ML17309A615
| ML17309A615 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/03/1997 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17264A925 | List: |
| References | |
| NUDOCS 9706240150 | |
| Download: ML17309A615 (120) | |
Text
CATEGORY j.
REGULATOIINPORNAT1ON DISTRIBUTION TEN (RIDE)
ACCESSION NBR:9706240150 DOC.DATE: 97/06/03 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH,NAME AUTHOR AFFILIATION
.MECREDY,R.C.
Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
DOCKET 05000244
SUBJECT:
Provides clarification to license amend Low Temp Overpressure Protection (LTOP)
LTOP analyses, encl.
DISTRIBUTION CODE:
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TITLE: OR Submittal: General Distribution request re proposed TS.Calculation re ENCL i
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NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 RECIPIENT ID CODE/NAME PD1-1 LA VISSING,G.
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4ND I
ROCHESTER GASANDELECTRIC CORPORATION
~ 89 FASTAYEIVLIE,ROCHESTER, N. Y Idio-0001 ARFA CODE716 546-2700 ROBERT C. MECREDY Vice President htvcleor Operotions June 3,
1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Clarifications to Proposed Low Temperature Overpressure Protection (LTOP) Technical Specification R.E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
(a)
Letter from R.C.
- Mecredy, RG&E, to G.S.
- Vissing, NRC,
Subject:
<<Revision to RCS Pressure and Temperature Limits Report (PTLR)
Administrative Controls Requirements,"
dated April 24, 1997.
Dear Mr. Vissing:
The purpose of this letter is to clarify several issues related to the previously submitted license amendment request (LAR) concerning LTOP.
Specifically, the following clarifications are provided:
a 0 b.
c ~
The specific use of ASME Code Case N-514 in the LTOP methodology is to calculate LTOP enable temperature only; we do not intend to use Code Case N-514 to increase the maximum pressure in the reactor vessel to 110> of Appendix G limits.
A clarification to the methodology stating this is attached.
A clarification to the methodology of determining minimum boltup temperature is proposed.
Using 10 CFR 50, Appendix G
as the basis for minimum boltup temperature results in a
reference temperature value of -52 F.
RG&E's use of 60 Fr as suggested in WCAP-14040-NP-A, provides significant margin to account for instrument uncertainty with respect to the Appendix G limit.
Based on questions received with respect to the previously submitted LTOP analysis, a set of responses is being provided for NRC review (Enclosure 3).
The results of our revised analyses are provided in Enclosure 4.
9706240i50 970bOS PDR ADOCK 05000244 P
~4005'IIIIIIIIIIIIIIIIIIIII/IIIIIIII/IIIIIII Based on these clarifications, several attachments to the April 24th LAR are being updated.
These are listed in Enclosure 1 to this letter.
- First, the Technical Specifications contained in Attachments II and III are revised to reference this document for the methodology and first use of the methodology for LTOP calculations.
- Second, Section 5.0 of the PTLR (Attachment IV) is updated for the same reasons.
- Finally, a revised Section 3.3 of the methodology (Attachments V and VI) is provided.
These revised pages should be substituted for the ones submitted in the April 24 LAR.
Very truly yours,
'Nd ~
Robert C. Meoredy Enclosures GJW/462 xc:
Mr. Guy Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentino Corporate Plaza West 286 Washington Ave. Extension
- Albany, NY 12203-6399
Enclosure 1 to June 3, 1997 Letter Replacement Pages for April 24, 1997 LAR 1.
'Attachment II page 5.0-22 2 ~
3.
4 ~
5.
Attachment III page 5.0-22 Attachment IV pages 3 and 5
Attachment V pages 3-8 and 3-9 Attachment VI page 3-7
FTI Non-Proprietary 86-1 234820-01
~ 9706240i50 LOW TEMPERATURE OYERPRESSURE ANALYSES
SUMMARY
REPORT Prepared for Rochester Gas 8 Electric Corporation Prepared by:
Reviewed by:
Approved by:
N.Vasudevan, Principal Engineer 8
Date:
> /> t'7 M.V.Parece, Senior Supervisory Engineer Date: 6'> P7 J.J.
udlin, Manager, Analysis Services Unit FRAMATOMETECHNOLOGIES INC.,
LYNCHBURG, VA.
FTI Non-Proprietary 86-1234820-01 RECORD OF REVISIONS REVISION NO.
