3F0298-07, Forwards Topical Rept for Review & Approval,Which Describes Addl Active Method of Preventing Boron Precipitation Following Design Basis Loca.Issuance of SER Is Also Requested
| ML20203K473 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/27/1998 |
| From: | Holden J FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20203K477 | List: |
| References | |
| 3F0298-07, 3F298-7, NUDOCS 9803050098 | |
| Download: ML20203K473 (16) | |
Text
.
8 ?%"P3M Florida Power C.M.".k mn February 27,1993 3F0298-07 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Request for NRC Approval of Topical Report - Boron Dilution by Reactor Coolant System llot Leg Injection - Crystal River Unit 3
References:
- 1. Topical Report BAW-10103A, Revision 3 July 1977, "ECCS Analysis of B&W's 177 FA Lowered-Loop NSS," Babcock & Wilcox
- 2. NRC to B&W letter, Topical Report Evaluation, dated February 4,1976
- 3. FPC to NRC letter (3F0997-28) dated September 12,1997, " Post LOCA Boron Precipitation Mitigation Plan"
- 4. FPC to NRC letter (3F1097 32) dated October 31, 1997
" License Amendment Request #223, Revision 0, Post-LOCA Boron Precipitation Mitigation Plan"
- 5. FPC to NRC letter (3F0198-44) dated January 31,1998, " Revision to Submittal Date for Hot Leg Injection via Reverse Flow Method of Post-LOCA Boron Precipitation Control"
Dear Sir:
M.
==
Florida Power Corporation (FPC) is submitting a topical report for NRC review and approval, E
which describes an additional active method of preventing boron precipitation following a design E
basis loss of coolant accident (LOCA) at Crystal River Unit 3 (CR-3). This additional method, hot leg injection via reverse Dow (HLI-RF) through portions of the Low Pressure Injection system (LPI), provides defense in depth for the current methods of post-LOCA boron dilution, Q.
Drop Line to Reactor Building Sump (DL-RB Sump) and Auxiliary Pressurizer Spray (APS).
=E -
Submittal of this topical report describing the HLI-RF method by February 27,1998, satisfies FPC's commitment made in References 3,4 and 5.
The topical report is related to the subject of FPC's License Amendment Request (LAR) #223 (Reference 4). However, NRC review of the topical report is requested separate from review of LAR #223. Submittal of the HLI-RF method as a topical report separate from LAR #223 has been discussed with the NRC Staff.
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i CRYSTAL RIVER ENERGY COMPLEX; 15760 W Power Line Street Crystal River. Flonda 344284708 = (352) 795-6486 9803050098 980227
- '*' Progress Cornpany PDR ADOCK 05000302 P
PDR.
l U. S. Nuclear Regulatory Commission 3F0298-07 Page 2 of 3
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The topical report consists of this submittal letter and the attached Description of Ilot leg injection Via Reverse Flow Through Portions of the LPI System (Attachment A); FPC Calculation M97-0088 (Attachment B); letter from Ingersoll Dresser Pump Company, dated November 12,1997 (Attachment C); FPC Calculation M97-0098 with supporting Framatome Technologies incorporated (FTI) Document 51-5000519-06 (Attachment D): and Acronyms and Abbreviations (Attachment E). FTl Document 51-5000519-06, provided as part of Attachment D, supersedes in its entirety FTl Document 51-5000519-02, submitted as Attachment D of LAR
- 223 (Reference 4).
Ilot leg injection via reverse flow (IILI-RF) was formally proposed to the NRC in Babcock and Wilcox (B&W) Topical Report BAW-10103 (Reference 1). That report described the basis for utilizing this boron precipitation mitigation option.
The NRC evaluation of BAW-10103 (Reference 2) acknowledged the conceptual feasibility of this method of baron precipitation mitigation and indicated that its use would be reviewed by the NRC for individual plants on a case-by-case basis.
A summary of the passive and active methods of controlling post-LOCA boron concentration and preventing precipitation, as well as a detailed discussion of the IIL1-RF method, is presented in Attachment A. A discussion of the mechanisms involved with boron precipitation following design basis LOCAs and the methods available at CR-3 have been previously provided to the NRC in License Amendment Requests #220 (approved as License Amendment #164) and #223.
