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{{Adams
#REDIRECT [[NOC-AE-16003347, Response to Request for Additional Information Regarding the License Amendment Request for Extension of Containment Leakage Rate Testing Program]]
| number = ML16089A406
| issue date = 03/17/2016
| title = Project, Units 1 and 2 - Response to Request for Additional Information Regarding the License Amendment Request for Extension of Containment Leakage Rate Testing Program
| author name = Nemeth P G
| author affiliation = South Texas Project Nuclear Operating Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000498, 05000499
| license number =
| contact person =
| case reference number = NOC-AE-16003347, STI: 34285574, TAC MF6176, TAC MF6177
| document type = Letter, Response to Request for Additional Information (RAI)
| page count = 92
| project = TAC:MF6176, TAC:MF6177
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 March 17, 2016 NOC-AE-1600334 7 10 CFR 50.90 File No. G25 Request for Additional Information Regarding the License Amendment Request For Extension of Containment Leakage Rate Testing Program South Texas Project Units 1 and 2 TAC NOS MF6176 and MF6177
 
==References:==
: 1. Letter from G. T. Powell, STP, to NRG Document Control Desk, "Units 1 and 2 License Amendment Request for Extending the 10 year ILRT to 15 years", dated April 29, 2015 (NOC-AE-15003227) (ML 15128A352)
: 2. Letter from G. T. Powell, STP, to NRG Document Control Desk, "Units 1 and 2 License Amendment Request for Extending the 10 year ILRT to 15 years PRA Supplement", dated June 29, 2015 (NOC-AE-15003266) (ML 15198A147)
: 3. Email from Lisa Regner, NRG, to Lance Sterling, STPNOC, "STP ILRT RAI (MF6176 and MF6177)", dated September 3, 2015 (AE-NOC-15002702) (ML 15251A216)
: 4. Email from Lisa Regner, NRG, to Lance Sterling, STPNOC, "Draft NRG RAI: Integrated Leak Rate Testing LAR STP ILRT RAI (MF6176 and MF6177)", dated September 10, 2015 (AE-NOC-15002701) (ML 16048A426)
: 5. Letter from Lisa Regner, NRG, to Dennis Koehl, STPNOC, "South Texas Project, Units 1 and 2 -Request for Additional Information Related to a License Amendment Request to Extend the Containment Integrated Leak Rate Test Frequency (CAC Nos. MF6176 and MF6177)", dated March 1, 2016 (ML 16053A187)
By Reference 1, STP Nuclear Operating Company (STPNOC) submitted a License Amendment Request (LAR) for extending the 10 year Integrated Leak Rate Test (ILRT) to 15 years. Reference 2 is a supplement to the original submittal that added additional information regarding Probabilistic Risk Assessment topics. By Reference 3 and Reference 4, the NRG staff previously requested additional information (RAI) for their review of the STPNOC LAR. In Reference 5 the NRG has requested that STPNOC provide information regarding Nuclear Safety Advisory Letter (NSAL)-06-6, NSAL-11-5 and NSAL-14-2, and lnfoGram (IG)-14-1.
STPNOC's response to Reference 5 is provided in the Enclosure to this letter. There are no commitments in this letter. STI: 34285574 NOC-AE-16003347 Page 2 of 3 If there are any questions regarding the RAI responses, please contact Rafael Gonzales at (361) 972-4779.
I declare under penalty of perjury that the foregoing is correct. Executed on 17,
/ Date / vY Peter Nemeth Secretary and General Counsel rjg
 
==Enclosure:==
 
STPNOC Responses to the Request for Additional Information Regarding Units 1 and 2 License Amendment Request for Extending the 10 year ILRT to 15 years, Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2, and lnfoGram (IG)-14-1.
cc: (paper copy) Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511 Lisa M. Regner Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 8 G9A) 11555 Rockville Pike Rockville, MD 20852 NRC Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 (electronic copy) NOC-AE-1600334 7 Page 3 of 3 Morgan, Lewis & Beckius LLP Steve Frantz U.S. Nuclear Regulatory Commission Lisa M. Regner NRG South Texas LP Chris O'Hara Jim von Suski! Skip Zahn CPS Energy Kevin Pollo Cris Eugster L. D. Blaylock Crain Caton & James, P.C. Peter Nemeth City of Austin Elaina Ball John Wester Texas Dept. of State Health Services Richard A. Ratliff Robert Free NOC-AE-1600334 7 Enclosure STPNOC Responses to the Request for Additional Information Regarding Units 1 and 2 License Amendment Request for Extending the 10 year ILRT to 15 years, Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and 2, and lnfoGram (IG)-14-1.