DESCRIPTION DATE 00 01 Original issue Complete revision to integrate additional runs and conclusions based on the additional runs
-all pages revised March 1995 June 1997
FTI Non-Proprietary 86-1234820-01 0
TABLEOF CONTENTS
1.0 INTRODUCTION
2.0 DISCUSSION OF LTOP EVENTS 2.1 LTOP EVENTS INITIATEDBY MASS ADDITION.
2.2 LTOP EVENTS INITIATEDBY HEATADDITION 3.0 EVENTS ANALYZED 4.0 ACCEPTANCE CRITERIA 5.0 METHODOLOGY.
6.0 ANALYSIS 6.1 MASS ADDITIONCASES 6.2 HEATADDITIONCASES 7.0
SUMMARY
AND CONCLUSIONS
8.0 REFERENCES
PLOTS OF THE RESULTS
.5
... 5
.... 6 18
..... 1 8 23
... 32b
.33
0
FTI Non-Proprietary 86-1 234820-01
1.0 INTRODUCTION
Framatorne Technologies Inc. (FTI) (formerly BBW Nuclear Technologies) updated the analysis of the low temperature 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. The results of the analyses of the limiting LTOP events were compared with 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 gives 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, ifthe charging pumps or ifthe safety injection(SI) pumps are started inadvertently.
Technical Specification 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 SpeciTication limits, an inadvertent Sl signal will not cause an Sl pump start.
Since the
f'.g 1
~q~
e
FTI Non-Proprietary 86-'i234820-Ot 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. With operational limits on starting the charging pumps, with an RC pump running, one charging pump startup can cause a mass addition event and this event is analyzed to show that the Appendix G limits are not violated. This is the most limiting mass addition case for Appendix G criterion.
Operating procedural limits on RC pumps will prevent the running of two pumps at primary temperatures lower than 135'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 Appendix G limitat 135'F, to show acceptability.
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 lNlTIATEDBY HEAT ADDlTION 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 willcause a slow rise in the water temperature and increase in pressure, ifthe 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. Ifthe operator does not terminate the transient, 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
FTI Non-Proprietary time to mitigate the event.
86-1 234820-01 The first type of temperature asymmetry can occur ifthe 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 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 willflow 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 s'econdary 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. Ifone RC pump is inadvertently started under these conditions, the RCS fiowrate 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 tge 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 one charging pump, was analyzed at a primary temperature of 60'F with one RC.pump operating
. The inadvertent startup of three charging pumps, was analyzed at 85' with no RC pump operating.
FTI Non-Proprietary 86-1234820-01 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 limitof 212'F is based on saturation temperature at atmospheric conditions.
Sixty degrees is the lower limitof the Appendix G curves.
To show that at 135'F the Appendix G limitis not violated, with two RC pumps operating and with three charging pumps started inadvertently, a case with this configuration but at a lower temperature of 60'F is run and the results compared with 135'F allowable limit.
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 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 limitof the Appendix G limits and has the lowest pressure limitfor 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. Ifthe 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:
The pressure and temperature of the reactor vessel can not exceed the the steady-state Appendix G limits, which are depicted in Table 2. This table is obtained from Reference 2.
The pressure in the RHR system can not exceed 110 percent of the design pressure of 600 psig, or 660 psig.
FTI Non-Proprietary 6-1234820-01 TABLE 1 LIST OF CASES Case no.
Description Primary RHR floe 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 Mass addition case Primary Press.
329.7 psia 2.
Mass addition case Primary Press.
329.7 psia.
3 gpm RC pump seal return 2a. Mass addition case Primary pressure 329.7.psia 3.
Mass addition case Primary pressure 14.7 psia.
No seal return.
4.
Mass addition case Primary pressure 14.7 psia.
No seal return.
85.0 1700.00 60.0 2000.00 60.0 2000.00 60.0 2000.00 212.0 2000.0 n/a n/a n/a n/a n/a
( continued) 0 closed closed closed open open
e
FTI Non-Proprietary
-1234820-01 TABLE1(continued)
LIST OF CASES Case no.
Description Primary RHR ftow RG 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 Primary pressure 329.7 psia No seal return.
- 6. Heat addition case Primary pressure 329.7 psia No seal return.
- 7. Heat addition case Primary pressure 329.7 psia.
- 8. Heat addition case Primary pressure 329.7 psia.
- 9. Heat addition case Primary pressure 329.7 psia.
60.0 2000.0 85.0 2000.0 280.0 2000.0 85.0 1700.0 320.0 1700.0 110.0 135.0 330.0 135.0 370.0
.0'losed closed closed closed closed 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 b,P to the suction pressure at the hot leg.
Case 2a peak RV pressure is compared with allowable Appendix G limitat 135'F.
10
FTI Non-Proprietary 86-'l 234820-Q't "TABLE2 R.E.Ginna 24 EFPY Cooldown Curve Data Points Caoldo Steady S T
60 65 70 75 80 85 90 95 100 105 110 115 120 125 L30 135 140 14$
150 15$
160 165 170 175 180 185 190 195 200 205 210 215 220 225 230 235 240 245 250 25$
Z60 26$
Z70 275 280 285 290 295 300 305 310 315 320 325 330 335 340 345 350 355 360 365 370 375 wn Curves tate P
540 542 544 545 54?