FPC, with suppoit from FTI, has evaluated the use of this method of post-LOCA baron precipitation control for CR-3 and has found it acceptable. Ilowever, implementation of the llLI-RF method at CR-3 requires NRC review and approval of the method. Therefore, FPC requests NRC review of the topical report and issuance of a safety evaluation report (SER).
FPC will implement the llLI-RF method based on the SER when issued by the NRC. FPC will continue to participate with the B&W Owners Group ir. efforts to resolve this issue generically.
There are no commitments made in this submittal. If you have any questions regarding this submittal, please contact Ms. Sherry Bernhoft, Manager, Nuclear Licensing at (352) 563-4566.
Sincerely, th -
J.. Iloiden. Director Site Nuclear Operations JJII:rer Attachments xc:
Regional Administrator, Region II NRR Project Manager Senior Resident Inspector l
1 l
U. S. Nuclear Reguletory Commission 3F0298-07 Page 3 of 3 ATTACHMENTS Atta'chment A Description ofIlot lag injection Via Reverse Flow Through Portions of LPI z
System Attachment U FPC Calculation M97 0088, "llydraulic Analysis for LPI Ilotleg injection to RCS" i
Attachment C Ingersoll Dresser Pump Company letter to FPC dated November 12, 1997, "811N 194 Decay lleat Pumps, Typical S/N - 1624920/21" Attachment D FPC Calculation M97-0098 R6, " Boron Dilution by llot leg lajection" (with supporting FTl Repor, $1-5000519-06, " Boron Dilution by RCS Ilot Ixg injection")
Attachment E Acronyms and Abbreviations 4
U.S. Nuclear Regulatory Commission Attachment A 3F0298-07 Page 1 of11 ATTACHMENT A DESCRIITION OF llOT LEG INJECTION VIA REVERSE FLOW TIIROUGH PORTIONS OF LPI SYSTEM lntroduction A discussion of the mechanisms involved with boron precipitation fe!!owing design basis loss of coolant accidents (LOCA) and the methods available for Crystal River Unit 3 (CR-3) was provided ia License Amendment Requests (LAR) #220 and #223 (References 3 - 8). It was discussed in those submittals and associated references that certain LOCAs may result in the concentration of boric acid in the reactor core increasing to the point which it would potentially approach the solubility limit and begin precipitating out of solution. It was discussed in those submittals that passive and active methods would be needed to control the boron concentration.
These methods will be initiated only if boron dilution is occurring in the sump or if sump sampling cannot be achieved. As described in those submittals, CR-3 uses the following methods to control post-LOCA baron concentration in the reactot core and prevent prec;pitation.
Passive Methods:
Reactor Vessel Vent Valve (RVVV) Overflow - This passive design feature results in natural circulation through the RVVVs and will automatically occur for cold leg breaks which result in sufficient refill of the reactor vessel (RV). Overflow through the RVVVs to the vessel downcomer replaces emergency core cooling system (ECCS) water of lower boron concentration from the lower plenum into the core region, which limits the maximum boron concentration to less than the solubility limit.
Hot Lee Nozzle Gan Flow - This passive design feature inherently utilizes natural circulation from the upper core region through the gaps between the hot leg outlet nozzles and core support shield to the downcomer. The flow of water through the hot leg nozzle gaps recirculates through the downcomer and mixing occurs thus diluting the concentration of boron in the core as the volume of water passed by the gaps is replaced with water of lower boron concentration.
Active Methods:
ECCS Flow Path Throuch the Reactor Vessel - Ti.is method applies to those breaks on the hot leg side of the RV. The ECCS flow path through the reactor coolant system (RCS) is from the cold leg, into the downcomer, through the core, and out the hot leg (to the break) which will supply a continuous flow of ECCS water through the RV, limiting the boron concentration to less than the solubility limit. No additional operator actions are required to ensure dilution. Breaks on the cold leg side of the RV do not provide this flow path.
U.S. Nucicar Regulatory Commission Attachment A 3F0298-07 Page 2 of 11 Drop Line to the Reactor Buildine (RB) Sump (DL-RB Sumn)- In this method, aligning the decay heat drop line to the RB sump will allow gravity feed of reactor coolant from the hot leg to the RB sump and recirculation back to the RV through the ECCS. Figure 1 shows the system Dow paths when using the DL-RB Sump method. This will result in injection flow through the core at a rate equal to the drop line flow rate plus core boil-off.
There are precautions with this method regarding when the drop line to the sump can be opened. Limitations associated with this method are currently prescribed in CR-3 Emergency Plan Implementing Procedure EM-225B, " Post-Accident Boron Concentration Management."