NOC-AE-16003347 Enclosure Page 1 of 10 By letter dated April 29, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15128A352), as supplemented by letters dated June 29, October 8, and November 11, 2015 (ADAMS Accession Nos. ML 15198A147, ML 15293A509, and ML 15329A304, respectively), STP Nuclear Operating Company (the licensee) requested changes to the Technical Specifications for South Texas Project (STP), Units 1 and 2. The proposed change would permit the existing Containment Integrated Leak Rate Testing frequency to be extended from 1 O years to 15 years on a permanent basis. The U.S. Nuclear Regulatory Commission staff has reviewed the information provided in your application and determined that the following additional information is required to complete the review. SCVB RAI: The STP Updated Final Safety Analysis Report (UFSAR) Section 6.2.1.3, "Mass and Energy Release Analyses for Postulated Loss of Coolant Accidents," states the use of the Westinghouse WCAP-10325-P-A methodology for loss-of-coolant accident (LOCA) mass and energy release analysis.
Westinghouse Electric Company LLC (Westinghouse) has issued Nuclear Safety Advisory Letters (NSALs)-06-6, 5, and-14-2, and lnfoGram (IG)-14-1 to report errors in this methodology.
Also, a new methodology (GOTHIC) is used for the LOCA containment analysis for which the mass and energy input needs to be corrected based on the above NSALs and the lnfoGram.
The licensee indicated that the three Westinghouse NSALs were corrected and incorporated into the new LOCA containment analysis and the analysis results have been incorporated into the UFSAR. 1. Please describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis.
Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses.
Provide a brief description of the changes from the previous analysis result$. 2. The information provided in the IG-14-1 is generic. Please describe STP plant specific analysis/evaluations performed to determine the applicability of the errors reported in the lnfoGram to STP and its impact on the current analysis of record. STP Response to Question 1: The response to RAI question 1 is provided in the following three sections.
 
===1.1 Please===
describe any changes in inputs and assumptions in the reanalysis that could potentially reduce the conservatism in the previous analysis.
RESPONSE:
The containment pressure-temperature response for LOCA was performed in two parts. The first part developed the mass and energy release for use in the containment pressure-temperature response.
The second part calculated the containment pressure-tempe'rature response.
* NOC-AE-16003347 Enclosure Page 2 of 10 The new containment mass and energy release analysis was performed using the same methodology as the previous analysis.
The analysis was performed in accordance with the NRC-approved methodology in WCAP-10325-P-A.
The revised analysis incorporated the issues addressed in NSAL-06-6, NSAL-11-5 and NSAL-14-2.
The incorporation of these issues resulted in an increase in mass and energy releases and did not reduce the conservatism from the previous analysis.
The previous containment pressure-temperature response analysis used the CONTEMPT computer code. The new containment response analysis was performed with the GOTHIC computer code using the NRC-approved methodology documented in Dominion topical report DOM-NAF-3 (Reference 1 ). UFSAR Section 6.2.1.1.3.1 provides a description of the key models in the GOTHIC analysis (see UFSAR Change Notice 3136, Attachment to this Enclosure).
The following items used in the GOTHIC analysis are essentially the same as the items used in the CONTEMPT analysis:
* Containment model
* Containment initial conditions
* Heat sinks
* Reactor Containment Fan Cooler (RCFC) model
* Containment spray model,
* Refueling Water Storage Tank (RWST) model
* Sump recirculation model
* Heat exchanger model Two significant modeling changes were made when converting from the CONTEMPT to GOTHIC computer models. The first change replaced the Uchida/Tagami condensing heat transfer model with the Diffusion Layer Model (OLM) as discussed in Section 3.3.2 of Reference
: 1. A sensitivity study was performed using the limiting peak pressure case which is the Double-Ended Hot Leg (DEHL) break with minimum safety injection and minimum containment heat removal systems. Results of the study presented on Figure 1 below shows that the use of the GOTHIC OLM model resulted in a 2.7 psi increase in the peak pressure for the limiting case. The second change added the liquid/vapor interface model between the atmosphere and the sump. The CONTEMPT model used a constant heat transfer coefficient of 0.4 btu while the GOTHIC model used a split heat transfer option that switches the hr-ft2-QF heat transfer from the vapor phase to the liquid phase as discussed in Updated Final Safety Analysis Report (UFSAR) Table 6.2.1.1-9.