549 SSI 5$4 556 5$9 562 56$
S68 572 576 580 584 589
$94 599 605 612 619 626 634
'42 652 661 672 683 696 709 723 738
'754 772 791
&II 833 856
&81 908 937 968 1002 1038 1077 1118 1163 1211 1262 1318 1377 1440 1509 1581 1660 1744 1 &34 1931 2034 2144 2262 2388 20F T
60 65 70 75 80 85 90 95 100 105 I IO I I 5 120 125 130 L35 140 145 150 155 160 16$
170 17$
180 185 190 19$
200 205 210 215 220 225 230 235 240 245 250 25$
260 265 270 275 280 285 290 295 300 305 P
SIS 516 518 519 521 523 525 528
$30 533 536 539
$42 546 550 554 558 563 568 574 5&0 5&7 594 601 609 618 628 638 649 661 673 687 701 717 734 752 772 793 816 840 866 895 92$
957 993 1030 1070 1114 1160 1211 40FT 60 65 70 75 80 85 90 95 100 105 110 IIS L20 125 130 135 140 145 150 ISS 160 165 170 L75 180 185 190 19$
200 205 210 215 220 225 230 235 Z40 245 250 255 260 265 270 275 280 285 290 295 300 P
489 490 492 493 495 497 499 501 506 509 512 516 519 523 528 532 537 542 54&
554 561 568
$76 585 594 603 614 625 637 651 665
'680 696 714 733 753 775 799 825 852 881 913 947 983 1023 1065 1110 1159 60F T
60 65 ~
70 75 80 85 90 "95 100 105.
L IO 115 L20 125 130 135 140 145 150 155 160 165 170 175 1 80 185 190 195 200 205 210 215 220 225 230 23$
240 245.
250 255
- 260, 265 270 275 280 285 290 295 300
'P 462 463 465 466 468 470 472 474 477 480 483 486 489 493 497
'01 506 511 516 522 529 536 S43 551 560 569 579 590 602 615 628 643 659 676 694 714 73$
758 783 809 838 869 902 937 975 1016 1061 1108 1159 lOOF T
60 65
'70
'75 80 85 90 95 100 LOS IIO 115 120 125 130 135 140 145 150 155 160 165 170 175 1 80 1 85 190 195 200 205 210 215 220 225 230 235 240 245 250 2$5 260 265 270 275 280 P
408 409 410 412 414 415 418 420 422 425 428 431 435 438 442 447 452 4$7 463 469 476 4&3 491 500 509 519 530 542 554 568 583
$99 616 634 654 676 699
'724 751 780 811 84$
881 920 285 1007 290 1056 295 1108
GlNNA RELAPG MODEL FIGURE 1 STEAM VtIE MSSv MSIV 9Ã 955 900 965 970 97$
900 978 891 MSSV STEAMVNE MSIV 890 880 875 870 86$
80) 855850 87a 7I z0 0U CJ To this model, added
- 1. RHR model
- 2. PORV model
- 3. Charging pump model Hoto that AFWand MFWmodeh aro deleted, hero for tho LTOPS 73348 73345 7334I 73343 73342 7334 I
.10 11
-12
.13 14
~15 18 47
. 48 l2541 73348 73345 738M 7XHQ 73342 73341 4IQOI 63348 6334$
63304 63%0 N302 63341 2254'I 10 11 12 13 l4 15
-18 83348 6334$
63$OI 63343 CQO2 63341 121 130 120 BIO 135 115
'113 110 10$
100 Im RC Pump B LEFT LOOP l~
1$8 165 170 17S 180 REACTOR VESSEL 220 230 200 295210 213 215 23$
RC 2ce Pump A RIGHT LOOP CO OI C4 CO C) 1$0 155
hot teg nozzle 364 360 loakago path hot teg nozzle FlGURE 2 GINNAREACTOR VESSEL AND CORE MODEL rl O
0
'U Ol 350 C)
C)
C9 uppor plenum 354 302 352 uppor plonum 368 326 338 cold leg nozzle 324 336 334 cold leg nozzle 320 318 316 332 330 328 CQ Cb M
CJ CO C) 312 375 Nato: Thh Is atwocorsctmnnol modol. heh svsraga cone 310 380
FlGURE 3 Primary Loop (LTOP Active Loop)
Hot Leg RHR SYSTEM MODEL Primary (Inactive Loop)
Cold Leg Tl 2:
O 0
100 280 450 453 RHR pump B 462 Heat exchanger B 463 469 sink RHR Relief Valve 468 473 472 461 460 457 452 454 RHR pump A 455 Heat exchanger A 475 456 CO.