Auxiliary Pressurizer Sprav (APS) - In this method, water from the RB sump is injected into the pressurizer via the pressurizer spray. This water then Dows into the hot leg forcing a reverse now through the reactor core. This method provides a constant How of water with lower baron concentration through the core, diluting the RCS boron concentration in the reactor core region, thereby preventing boron precipitation. The now path is through the APS line, supplied from the low pressure injection (LPI) system, out of the pressurizer through the surge line into the hot leg, and then into the RV. Figure 2 shows the system Dow paths when using the APS method. APS is effective when ?he spray now rate exceeds the boil-off rate.
Proposed New Method in addition to the above methods FPC has evaluated another active method that would be available for use at CR-3. This method provides hot leg injection via reverse now (HLI-RF),
through portions of the LPI system. This method involves aligning the ECCS flow path in a manner that has not been previously approved by the NRC for CR-3. This alignment involves securing one train of ECCS (if nmning), aligning the system to provide reverse flow through the idle LPI pump, into and through the decay heat drop line to the hot leg, thereby providing reverse flow through the reactor core.
As part of the original licensing basis for boron precipitation control at CR-3, Babcock and Wilcox (B&W) Topical Report BAW-10103 (Reference 1) discussed the alignment of a part of the LPI injection to Dow backward through the drop line into the hot leg. The NRC evaluation of the topical report acknowledged the conceptual feasibility of this method of boron dilution and indicated its application would be reviewed on a case-by-case basis for individual plants.
FPC, with support from Framatome Technologies Incorporated (FTI), evaluated the use of this method of post-LOCA boron precipitation control for CR-3, and has found it acceptable. This method will provide an additional means of post-LOCA boron precipitation control. The results of this evaluation are included below. The FTI evaluation of this method is documented in FTI Report 51-5000519-06, provided as Attachment D. Additional discussion of HLI-RF, including a demonstration of its effectiveness, can be found in Reference 9.
U.S. Nuclear Regulatory Commission Attachment A 3F0298-07 Page 3 of 11 f
Ikwrlation of Ill,I RF Method Figure 3 shows the system flow paths when using the llLI-RF method. In this method of post-LOCA boron dilution, ECCS flow is simnitaneously injected into the RCS via the following three flow paths:
LPI through the core flood line nozzle to the reactor vessel downcomer liigh pressuie injection (IIPI) system to the RCS cold legs, with water supply provided by the operating LPI pump Reverse flow through the decay heat drop line to the RCS hot leg The ECCS tlow rate will be established through each of these injection paths to ensure sufficient flow to the core for removal of decay heat and maintain adequate cofe cooling. To accomplish this during the time when llL1-RF may be needed to prevent post-LOCA boron precipitation, the flow rate through the flow paths will exceed: 1) the core boil-off rate necessary to remove decay heat and 2) hot leg nozzle gap flow.
To provide the ECCS injection into the RCS as described above, one operating LPI pump continues to be aligned to provide flow through one core flood line nozzle and to the suction of one IIPI pump which is also providing ECCS injection flow. After ensuring adequate operation
. f one ECCS train. the opposite ECCS train is secured. The LPI cross connect line is opened and a portion of the ECCS f5w is routed backwards through the idle LPI pump, through the decay heat drop line, and inic the hot leg. This alignment reverses the typical flow direction in the id:e LPI pump and decay heat drop line, The flow path inside the reactor vessel during HLI-RF before and after core boiling suppression is shown in FTI-51-5000519-06, Figures 3 and 4, respectively (Attachment D). Flow from the hot leg enters the reactor vessel outlet plenum where a portion of the hot leg injection may flow through the hot leg nozzle gap to the downcomer. The remaining HLI-RF flows into the upper plenum and to the core. As discussed in the following section, the minimum required HLI-RF flow rate will exceed the core boil-off rate plus the flow that could potentially bypass the core by flowing through the hot leg nozzle gap. A net reverse flow of lower boron concentration fluid through the core will arrest and retard the process of concentrating of boron which will prevent reaching the solubility limit. The net reverse flow through the core will then pass through the lower plenum and downcomer to the cold leg where it will flow out the cold leg break. The analyses to support this method are discussed below.