A separate sensitivity study was performed using the same limiting case discussed earlier. The results presented on Figure 2 below show that the change in the liquid/vapor model had a negligible change on the peak pressure.
NOC-AE-1600334 7 Enclosure Page 3of10 1.2 Please describe which UFSAR sections and figures contain the revised results of the LOCA mass and energy releases, containment pressure response, and Equipment Qualification pressure/temperature response analyses.
RESPONSE:
UFSAR Sections 6.2.1.1 and 6.2.1.3 discuss the LOCA containment response and mass and energy release analysis.
The mass and energy release data are presented in UFSAR Tables 6.2.1.3-4 to-18. The containment pressure/temperature responses are shown in UFSAR Figures 6.2.1.1-30 to-38. UFSAR Change Notice 3136 has been issued to reflect the revised analysis.
A copy of the incorporated change notice pages to the UFSAR have been included in the Attachment of this Enclosure.
Figures 3 and 4 below present the equipment qualification pressure/temperature response.
These figures are a composite of the peak pressures and temperatures from the LOCA and steam line break analyses.
 
===1.3. Provide===
a brief description of the changes from the previous analysis results. RESPONSE:
The combination of the increased mass and energy release and changes to the containment model for the limiting case (DEHL break with minimum safety injection and minimum containment heat removal) resulted in a change of the peak containment pressure from 39.5 psig to 40.1 psig. The peak containment temperature changed from 264°F to 262°F, and the peak containment sump temperature changed from 267°F to 274°F. STP Response to Question 2: IG-14-1 identified that the stainless steel volumetric heat capacity value that is used in the Westinghouse LOCA M&E release analysis methodology was identified as being lower than the current ASME Boiler and Pressure Vessel Code data. IG-14-1 concluded that the current Westinghouse LOCA M&E release methodology provides a conservative calculation of the energy release rate for input to containment calculations, the methodology has been proven to be overall conservative for containment integrity and downstream analyses, including EQ, and no further action on the part of the utility is required.
Additional discussions with Westinghouse identified that the stainless steel specific heat values used in the current analysis were approximately 20% lower than the current ASME Boiler and Pressure Vessel Code data. To assess the potential impact of the additional energy that could be released due to the higher specific heat values, a sensitivity study was performed.
The sensitivity study determined the amount of additional energy required to increase the calculated peak containment pressure to exceed the Technical Specification 6.8.3.j value of 41.2 psig (Pa). The results of the sensitivity study show that the energy released from the primary and secondary metal mass would have to increase by 46% before the Pa value of 41.2 psig was exceeded.
Since the 46% additional energy required to exceed the Pa limit is greater than the additional 20% energy that could be released due to the difference in the specific heat values, margin still exists to ensure that the Pa value will not be exceeded during a LOCA event.
Sensitivity Study Description NOC-AE-16003347 Enclosure Page 4of10 A summary of the LOCA containment pressure-temperature analysis is presented in UFSAR Section 6.2.1 as amended by Change Notice 3136 (see Attachment).
UFSAR Table 6.2.1.1-2 summarizes the results of the peak containment pressure analysis.
The DEHL break with minimum safety injection and minimum containment heat removal was chosen since it is the limiting case that determines Pa. UFSAR Figure 6.2.1.1-30 provides the containment pressure response versus time for the DEHL break with the minimum containment heat removal case. UFSAR Table 6.2.1.3-18 provides the energy balance for this case up to the end of blowdown.
UFSAR Table 6.2.1.1-1 O provides the accident chronology for this event. The sensitivity study calculated the additional energy from the metal mass that would be required to increase the peak containment pressure from 40.1 psig to 41.2 psig (Pa). The premise of the sensitivity study is that an increase in the specific heat of the stainless steel would proportionately increase the energy release from the primary and secondary metal. Therefore, if the specific heat were to double, the energy release from the primary and secondary metal mass metal would also double. The LOCA containment pressure-temperature analysis uses the mass and energy releases for the first 3600 seconds, with the sensible energy from the RCS and steam generators being transferred to the sump; after 3600 seconds, energy addition is by decay heat only. The GOTHIC model used for the design basis analysis was modified to add a multiplier to the energy release for the duration of the mass and energy releases to determine the energy required to increase the calculated peak pressure from 40.1 to 41.2 psig. The resulting pressure versus time is provided on Figure 5 which shows that the first peak is limiting.