CO h)
CO IV ID
FTI Non-Proprietary 86-1 23482041 5.0 METHODOLOGY The LTOP transient analyses were performed using the RELAP5/MOD2-B&W Version 20 (Reference 5) computer code, which has received full certification at Framatome Technologies Incorporated(FTI). RELAP5/MOD2 BBW 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-BBWhas special process models that are not available in the industry 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).
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 II5
FTI Non-Proprietary 86-1 234820-01 assumed to fail closed. The PORV was set to liftwhen 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'odel 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, & 212
'F, and at a pressure of 315.
At less than 135'F, running of both the RC pumps is prohibited by operating procedures. 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. To show that above 135'F, with two RC pumps operating and with mass addition due to three charging pumps, one case was run with this scenario but at a lower temperature of 60'F. The peak pressures at lower temperature willbe higher. in the mass addition case and hence, the results from this run were compared with the allowable Appendix G limitat 135'F to prove that it was acceptable.
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 i'6
FTI Non-Proprietary 86-1234820-01 with the acceptance criteria. Different cases have different assumptions.
See Table 1 for details.
TABLE 3 Cversus position Copes Vulcan Valve - Model Number D-100-160 Stroke 'le 0.0 1.9 7.9 14.0 20.0 26.1 32.2 38.2 44.3 50.3 62.5 68.5 73.6 78.3 84.5 91.6 98.6 100.00 C normalized 0.0 0.016 0.067 0.143 0.231 0.346 0.474 0.626 0.734 0.823 0.878 0.924 0.957 0.970 0.977 0.985 0.992 0.999 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
(a FTl Non-Proprietary 86-1 234820-01 criteria.
TABLE4 FLOW VERSUS RCS PRESSURE FOR ONE Sl PUMP AT THE R.E.GINNA STATION RCS Pressure, si 600 500 400 300 200 100 Sl Flow, m
413 440 466 490 514 536 558 TABLE5 RC PUMP STARTUP PROFILE Time, sec 0.0 3.50 6.60 9.7 13.3 15.8 S eed,r m
240 480 720 960 1080 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.
Allvalues were taken from References 4, 6 8 7. The case numbers correspond to those shown in Table 1.
6.1 6.1.1 Mass Addition Cases 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
FTI Non-Proprietary 86-1234820-01 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 limitat 85' is 540 psig or 554.7 psia.
Therefore, there is 74.5 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.
TABLE6 SEQUENCE OF EVENTS-MASS ADDITIONCASE WITH THREE CHARGING PUMPS, 85'F PRIMARYTEMPERATURE EVENT 3 Char in um s started Char in um s reach full flow Peak pressure of 480.2 psia reached in the bottom of the reactor vessel Peak pressure of 470.3 psia reached in the hot le connection to RHR TIME IN SECONDS 0.0 1.0 534.0 534.0 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. The transient is initiated with starting of one charging pump.
No pressurizer vent is open and no Sl 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 554.32 psia.
The Appendix G allowable pressure at this temperature is 554.70 psia. The peak pressure in the RHR system is calculated by adding
FTI Non-Proprietary 86-1 234820-0't 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 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 limitand the RHR system has margin to the acceptance limit. The sequence of events is shown in Table 7.
TABLE 7 SEQUENCE OF EVENTS - MASS ADDITIONCASE WITH ONE CHARGING PUMP, 60'F PRIMARYTEMPERATURE EVENT One char in um started Char in um reaches. full flow
- Peak pressure of 517.97 psia reached at RHR suction oint Peak pressure of 554.32 psia reached in reactor vessel downcomer TIME,SECS 0.0 1.0 19.1 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 Sl flow and the flow through the vent are equal.
The PORVs do not have to open to relieve the pressu're.
The PORVs are not credited in the analysis.
The reactor vessel reaches a peak pressure of 414.82 psia. The Appendix G allowable pressure at this temperature is 554.70 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 flow rate.
The peak RHR system pressure thus calculated is 542.96 psia as compared with the structural allowable peak pressure of 674.70 psia.
50
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0
FTI Non-Proprietary 86-1234820-01 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 limitfor 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 ADDITIONCASE WITH 1.1 SQ.INCH VENT AND ONE Sl PUMP INJECTION, PRIMARYTEMP. 60'F EVENT One safet in ection um started Safe in'ection um reaches fullflow Peak pressure of 404.93 psia reached at RHR inlet Peak pressure of 414.82 psia reached in reactor vessel TIME,SEC 0.0 1.0 166.00 175.00 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 willexperience 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 Sl 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 397.38 psia.
The Appendix G allowable pressure at this temperature is approximately 710.7 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
L% r" e.
