASE- PRIMARY TEMPERATURE 85'F, 2000 GPM RHR, ONE RC PUMP STARTED EVENT TIME,SECS One RC um started 0.0 RC um reaches full flow 17.4 PORV o ens for the first time 22.5 Peak pressure of 558.04 psia reached 22.5 in the reactor vessel Peak pressure of 656.34 psia reached 22.5 in the RHR s stem 6.2.3 Case 7 Case 7 is a heat addition case with the primary system initialized at 280'F and 329.7 psia. The secondary system is at a temperature 50'F higher than the primary system. The RHR system is running at a capacity of 2000 gpm total.

The RHR system is modeled explicitly for the heat addition cases. No pressurizer vent or seal leakage is modeled.

The transient is initiated by starting the reactor coolant pump in the loop in which the pressurizer is attached. The reactor coolant pump forces flow through the loops, thus allowing the secondary side to heatup the primary side. This results in an expansion of the primary system fluid. Since the pressurizer is water-solid, the pressure rises until the PORV opens to relieve the pressure. This case is run until the PORV cycles a few times to assure that the peak pressure is declining with every cycle.

The peak pressure reached in the reactor vessel is 569.33 psia. The allowable pressure for this temperature is 1116.9 psia. Hence, this case passes the Appendix G (Code Case N-514) limit.

The peak RHR system pressure reached in this case is 663.66 psia. The allowable value for this system is 674.70 psia. Hence, the RHR system also passes the pressure acceptance criterion.

Figures 30 through 38 show the reactor vessel pressure, RHR system pressure, the primary system temperatures in the two loops, flow rates in the two loops, the secondary system temperatures in the two loops and the PORV flow rate.

Table 12 shows the sequence of events for this case.

25

'A FTI Non-Proprietary 86-1 23482043 TABLE 12 HEAT ADDITION CASE-PRIMARY TEMPERATURE 280'F, 2000 GPM RHR FLOW, ONE RC PUMP STARTED EVENT TIME, SECS One RV um started 0.0 PORV o ens for the first time 10.0 RC um reaches full flow 17.4 Peak pressure of 663.66 psia reached in 46.00 the RHR s stem Peak pressure of 569.33 psia reached in 46.00 the reactor vessel 6.2.4 Case 8 Case 8 is a heat addition case with the primary system initialized to 85'F and 329.7 psia. The secondary system is at a temperature 50'F higher than the primary system. The RHR system is running at a capacity of 1700 gpm total.

The RHR system is modeled explicitly for the heat addition cases. No pressurizer vent or seal return is modeled.

The transient is initiated by starting the reactor coolant pump in the loop in which the pressurizer is attached. The reactor coolant pump forces flow through the loops, thus allowing the secondary side to heat the primary side. This results in an expansion of the primary system fluid. Since the pressurizer is water-solid, the pressure rises until the PORV opens to relieve the pressure. This case is run until the PORV cycles a few times to assure that the peak pressure is declining with every cycle.

The peak pressure reached in the reactor vessel is 546.79 psia. The Appendix G(Code Case N-514) allowable for this temperature is 618.6 psia. Hence, this case passes the Appendix G limit.

The peak RHR system pressure reached in this case is 640.78 psia. The allowable value for this system is 674.70 psia. Hence, the RHR system also passes the pressure acceptance criterion.

Figures 39 through 47 show the reactor vessel pressure, RHR system pressure, the primary system temperatures in the two loops, flow rates in the two loops, the secondary system temperatures in the two loops and the PORV flow rate.

Table 13 shows the sequence of events for this case.

26

e FTI Non-Proprietary 86-123482043 TABLE 13 HEAT ADDITION CASE- PRIMARY TEMPERATURE 86'F, RHR FLOW AT 1700 GPM, ONE RC PUMP STARTED EVENT TIME,SECS One RC um started 0.0 RC um reaches full flow 17.4 PORVo ens first time 23.2 Peak RV ressure of 546.79 sia reached 23.2 Peak RHR pressure of 640.78 psia 23.2 reached 6.2.5 Case 9 Case 9 is a heat addition case with the primary system initialized to 320'F and 329.7 psia. The secondary system is at a temperature 50'F higher than the primary system. The RHR system is running at a capacity of 1700 gpm total ~

The RHR system is modeled explicitly for the heat addition cases. No pressurizer vent or seal leakage is modeled.