ECCS Reauirements for HLI-RF Preventing post-LOCA boron precipitation using HLI-RF will involve a line-up of the ECCS flow path that has not been previously approved by the NRC for CR-3. This line-up includes securing one train of ECCS (if running), providing reverse flow through the idle LPI pump and the decay heat drop line, and providing reverse flow through the reactor core.
(
U.S. Nuclear Regulatory Commission Attachment A 3F0298-07 Page 4 of 11 in ITl Report 51 5000519 06 FTl recommends maintaining flow rates through the RCS injection paths as described in Table 1. These flow rates provide both core cooling and boron dilution.
Tabl: 1 Flow Rates for llLI RF Flow Path Flow Rate (gpm)
Lpl flow through core Good line nozzle to the reactor vessel downcomer approximately 1000 llPI system to the RCS cold legt 600 Reverse flow through the decay heat drop 500 line to the RCS not leg An examph provided in FTl Report 515000519-06 states that at at RCS pressure of ~12 psia (corresponding to 4 :.uration temperature of 305' F), all of the baron initially injected into the RCS from the Core Flood Tanks (CFT) and Borated Water Storage Tank (BWST) will not remit in baron precipitation. At higher temperatures and pressures, the boron solubility limit is greater than the maximum possible core boron concentration, in addition, based on 1.0 times the ANS 1971 fission product decay heat, the carilest time following a LOCA at which boron concentration in the reactor core could reach the solubility limit is approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Taking into consideration the Appendix K decay heat level of 1.2 times ANS 1971, the time to reach the solubility limit is approximately 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. This is based on a large break LOCA (LBLOCA), where the RCS pressure and temperature rapidly approach RB conditions. In the case of small break LOCAs (SBLOCA), the RCS pressure and temperature can remain elevated above the containment pressure. The higher saturation temperature results in a higher boron solubility limit that cannot be reached until later in the transient.
The llLI RF flow rate was calculated to ensure a net reverse flow through the core that will dilute the core boron concentration, considering the core boil-off rate and an allowance for flow that could potentially bypass the core by flowing through the hot leg nozzle gap. In FTI Report 51-5000519-06,171'l recommends that the llLI RF alignment provide up to 600 gpm flow for oft 1 liFi pump, a minimum hot leg injection flow of 500 gpm for boron dilution, and approximately 1000 gnm into one core 11ood line nozzle. Following either a SBLOCA or LBLOCA, a minimum IILI RF flow of 500 gpm will provide sufficient reverse flow to dilute the core boron concentration and prevent boron precipitation at 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and later. Figures 5 through 8 of FTI-515000519-06 (Attachment D) refimt boron concentrations versus time for LBLOCA and SBLOCA based on use of IILI-RF.
As decay heat decreases with time, the minimum required IILI-RF flow will eventually be sufficient to suppress core boiling. At the point that the llL1 RF flow is sufficient to overcome core boiling, boron precipitation will no longer be a concern. Re establishment of subcooling and suppression of core boiling climinates the mechanism that concentrates the boron, thereby climinating the boron concentration concerns for the remainder of the event.
F U.S. Nuclear Regulatory Commission Attachment A 3F0298 07 Page 5 of 11 Snlem Analnl5 1.P1 Flow Rate FPC performed a hydraulic analysis of the LPI system to demonstrate that the llLI.RF flow requirements determined by FTl would be satisfied. This analysis also evaluated the impact of reverse Dow through the affected LPI components, including the LPI pump. This analysis, FPC Calculation M97-0088, is provided as Attachment B.
liydraulic modeling of the LPI system concluded that the operating LPI pump is capable of supplying 500 to 1000 gpm of reverse flow through the drop line throughout the range of RCS pressures for which reverse flow would be required, while simultaneously providing necessary ECCS flow. At higher pressures when 1000 gpm flow through the drop line could not be achieved, flow through the normal LPI injection path may be throttled in order to maintain reverse now through the drop line greater than 500 gpm. The results of the analysis are summarized in Table 2.