AC&
"$y
FTI Non-Proprietary 86-1 234820-01 based on a 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 8 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 and the RHR system has margin to the acceptance limit. The sequence of events is shown in Table 9.
TABLE 9 MASS ADDITIONCASE-VENT OF 1.1 SQ.INCHES AREA OPEN, ONE Sl PUMP START, PRIMARYTEMPERATURE 212'f EVENT One safe in'ection um started Safet in'ection um reaches full fiow Peak pressure of 387.88 psia reached at RHR s stem suction oint Peak pressure of 397.38 psia reached in reactor vessel TIME,SECS 0.0 1.0 200.0 200.0 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 in this transient.
There is no RC pump seal return flow modeled.
The transient 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. Since this case is run in lieu of a 135'F case, the peak reactor vessel pressure obtained is compared with the Appendix G allowable pressure at 135'F. The Appendix G allowable pressure at this temperature is 597.70 psia.
Since the primary system is less compressible at lower temperatures, the peak pressure obtained at 60'F is higher than the value that would be obtained at 135'F. 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 flow rate.
The peak RHR system pressure thus calculated is 663.49 psia as compared with the structural allowable peak pressure of 674.70 psia.
FTl Non-Proprietary 86-1234820-01 Figures 57 8 58 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 limitand the RHR system also has margin to the acceptance limit. The sequence of events is shown in Table 7a.
TABLE9a SEQUENCE OF EVENTS - MASS ADDITIONCASE WITH THREE CHARGING PUMPS, 60'F PRIMARYTEMPERATURE EVENT Three char in um s started Char in um s reache full.flow Peak pressure of 525.46 psia reached at RHR suction oint Peak pressure of 587.44 psia reached in reactor vessel downcomer TIME,SECS 0.0 1.0 7.45 7.45 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 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 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 flowthrough 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 Appendix G allowable for this temperature is 554.7 psia.
Hence, this case'passes the Appendix G 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 accept'ance criterion.
I,
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I
FTI Non-Proprietary 86-1 234820-01 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 ADDITIONCASE-PRIMARYTEMPERATURE 60'F, 2000 GPM RHR, ONE RC PUMP STARTED EVENT One RC um started RC um reaches full flow PORV o ens for the first time Peak pressure of 551.26 psia reached in the reactor vessel Peak pressure of 650.05 psia reached in the RHRs stem TIME,SECS 0.0 17.4 46.00 46.00 46.00 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 explicitlyfor 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 flowthrough 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 558.04 psia.
The Appendix G allowable for this temperature is 563.7 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.
FTl Non-Proprietary 86-1 234820-01 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, and the secondary system temperatures in the two loops. Table 11 shows the sequence of events for this case.
TABLE 11 HEAT ADDITIONCASE-PRIMARYTEMPERATURE 85'F, 2000 GPM RHR, ONE RC PUMP STARTED EVENT One RC um started RC um reaches full flow PORV o ens for the first time Peak pressure of 558.04 psia reached in the reactor vessel Peak pressure of 656.34 psia reached in the RHR s stem TIME,SECS 0.0 22.5 22.5 22.5 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 explicitlyfor 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 flowthrough 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 Appendix G allowable for this temperature is 1016.7 psia.
Hence, this case passes the Appendix G 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,
P+
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FTI Non-Proprietary 86-1234820-01 the secondary system temperatures in the two loops and the PORV fiow rate.
Table 12 shows the sequence of events for this case.
TABLE 12 HEAT ADDITIONCASE-PRIMARYTEMPERATURE 280'f, 2000 GPNI RHR FLOW, ONE RC PUMP STARTED EVENT One RV um started PORV o ens for the first time RC um reaches fullflow Peak pressure of 663.66 psia reached in the RHR s stem Peak pressure of 569.33 psia reached in the reactor vessel TIME, SECS 0.0 10.0 17.4 46.00 46.00 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 explicitlyfor 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 flowthrough 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 allowable for this temperature is 563.7 psia.
Hence, this case passes the
'ppendix 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.
FTl Non-Proprietary 86-1234820-01 TABLE 13 HEAT ADDITIONCASE-PRIMARYTEMPERATURE 85'f, RHR FLOW AT 1700 GPM, ONE RC PUMP STARTED EVENT One RC um started RC um reaches full flow PORVo ens first time Peak RV ressure of 546.79 sia reached Peak RHR pressure of 640.78 psia reached TIME,SECS 0.0 17.4 23.2 23.2 23.2 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 flowthrough 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 563.83 psia. The Appendix G allowable for this temperature is 1391.70 psia.
Hence, this case passes the Appendix G 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 rea'ctor 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.