The transient is initiated by starting the reactor coolant pump in the loop in which the pressurizer is attached. The reactor coolant pump forces flow through the loops, thus allowing the secondary side to heat the primary side. This results in an expansion of the primary system fluid. Since the pressurizer is water-solid, the pressure rises until the PORV opens to relieve the pressure. This case is run until the PORV cycles a few times to assure that the peak pressure is declining with every cycle.

E The peak pressure reached in the reactor vessel is 563.83 psia. The allowable pressure for this temperature is 1529 4 psia. Hence, this case passes the Appendix G (Code Case N-514) limit.

The peak RHR system pressure reached in this case is 655.66 psia. The allowable value for this system is 674.70 psia. Hence, the RHR system also passes the pressure acceptance criterion.

Figures 48 through 56 show the reactor vessel pressure, RHR system pressure, the primary system temperatures in the two loops, flow rates in the two loops, the secondary system temperatures in the two loops and the PORV flow rate.

Table 14 shows the sequence of events for this case.

27

FTl Non-Proprietary 86-1 23482043 TA8LE 14 HEAT ADDITION CASE - PRIMARY TEMPERATURE 320'F,RHR 1700 GPM FLOW RATE, ONE RC PUMP STARTED EVENT TIME,SECS One RC um started 0.0 PORVo ens first time 8.81 RC um reaches full flow 17.4 Peak pressure in RHR system of 655.66 10.5 sia reached Peak pressure of 563.82 psia reached in 21.3 the RV 7.0

SUMMARY

AND CONCLUSIONS Framatome Technologies Incorporated (FTI) updated the analysis of the low temperature overpressure events for the Rochester Gas and Electric (RGE)

Robert E.Ginna Nuclear Power Station. This analysis becomes the new analysis of record for RGE. In this effort, a spectrum of LTOP events to bound all possible operational configurations was analyzed and the results compared to the acceptance criteria of the Appendix G limits for embrittlement and the RHR overpressure structural design limit.

The most limiting mass addition case analyzed is a case with three charging pumps turned on when the primary system is at 60'F with two RC pumps running. This resulted in a peak pressure in the reactor vessel of 587.44 psia, which is lower than the Appendix G(Code Case N-514) limit at this temperature.

The peak pressure in the RHR system in this case with 2000 gpm of RHR flow(

i.e. two RHR pumps running ) is 663.5 psia. The RHR system passes the structural acceptance criterion set for the RHR system by a margin of 11.2 psi.

The most limiting heat addition case is the start of a reactor coolant pump with the primary system at 60 'F. The peak reactor vessel pressure reached in tljy transient was 551.25 psia. The Appendix G(Code Case N-514) limit is 608g7 psia. Hence, this case passes with a margin of 57.@$ si. The peak pressure at the RHR pump discharge for this case was 649.96 psia as compared with an acceptance limit of 674.7 psia. The margin in the RHR system is 24.74 psi.

For the RHR system, the limiting event is a reactor coolant pump start with both the RHR pumps running and the primary initial temperature at 280'F. In this case, the peak RHR pressure reached is 663.66 psia as compared with an allowable of 674.70 psia. Above 280'F primary temperature, only one RHR pump will be running, yielding a greater margin to the pressure limit.

FTI Non-Proprietary 86-123482043 When the plant is in a configuration in which the pressurizer vent(1.1 sq.inches) is open, the primary system pressure will be at atmospheric pressure in the pressurizer. No RC pump will be allowed to run under vented conditions since NPSH will not be available to run any pump. The most limiting mass addition for this plant condition is the start of an Sl pump when the initial primary temperature is at 60'F. This case has y pegreactor vessel pressure of ~'$sia, which is less than the Appendix GfimiFby, psi. The peak RHR ressure in this case is .