Table 2 IILI RF Flow Rate RCS Pressure Drop line Reverse Normal LPI Flow LPI Pump Flow (psig)
Flow (gpm)
(gpm)
(gpm) 0 999.8 1350,1 3048.3 10 999.9 1350,1 3048.5 20 1000.4 1350.0 3048.8 30 1000.2 1349.2 3047.9 50 1000.9 1350.I 3049.6 65 1000.3 1349.9 3048.6 70 1000.1 1349.6 3048.1 80 990.6 1350.5 3039.5 85 834.8 1525.2 3059.6 99 698.3 1650.0 3048.0 95 600.7 1700.6 2999.9 100 595.8 1575,1 2872.0 I10 5%.9 1275.3 2575.4 120 583.8 1000.3 228).3
U.S. Nucle r Regulatory Commission Attachment A 3F0298 07 Page 6 of 11 NPSil Evaluation Net positive suction head (NPSil) required and available for the LPI nmp in this configuration was also evaluated to ensure cavitation within the pump would not c,
The analysis concluded that adequate NPSil is available for the LPI pumps. The analysis perk ud to support this conclusion, FPC Calculation h197-0088, is provided as Attachment B.
Component Evaluation Components within the flow path for this method (llLI.RF) were evaluated for the effects of reverse Dow. The critical components evaluated were:
the windmilling LPI pump. effects upon seals, motor, and potential pressure drops the control valves which will be used to control flow in the reverse direction the heat exchangers Effects upon the LPI pump sesis in backflow conditions have been evaluated by the pump seal manufacturer. This evaluation concludes that the LPI pump seals will perform acceptably under the approximate range of 500 to 1000 gpm backDow conditions. The letter from the pump seal manufacturer, John Crane incorporated dated August 13,1996, is included in FPC Calculation h197 0088 (Attachment B).
The LPI pump manufacturer, Ingersoll-Dresser Pump Company, has reviewed the pump with regard to running in reverse rotation. The conclusion was timi the pump will not have a problem running up to full speed in reverse, with no damage or loss of service life. The letter from Ingersoll Dresser Pump Company, dated November 12, 1997, is provided as Attachment C, The differential pressure drop across the windmilling decay heat pump has been determined and was 4
used in the development of the hydraulic models previously described. Wintimilling an AC motor at speeds of up to 890 rpm (50% of 1780 rpm) does not create problems for the motor or bearings.
When llLI RF is secured, pump coastdown from reverse rotation will os cur prior to restarting the idle LPI pump in the forward flow direction.
Toe ability of the control valves DilV-110 and DilV-111 in the LPI pump discharge to regulate flow in the approximate range of 500 to 1000 ppm was..iscused with Crane Valve, the supplier of these valves. Crane Valve confirmed that these valves would perform acceptably for an extended period.
The record of this communication with Crane Valve is included in FPC Calculation h197-0088 (Attachment B).
LPI injection flow will be throttled to approximately 1000 gpm by DilV-5 and DilV-6. These valves nave been evaluated for similar throttling applications. Based on correspondence from Crane Valves and communications with FPC's hiaterial Technology group, structural integrity of the valves is expected to be main,ained in this configuration.
s
U.S. Nuclear Regulatory Commission Attachment A j
31:0298-07 Page 7 of 11 i
llydraulically, the heat exchangers are unaffected by the direction of How on the tube side. The heat 4
transfer characteristics of the heat exchangers would be affected in that the amount of heat transfer through this heat exchangc. is less than the amount when tube How is in the normal direction since these heat exchangers are counterflow heat exchangers, lleat transfer to the decay heat closed cycle cooling water system is, therefore, bounded by existing heat transfer analysis. No credit is taken for any heat transfer through the reverse flowing heat exchanger.
This r ;ew of components subjected to reverse now conditions indicates that all components will perforn. cceptably under reverse now cenditions of 500 - 1000 gpm.
ITI has also evaluated the impact of the hot leg injection on the hot leg piping, the reactor vessel, and the reactor vessel internals. The evaluation includes:
Steam water interaction and/or cold water-hot water interactions (water hammer)
Stratified liquid How in the hot leg pipe Temperature rates of change for the reactor vessel and the reactor vessel internals Operation within the Pressure-Temperature limits Reverse flow in the core The res tits of the evaluation are documented in FTl Report 515000519-06, pr Mded in Attachment D. The evaluation indicates that there are no thermal-hydraulic, mechanical, or core conditions that will prevent the use of IILI RF to dilute core boron concentration.
Procedures Guidance on the use of the llLI RF method is provided in Emergency Phn Implementing Procedure EM 22511, "Fost Accident Baron Concentration Management." A note in that procedure states that this method cannot be implemented until after appropriate approsal by the NRC of this method.
Following NRC review and approval, this post-LOCA boron dilution method will be implemented only at the direction of the Technical Support Center (TSC) similar to the other active boron dilution methods.