1 II a
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FTI Non-Proprietary 86-1234820-01 TABLE 14 HEAT ADDITIONCASE - PRIMARYTEMPERATURE 320'F,RHR 1700 GPM FLOW RATE, ONE RC PUMP STARTED EVENT One RC um started PORVo ens first time RC um reaches full fiow Peak pressure in RHR system of 655.66 sia reached Peak pressure of 563.82 psia reached in the RV TIME,SECS 0.0 8.81 17.4 10.5 21.3 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
'verpressure structural design limit.
The most limiting mass addition case analyzed is a case with one charging pump turned on when the primary system is at 60'F with one RC pump running. This resulted in a peak pressure in the reactor vessel of 554.32 psia, which is marginally lower than the Appendix G limitat 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 656 psia.
The RHR system passes the structural acceptance criterion set for the RHR system by a margin of 18.7 psi. Note that below 135'F primary temperature, only one RC pump is allowed to run, by operating procedures.
Above 135'F, two RC pumps can be running and three charging pumps can start, resulting in a mass addition event.
In this case, the primary pressure was at 329.7 psia, initially. The peak reactor vessel pressure reached was 587 44 psia.
This case was run at a conservative primary temperature of 60'F and the results compared with limits at 135'F. The Appendix G limitfor this temperature is 597.70 psia. This gives a margin of 10.26 psi. The calculated peak RHR system pressure in this case was 663.50 psia against an allowable pressure value of 674.70 psia, giving a margin of 11.20 psi.
The most limiting heat addition case is the start of a reactor ccolant pump with the primary system at 60 'F. The peak reactor vessel pressure reached in this transient was 551.25 psia. The Appendix G limit is 554.7 psia.
Hence, this case passes with a margin of 3.45 psi. The peak pressure at the RHR pump Q ~)Q
FTI Non-Proprietary 86-1 234820-01 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, orily one RHR pump willbe running, yielding a greater margin to the pressure limit..
When the plant is in a configuration in which the pressurizer vent(1.1 sq.inches}
is open, the primary system pressure willbe at atmospheric pressure in the pressurizer.
No RC pump willbe 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 a peak reactor vessel pressure of 414.82 psia, which is less than the Appendix G limitby 139.88 psi. The peak RHR pressure in this case is 542.96 psia as compared with the allowable presssure of 674.70 psia.
Consequently, 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.
FTI Non-Proprietary
-1 234820-01 TABLE16
SUMMARY
OF RESULTS Peak press.
Structural in RHR allowable system in psia in psia RESULTS OF THE MASS ADDITIONCASES Case ID Description Peak pressure Allowable per Margin Margin in reactor Appendix G in psi in psi vessel,psia in psia Case 1.
85'F, three charging pumps started, no RC pump running, primary pressure 329.7 psia No RC pump seal leakage 1700 gpm RHR 480.19 Case 2 60'F, one charging pump started, one RC pump running, primary pressure 329.7 psia 3 gpm RC pump seal leakage 2000 gpm RHR 554.32 563.70 554.70
+83.51 0.38 598.43 674.70 76.27 656.00 674.70 18.7 (continued) 30
FTl Non-Proprietary
-1 234820-01 TABLE15(continued)
RESULTS OF THE MASS ADDITIONCASES Case ID Description Peak pressure Allowable per in reactor Appendix G vessel,psia in psia Margin ln psl Peak press.
Structural Margin in RHR allowable in psi system 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.
2000 gpm RHR 414.82 554.70 Case 4 212'F primary,no RC pumps, 14.7 psia initial primary
- pressure, one Sl pump turned on.
2000 gpm RHR 397.38
=-710.7 139.88 542.96 674.70 131.74 313.32 525.91 674.70 148.79 Case 2a 60'F primary, two RC pumps, 329.? psia initial pressure three charging pumps turned on.
2000 gpm RHR 587.44 597.70 O 135'F 10.26 663.49 674.70 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) 31
FTI Non-Proprietary
-1234820-01 TABLE15(continued)
RESULTS OF HEATADDITIONCASES Case ID Description Peak pressure in reactor vessel,psia Allowable per Margin Appendix G in psi in psia Peak press.
Structural Margin in RHR allowable in psi system in psia in psia 554.7 Case 5 60'F primary, 2000 gpm RHR, one RC pump started.
Primary pressure 329.7 psia 551.25 3.45 649.96 674.70 24.74 Case 6 85'F primary,2000 gpm RHR, one RC pump started.
Primary pressure 329.7 psia 558.04 5.66 656.34 674.70 18.36 1016.7 Case 7 280'F primary, 2000 gpm RHR, one RC pump started Primary pressure 329.7 psia 569.33 447.37 663.66 674.70 11.04 Case 8 85'F primary, 1700 gpm RHR, one RC pump started Primary pressure 329.7 psia 546.79 563.7 16.91 640.?8 674.70 33.92 32
FTI Non-Proprietary
-1234820-01 TABLE15(continued)
RESULTS OF HEATADDITlONCASES Case ID Description Peak pressure Allowable*per Margin in reactor Appendix 6 in psi vessel,psia in psia Peak press.