The results of the analysis show that a factor of 1.02 is required to raise the calculated peak pressure to 41.2 psig. UFSAR Table 6.2.1.3-18 shows that the total energy release to containment (Total Effluent) is 410.27 MBTU. So the additional energy added to containment.
during the blowdown phase is 8.2 MBTU (0.02 X 410.27 MBTU). The energy balance on UFSAR Table 6.2.1.3-18 shows that the energy contributed to the energy release by the primary metal (204.93-192.02 MBTU) and secondary metal (161.72-156.81 MBTU) during the blowdown phase is 17 .82 MBTU for the current analysis.
The additional energy from the primary and secondary metal would have to increase by a factor 46%
100), which is greater than the additional 20% energy that could be provided by the differences in the specific heat values.
NOC-AE-16003347 Enclosure Page 5of10 Figures 1-5 Hi Figure 1 Containment Pressure (psia) with Uchida/Tagami Heat Transfer Coefficient (HTC) PR1 DC68T i i ,... : ! /
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...____.__._......_._u..i.i 0.1 10 100 1000 1e+004 Time (sec) GOTHIC 8.0 QA Mar/07/2016 11 :09:45 PRl Containment Pressure (psia) with Uchida/Tagami Heat Transfer Coefficient (HTC) DC68T Double-Ended Hot Leg Break Minimum Safety Injection, Minimum Containment Heat Removal System (Can be compared with UFSAR Figure 6.2.1.1-30)
Figure 2 NOC-AE-16003347 Enclosure Page 6of10 Containment Pressure (psia) with No SPLIT or Liquid/Vapor Interface heat transfer 111 PR1 DC68T 0----
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u..u.....___._..L...J....J..U.J1UJe+oo4 Tfme (sec) GOTHIC 8.0 QA Mar/07/2016 11 :51 :4.6 PRl Containment Pressure (psia) with No SPLIT or Liquid/Vapor Interface heat transfer DC68T Double-Ended Hot Leg Break Minimum Safety Injection, Minimum Containment Heat Removal System (Can be compared with UFSAR Figure 6.2.1.1-30)
Figure 3 NOC-AE-16003347 Enclosure Page 7of10 Peak Pressure Composite for Equipment Qualification .. .e: I!! :I .. "' Q) .. a. Peak Containment Pressure Composite 70 1111 EQ Pressure Profile 60 50 40 30 20
----10 0 0.1 I I I / ,,. .... / _,.. .... .... I I / I *' ,, -EQ Pressure Profie --LOCA Pr Composite
,..._ r-----* MSLB Pr Compostte
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LOCA Pressure I I 10 100 1000 10000 100000 Time (seconds) 1000.000 360 340 320 300 280 260 GI s 240 f! GI
::. 200 180 160 140 Figure 4 NOC-AE-16003347 Enclosure Page 8of10 Peak Temperature Composite for Equipment Qualification Peak Containment Temperature Composite 1111 -EO Temperature Profile I I I 111111 I I -EQ Temperature Profile ----LOCA Tv Composite
-.... ' ----MSLB Tv Composite
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1 e+004 Time (sec) GOTHIC.8.0 QA Mar/07/201610:14:54 PRl Containment Pressure (psia) with Energy Multiplier of 1.02 (2%) DC68T Double-Ended Hot Leg Break Minimum Safety Injection, Minimum Containment Heat Removal System (Can be compared with UFSAR Figure 6.2.1.1-30)
References NOC-AE-16003347 Enclosure Page 10of10 1. ML063190467, Dominion, Approved Topical Report DOM-NAF-3 NP-A, GOTHIC Methodology for Analyzing the Response to Postulated Pipe Ruptures Inside Containment, November 16, 2006.