" sia as compared wi 'ie allowable presssure of 674.70 psia.

Conseq6ent, this case bounded by start of a charging pump at 60'F with the pressurizer vent closed and PORV operable.

The summary of results of all LTOP cases is shown in Table 15.

I Non-Proprietary 23482043 TABLE 15

SUMMARY

OF RESULTS RESULTS OF THE MASS ADDITION CASES Case ID Description Peak pressure Allowable per Margin Peak press. Structural Margin in reactor Appendix G, in psi in RHR allowable in psi vessel,psia Code Case'-514 system in psia in psia in psia Case 1 85 F, three charging pumps started, no RC pump running, primary pressure 329.7 psia No RC pump seal return flow 1700 gpm RHR 480.19 618.6 138.41 598.43 674.70 76.27 Case 2 60'F, one charging pump started, one RC pump running, primary pressure 329.7 psia 3 gpm RC pump seal return flow =

2000 gpm RHR 554.42 608.7 54.28 656.08 674.70 18.62 (continued) 30

i Non-Proprietary 23482043 TABLE 15(continued)

RESULTS OF THE MASS ADDITION CASES Case ID Description Peak pressure Allowable per Margin . Peak press. Structural Margin in reactor Appendix G, in psi in RHR allowable ln psl vessel,psia Code Case system in psia N-514 in psia in psia Case 3 60'F, 14.7 psia primary pressure 1.1 sq.inch vent open, one Sl pump on, no RCpumps on.

I 2000 gpm RHR 413.48 608.7 195.22 542.34 674.70 132.36 Case 4 212'F primary,no RC pumps, 14.7 psia initial primary pressure, one Sl pump turned on.

I 2000 gpm RHR 398.72 -=780.3 383.58 525.91 674.70 148.79 Case 2a 60'F primary, two RC pumps, 329.7 psia initial pressure three charging pumps turned on.

)

2000 gpm RHR 587.44 608.7 21.26 663.49 674.70 11.21 Note: The RHR peak pressure is calculated by adding to the peak pressure at hot leg a value of 138.03 psi, which is the pressure drop between node 100 and node 455 in the 85'F heat addition case, Case 6.

(continued)

Tl Non-Proprietary 234820-03 TABLE 15(continued)

RESULTS OF HEAT ADDITION CASES Case ID Description Peak pressure Allowable per Margin Peak press. Structural Margin in reactor Appendix G in psi in RHR allowable in psi vessel,psia in psia =-

system in psia in psia Case 5 60'F primary, 2000 gpm RHR, one RC pump started.

Primary pressure 329.7 psia 551.25 608.7 57.45 649.96 674.70 24.74 Case 6 85'F primary,2000 gpm RHR, one RC pump started.

Primary pressure 329.7 psia 558.04 618.6 60.56 656.34 674.70 18.36 Case 7 280'F primary, 2000 gpm RHR, one RC pump started Primary pressure 329.7 psia 569.33 1116.9 ,547.57 663.66 674.70 11.04 Case 8 85'F primary, 1700 gpm RHR, one RC pump started Primary pressure 329.7 psia 546.79 618.6 71.81 640.78 674.70 33.92 32

I Non-Proprietary 234820-03 TABLE 15(continued)

RESULTS OF HEAT ADDITION CASES Case ID Description Peak pressure Allowable per Margin Peak press. Structural Margin in reactor . Appendix G in psi in RHR allowable in psi vessel,psia in psia system in psia in psia Case 9 320.0'F primary, 1700 gpm RHR, one RC pump started Primary pressure 329.7 psia 563.82 1529.4 965.58 655.66 674.70 19.04 Note: Appendix G allowables shown here are from Table 2. Reference 4 had an earlier Appendix G curve from the UFSAR of Ginna plant a'nd the values were slightly different..

32a

FTI Non-Proprietary 86-1 234820-03

8.0 REFERENCES

1. U.S.Nuclear Regulatory Commission Regulatory Guide 1.99, "Embrittlement of Reactor Vessel Materials", Revision 2, May 1988.