Structural in RHR allowable system in psia in psia Margin In psl Case 9 320.0'F primary, 1700 gpm RHR, one RC pump started Primary pressure 329.7 psia 563.82 1391.7 827.88 655.66 674.70 19,04 Note: Appendix 6 allowables shown here are from Table 2. Reference 4 had an earlier Appendix G curve from the UFSAR of Ginna plant and the values were slightly different.
32a
my sr>M
FTI Non-Proprietary 86-1 234820-0'1
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 LimitCurves 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, "LowTemperature Overpressure Analysis for RGE - Ginna Plant" February 1995.
5.
BAW-10164P-A, "RELAP5/MOD2-B8W - 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-Proprletary 86-1 234820-01 PLOTS OF THE RESULTS
lA
1 FIGURE 4 CASE 1 MASS ADDITIONCASE PRIMARYTEMPERATURE 85oF PRIMARYPRESSURE 329.7 PSIA 3CHARGING PUMPS NO RC PUMP RUNNING NO SEAL LEAKAGE 450.--
ll O
U Oa (D
400 350 300
~
'5 0
'00 0
80 160 320 TIMEIN SECONDS 480 CO0) tV 4)
CD C)
450 FIGURE 5 CASE 1 MASS ADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA 3 CHARGING PUMPS NO RC PUMP RUNNING NO SEAL LEAKAGE rl OD 0U Q
0) 0 0
O 400 950 900-250 --
CO CD hD CP CO C) 200 0
80 160 240 920 400 TIMEIN SECONDS 480
560 520 480 440 400 360 FIGURE 6 CASE 2 MASS ADDITIONCASE'RIMARYTEMPERATURE 60'F PRIMARYPRESSURE 329.7 PSIA 1 CHARGING PUMP ONE RC PUMP RUNNING 3 GPM SEAL I EAKAGE il z
O 0
CD Q
CO CD h3 Co h3 C) 320 0
10 20 30 40 50 TIMEIN SECONDS 60 70
560 520 480 440 400 360 FIGURE 7 CASE 2 MASS ADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARY PRESSURE 329.7 PSIA 1 CHARGING PUMP ONE RC PUMP RUNNING 3 GPM SEAL I EAKAGE O
0 0o CD Q)
CO CD I
M Co C) 320 0
10 20 30 40 50 TIME IN SECONDS 60 70 80
480 FIGURE 8 CASE 3 MASS ADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 14.7 PSIA 1 SI PUMP STARTED NO RC PUMP RUNNING 1.1 SQ.INCH VENT NO SEAL LEAKAGE 400 320 240 160 80 0
0 50 100 TIMEIN SECONDS 125 150 175
tjl
~\\
C4O0 480 320-FIGURE 9 CASE 3 MASS ADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 14.7 PSIA 1 Sl PUMP STARTED NO RC PUMP RUNNING 1.1 SQ.INCH VENT NO SEAL LEAKAGE Tl 0D O'a (D
240 160 00 CD I
M CQ CXI fV C) 0 0
50 TIME IN SECONDS 125 150 1'75
7 e
0
~\\
0OR O
4SO 400 320 240 FIGURE 10 CASE 4 MASS ADDITIONCASE PRIMARYTEMPERATURE 212oF PRIMARYPRESSURE 14.7 PSIA 1 Sl PUMP STARTED NO RC PUMP RUNNING 1.1 SQ.INCH VENT NO SEAL LEAKAGE ll 0D Oo (D
9)
Co G) lV (1i Ql C) 0 0
15 50 75 l00 TIME IN SECONDS 150 l75
~\\
Ck0 6
400 320 FIGURE 11 CASE 4 MASS ADDITIONCASE PRIMARYTEMPERATURE 212oF PRIMARY PRESSURE 14.7 PSIA 1 Sl PUMP STARTED NO RC PUMP RUNNING 1.1 SQ.INCH VENT NO SEAL LEAKAGE Tl O
OU Q
240 160 80 0
0 50 75 125 TIMEIN SECONDS 150 175 00 CD GD CX' CD
M P0 PlA0R eZ0 520 480 FIGU 12 CASE 5 HEATADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR n
0 0'a CO 0)
M 00
!V C) 320 0
20 60 40 Transient time in secs 80
P4 Pl4 680 FIGURE 13 CASE 5 HEATADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP.