Notwithstanding the note in EM-225B, FPC's position is that, pursuant to 10 CFR 50.54(x) and (y),
this method could be used at CR-3 prior to NRC review and approval, but only as an eraergency action and only if the other available methods of boron dilution are not adequately controlling boron concentration in the reactor vessel. Approval by the accident assessment team assembled in the TSC and the Emergency Coordinr. tor would be required prior to use of this method under thes:
circumstances.
FIC considers that providing this guidance and controls on use of IIL1 RF in EM 225B at this time helps assure nuclear safety since it ensures that all options for controlling boron concentration will be readily available during post-accident conditions.
U.S. Nuclear Regulatory Commission Attachment A 3F0298 07 Page 8 of 11 Conclusion FPC, with support from FTI, has evaluated the use of the llL1 RF metlux! of post LOCA boron concentration control for CR 3 arnt has found it acceptable. Evaluation of this meth(xl included determination of ECCS flow rates for core decay heat removal and boron dilution, hydraulic analysis of the LPI system, and review of components for reverse flow effects. This is an additional mettuxi for post LOCA boron concentration control.
References 1.
Topical Repcu ilAW 10103A, Revision 3, July 1977, "ECCS Analysis of B&W's 177 FA Lowered Loop NSS," Babcock & Wilcox
_2.
NRC to ll&W letter, Topical Report Evaluation, dated February 4,1976 3.
FPC to NRC letter, 3F1097 32, dated October 31,1997, " License Amendment Request
4.
FIC to NRC letter, 3F1097 08, dated October 31,1997, "Li:ense Amendment Request
- 220, Revision 1: Revision of Operating License Condition 2.C.(5): (TAC No. 99128)"
5.
FPC to NRC letter, 3F1297 21, dated December 1,1997. " Clarification 7 License Amendment Request #220, Revision 1 (TAC No. 99128)"
6.
FPC to NRC letter,3F1297 12, dated December 4,1997 " Additional Information Regarding l
the Post LOCA Boron Precipitation Prevention Plan for CR 3" 7.
FPC to NRC letter, 3F1297-43, dated December 13,1997, " Additional Information on License Amendment Request #220 - Revision of Operating License Condition 2.C.(5)(TAC No. M99128)"
8, FPC to NRC letter, 3F124/-44, dated December 20,1997, " Additional Informativa Regarding License Amendment Requests #220 & #223 (TAC Nos. M99128 & M99892)"
9, Framatome Technologies Inc. Document 86-1266272-01, " Post LOCA Boron Concentration Management tbr CR-3 " February,1998 r*w-w-ye-ewres--'-p y
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U.S. Nuclear Regulatory Commission Attachment A 310208 07 l' age 10 of II Figure 2 Auxillary Pressurizer Spray (Flow Schematic)
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U S. Nuclear Regulatory Commission Attachment A 31'0298 07 Page 11 of 11 Figure 3 Hot Log injection via Reverso Flow (Flow Schematic)
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i U.S. Nuclear Regulatory Commission Attachment E j
3F0298-07 Page 1 of 1 ATTACIIMENT E ACRONYMS AND ABBREVIATIONS APS....... Auxiliary Pressurizer Spray B&W....... Babcock and Wilcox IlWST,..... Borated Water Storage Tank CFT....... Core Flood Tank CR-3....... Crystal River Unit 3 DL-RB Sump.. Drop Line to Reactor Building Sump (mitigation method)
ECCS...... Emergency Core Cooling System FPC....... Florida Power Corporation FTl........ Framatome Technologies incorporated gpm....... gallons per minute Ill.1 RF...
. Ilot leg injection via Reverse Flow (mitigation method)
IIPI........ liigh Pressure injection system LAR
...... License Amendment Request LBLOCA
... Large Break LOCA LOCA...... Loss of Coelant Accident LPI........ Low Pressure Injection system NRC....... U.S. Nuclear Regulatory Commission ppm....... parts per million RB
...... Reactor Building -
RCS....... Reactor Coolant System RV........ Reactor Vessel RVVV...... Reactor Vessel Vent Valve SBLOCA.... Small Break LOCA TSC....... Technical Support Center
- =
. m 1
ATTACIIMENT B TO 3F0298 97 FPC CALCULATION A197-0088, Revision 0 Ilydraulic Analysis for LPI Ilotleg Injection to RCS (Computer Output omitted) l l
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