, 2. WCAP-14684, "R.E.Ginna Heatup and Cooldown Limit Curves for Normal Operation," June 1996.

3." NUREG/CR-5194 EGG-2531 R4,"RELAP5/MOD2 Models and Correlations", August 1988.

4. FTI Document 32-1232650-00, "Low Temperature Overpressure Analysis for RGE - Ginna Plant" February 1995.

5. BAW-10164P-A, "RELAP5/MOD2-B&W-An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis," Code Topical Report, Revision 3, July 1996.

6. FTI Doc. 32-1266167-00, "Additional LTOP Heat Addition Cases", June 1997.

7. FTI Doc. 32-1266168-00, "Ginna LTOP Mass.Add.", June 1997.

32b

FTI Non-Proprietary 86-123482043 PLOTS OF THE RESULTS I

33

FIGURE 4 CASE 1 MASS ADDITION CASE PRIMARY TEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA 3CHARGING PUMPS NO RC PUMP RUNNING NO SEAL LEAKAGE n

Z,'

4S0 -

C4 O 0 U

0 CO 400 350 300 j

II I

I 200 0 80 160 240 320 480 TIME IN SECONDS

FIGURE 5 CASE 1 MASS ADDITION CASE PRIMARY TEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA 3 CHARGING PUMPS NO RC PUMP RUNNING NO SEAL LEAKAGE ll O

O 450 Q P9 0

0 0 "-

350 300-00 t

25 0 fV Po 200 CD

<<0 $0 160 240 320 480 t CD TIME IN SECONDS

FIGURE 6 MASS ADDITION CASE PRIMARY TEMPERATURF 60'F PRIMARY PRESSURE 329.7 PSIA 1 CHARGING PUMP ONE RC PUMP RUNNING 3 GPM SEAL LEAKAGE 560 Tl 0

a 520 O I0 5

480 440 400 CO 360 320 0 10 20 30 40 50 60 20 PJ TIME IN SECONDS C) 1 C)

FIGURE 36 CASE 7 HEAT ADDITION CASE PRIMARY TEMPERATURE 280'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR 332 r1 P O D

G U 328 O u

CO U

~I 324 320 316 zO 312 O

30S 10 20 30 50 Transient time in secs

FIGURE 37 CASE 7 HEAT ADDITION CASE PRIMARY TEMPERATURE 280'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED

'000 GPM RHR 332 rl 0

O 32$ a 324 320 316 312 30S 0 IO 20 30 50 Transient time in secs

FIGURE 38 CASE 7 HEAT ADDITION CASE PRIMARY TEMPERATURE 280'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR 150 11 O

0 U

(D 9)

~I 100 O

tel 75 U

0 so 10 20 30 50 Transient time in secs

FIGURE 39 CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85oF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 'Tl 560 0

O 520 U (D

Gl 0 480 0

z 440 400 360 320 0 10 15 20 25 30 35 TIME IN SECONDS

FIGU CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85'F PRIMARY PRESSURE 329.7 PS)A NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 680 ll z

O 640 0 U

(D Gl 6oo Oc 8

560

.g 520 C4 4SO Co I

PU 440 10 15 20 25 30 35 CO TIME IN SECONDS Pv tD I

CD 44

FIGURE 41 CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85oF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR xl0 20 ll O

D 16 O

O CD Dl 12 S

4 CD 0

I fu 10 15 20 30 35 40 CD TIME IN SECONDS I

C)

V4

FIGURE CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85oP PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR n

O D

O U

(D CA

~1 C4 -800 0

0 0 -1200 R

> -It'00

-20M

-2400 10 20 .30 35 TIME IN SECONDS

FIGURE 43 CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85oP PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 110 105 A

0 O

100 95 90 O 8S g

80 0 10 IS 20 30 3S TIME IN SECONDS

FIGURE 44 CASE 8 <EAT ADDITION CASE 'PRIMARY TEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 140 130

~ I 0

0 l20 g

O IIO I I

100 0

80 0 10 20 30 35 40 TIME IN SECONDS

FIGURE 45 CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85oF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 136 132 A

12S

.9 C4 8

124.