ONE RC PUMP STARTED 2000 GPM RHR LEGEND RHR-P VMP A
~
RHR-PVMPB 0D 0a (0
C0 g %
fD (0I CD 560 520 480 Co CD I
M CD CO C) 440 20 40 60 Transient time in secs
Q0 lQ Og l04 96 88 80 72 64 FIGURE 'I4 CASE 5 HEATADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR Tl Z0D 23 Oo Q
CJ CD I
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2000 GPM RHR
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FIGURE 19 CASE 5 HEATADDITIONCASE. PRIMARYTEMPERATURE 60oF PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR 115 110 105 100 95 90 85 0
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FIGURE 20 CASE 5 HEATADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED-2000 GPM RHR 50 30 20 10 0D OUI CD CO CD fV GD COM C) 20 40 60 80 100 Transient time in secs 560 520 480 440 FIGURE CASE 6 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR ll 0D 0U CD PD 0)
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FIGUR 22 CASE 6 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR 0D 0
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120 112 104 96 88 80 10 20 30 50 0D Oo.
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FIGU 24 CASE 6 HEATADDITIONCASE PRIMARYTEMPERATURF 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED
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FIGUR CASE 6 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR 136 132 128 124 120 116 10 20 30 Transient time in secs 50 n
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10 20 30 Transient time in secs 120 100 80 60 40 20 Fl E 29.
CASE 6 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR Tl OD O'a (D
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10 20 30 50 Transient time in secs 550 500 450 FIGURE 30 CASE 7 HEATADDITIONCASE PRIMARYTEMPERATURE 280'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR n
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650 600 550 500 450 FIGURE 31 CASE 7 HEATADDITIONCASE PRIMARYTEMPERATURE 280'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO SI, NO CHARGING.PUMP ONE RC PUMP STARTED 2000 GPM RHR LEGEND
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310 305 300 29$
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Fl E 32 CASE 7 HEATADDITIONCASE PRIMARYTEMPERATURE 280'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC'PUMP STARTED 2000 GPM RHR 4l 30 20 10 Transient time in secs 50 Tl 0
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FIGURE 35 CASE 7 HEATADDITIONCASE PRIMARYTEMPERATURE 280'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 2000 GPM RHR rl O
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100 75 10 20 30 Transient time in secs 50
520 480 FIGURE 39 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR
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680 FIGUR 40 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR Tl 0
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FIGURE 42 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 850F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR L
10 15 20 TIMEIN SECQNDS 30 35
110 105 FIGURE 43 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO SI, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR ll O
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10 15 20 TIMEIN SECONDS 25 30 35
136 FIGURE 45 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR bQ A
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C4 8
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FIGURE 46 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO SI, NO'CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 136 O
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10 15 20 TIME IN SECONDS 30 35
120 FIGURE 47 CASE 8 HEATADDITIONCASE PRIMARYTEMPERATURE 85'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUIVIP STARTED 1700 GPM RHR rl OD 0
13 10 Dl 00 CD hJ CO bJ C) 10 1$
20 2$
TIME IN SECONDS aa 3$
550 FIGURE 48 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320oF PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR T1 Z0 0
Q tD 450 400 350 00 CD lO CD OC fO 10 15 20 TIMEIN SECONDS 30 35 40
FIG 49 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARYPRESSURE 329.7 PSIA
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600 g
550
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350 FIGURE 50 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARY PRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 345 340 335 330 320 10 15 20 25 TIME IN SECONDS 30 35 40
368 FIGURE 51 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR A
C400 360 g
352 U
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344 336 328 320 0
10 l5 20 25 30 35 40 TIME IN SECONDS
lasts
x10 20 FIG 52 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320 F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 16 12 T
l 10 20 TIMEIN SECONDS
. 30 40
FIGURE 53 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR
-400 le Cll Pl C4
-800 00 g -I200 g
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C4 A
C4 8
8 37$
370 365 FIGURE 54 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR fl O
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9)
CO CD I
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150 FIGURE 56 CASE 9 HEATADDITIONCASE PRIMARYTEMPERATURE 320'F PRIMARYPRESSURE 329.7 PSIA NO VENT, NO Sl, NO CHARGING PUMP ONE RC PUMP STARTED 1700 GPM RHR 125 100 I
i 1
I I
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FIGURE 57 CASE 2a MASS ADDITIONCASE PRIMARYTEMPERATURE 60'F PRIMARYPRESSURE 329.7 PSIA 3CHARGING PUMPS TWO RC PUMP RUNNING 550 500 450 350 300 0
lQ 20 30 40 50 TIMEIN SECONDS 70 80
550 FIGURE 58 CASE 28 MASS ADDITIONCASE PRIMARYTEMPERATURF 6P F PRIMARYPRESSURE 329 7 PSIA 3CHARGING PUMPS TWO RC PUMP RUNNING Fc
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10 20 30 40 TIME IN SECONDS 50 70 80
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