EI 120 CQ Q

O O

CQ 116 112 10 15 20 35 40 TIME IN SECONDS

e FIGUR CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURF 85'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR ll 140 O

O bQ U 136 a CD C4 CD O

O 132 8

A C4 8

128 8

124 CO 00 aO O

120 I CQ 00 116 10 15 20 30 3$

C)

TIME IN SECONDS I C)

FIGUR CASE 8 HEAT ADDITION CASE PRIMARY TEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA NO VENT; NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR "rl 120 O

I I

Il l

l aO 0

(D fD 80 60 40 20 10 15 20 25 30 35 TIME IN SECONDS

FIG 48 CASE 9 HEAT ADDITIONCASE PRIMARY TEMPERATURE 320'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED

'I 1700 GPM RHR n

0

~ \

550 0 O

CD 0 500 O

O 450

~

g 4M Q 350 300 0 10 20 30 35 40 TIME IN SECONDS

0 0

FIGU CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 320 F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR Tl 0

0 O

(0 fD O 600 C4 Sso

.9 soo 450 lo 20 30 3$

TIME IN SECONDS

FIGURE 50 CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 320OP PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARG1NG PUMP ONE RC PUMP STARTED 1700 GPM RHR 350 Q 345 A

0 0

340 U

335 330 O 325 320 IO 20 3S 40 TIME IN SECONDS

RE 51 CASE 9 HEAT ADDITIONCASE PRIMARY TEMPERATURF 32QoF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 368 rl

'z O

360.

0 U

CD Q

0 352 D

R 344 336 CO 328 O fV CO Pv 320 CO 0 10 15 20 30 35 40 I

TIME IN SECONDS C)

FIG 2 CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 320oF PRIMARY PRESSURE 32S.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR x10 I 0

n O

0U 16 CD fD 12 8

4 0 1 CO 10 20 30 40 Pu CD TIME IN SECONDS I CD

FIG 53 CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 320oF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 400 Pl l4 -800 0

0 Q -1200

>

~-iae

-2000

-2400 10 20 30 35 TIME IN SECONDS

FIGURE 54-CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 32POF PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 37$

370 DD A

A 365

~ g C4 8

360

%4 EJ 355 Gg a

O CJ CII 350 10 15 20 30 40 TIME IN SECONDS

FIGURE 55 CASE 9 HEAT ADDITIONCASE PRIMARY TEMPERATURE 320'F PRIMARY PRESSURE 329.? PSIA NO VENT, NO SI, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 372 Tl O

bO

<0 36$ O

'O 0 f4 O CD O

c4

~ I 364 8

.8 360 8

356 CO 4

O i 352 fV 44 CO 34S bd 10 l5 20 30 C) l TIME IN SECONDS C) i@4

FIGURE CASE 9 HEAT ADDITION CASE PRIMARY TEMPERATURE 3200F PRIMARY PRESSURE 329 7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 150 n 0

0 0

U 100 0

50 10 15 20 25 30 35 TIME IN SECONDS

FIGURE 57 CASE 2a MASS ADDITION CASE PRIMARY TEMPERATURE 60'F PRIMARY PRESSURE 329.7 PSIA 3CHARGING PUMPS TWO RC PUMP RUNNING 550 500 I

l j 450 400 350 300 0 10 20 30 40 50 60 70 80 TIME IN SECONDS

FIGURE 58 CASE 2a MASS ADDITION CASE PRIMARY TEMPERATURF 6Q P PRIMARY PRESSURE 329.7 PSIA 3CHARGING PUMPS TWO RC PUMP RUNNING 550 n O

!

6.

O

'U 500 ~

CD Gl I

0 0 450 K 400 350 i

250 0 10 20 30 40 50 60 70 80 TIME IN SECONDS

Attachment VIII W CAP-14684 (First use of P/T limit methodology, No change from that provided in April 24, 1997 RG&E letter to NRC.)