 
==Attachment:==
: 1. Incorporated UFSAR Change Notice 3136 Incorporated UFSAR Change Notice 3136 NOC-AE-16003347 Enclosure Attachment
_Table 6.1-1 6.1-3 6.1-4 6.2.1.1-1 6.2.1.1-2
 
6.2.1.1-3 6.2. 1.1-4 6.2.1.1-5 6.2.l.1-7 6.2.1.1-8 6.2.1.1-9 6.2.1.1-10 6.2.1.1-14 6.2.1.1-15 6.2.1.2-1 (Item G) 6.2.1.2-1 (Item J) 6.2.1.2-1 (Item K) 6.2.1.2-1 (Item L) 6.2.1.2-1 (Item M) _6.2.1.2-1 (Item N) NOC-AE-16003347 Enclosure Attachment Page 1 of 77 LIST OF TABLES CHAPTER6 Title Engineered Safety Features Materials Protective Coatings on Westinghouse-Supplied Equipment Inside Containment Coating Schedule for Surfaces Inside Containment (Excluding NSSS Scope of Supply) Containment Design Accidents DBA Calculated Pressure,s in Containment Containment Data Used in PIT Analysis Not Used Engineered Safety Features System Information Modeling of Structural Heat Sinks for Containment Analyses Thermophysical Properties of Structural Heat Sink Materials for Containment Analysis Containment Heat Sink Surface Heat Transfer Model Accident Chronology for DBA LOCA Summary of Containment MSLB PIT Analysis Results Accident Chronology for DBA MSLB (Peak Temperature Case) Short-Term Mass and Energy Release Rates forSubcompartment Analyses for Pressurizer Spray Line DEG Break Short-Term Mass and Energy Release Rates for Subcompartment Analyses for MSLB Short-Term Mass and Energy Release Rates for Subcompartment Analyses for Main Feedwater Line Break Short-Term Mass and Energy Release Rates for Subcompartment Page 6.1-7 6.1-11 6.1-12 6.2-56 6.2-58 6.2-59 6.2-61 6.2-62 6.2-65 6.2-66 6.2-67 6.2-68 6.2-70 6.2-72 6.2-82 6.2-83 Analyses for CVCS Letdown Line Break -Radioactive Pipe 6.2-85 Chase Subcompartment Blowdown Short-Term Mass and Energy Release Rates for Subcompartment Analyses for CVCS Letdown Line Break -RHR lA Valve 6.2-86 Room Subcompartment Analyses Short-Term Mass and Energy Release Rates for Subcompartment 6.2-88 Analyses for CVCS Letdown Line Break -Regenerative Heat Exchanger Subcompartment Blowdown 6.2.1.2-1 (Item P) Short-Term Mass and Energy Release Rates for Subcompartment Analysis for RHR: 12" Line DEG 6.2-89 6.2.1.2-1 (Item Q) Short-Term Mass and Energy Release Rates fQL. _____________
_ Subcompartment Analysis for FW 16" DEG Break at SG Nozzle 6.2-97 Connection, HFP, FW @ 460 °F TC6-3 Revision 18 Table 6.2.l.2-5A 6.2.1.2-SB 6.2.1.2-6 6.2.l.2-6A 6.2.1.2-7A 6.2.1.2-7B 6.2.1.2-7C 6.2.1.2-7D 6.2.L2-8A 6.2.1.2-8B 6.2.1.2-9 6.2.1.2-13 6.2.1.2-14 6.2.1.2-15 LIST OF TABLES (Continued)
CHAPTER6 Steam Generator Loop Compartment Peak Pressure Summary for RlIR. Line Break Analysis Steam Generator Loop Compartment Peak Pressure Summary for FWLB Analysis Steam Generator Loop Compartment Pressure -Junction Properties for RHR/SI Analysis ( 42-Node Model) Steam Generator Loop Compartment Pressure Analysis -Junction Properties for FWLB Analysis.
Steam Generator Loop Compartment Analysis -Force Coefficient (Area Projections) for Steam Generator Subjected to RHR Line Break Steam Generator Loop Compartment Analysis -Moment Coefficient (Area Projections) for Steam Generator Subjected to RHR Line Break Steam Generator Loop Compartment Analysis -Force Coefficient (Area Projections) for Steam Generator Subjected to FWLB Steam Generator Loop Compartment Analysis -Moment Coefficient (Area Projections) for Steam Generator Subjected to FWLB Steam Generator Loop Compartment Analysis -Force Coefficient (Area Projections) for Reactor Coolant Pump Subjected to RlIR. Line Break Steam Generator Loop Compartment Analysis -Moment Coefficient (Area Projections) for Reactor Coolant Pump Subjected to RHR Line Break
* Pressurizer Subcompartment Analysis Spray Line Break NOC-AE-16003347 Enclosure Attachment Page 2 of77 6.2-94 6.2-96 6.2-98 6.2-102 6.2-104 6.2-105 6.2-106 6.2-107 6.2-108 6.2-109 6.2-110 Main .Steam Line and Feedwater Line Subcompartment Analysis Main Steam Line and Feedwater Subcompartment 6.2-111 Analysis Junction Description
-Steam Line Break Analysis Regenerative Heat Exchanger Subcompartment Nodal Description TC6-4 \ 6.2-112 6.2-113 Revision 18 Table 6.2.1.2-16 6.2.1.2-17 6.2.1.2-18 6.2 .. 1.2-19 6.2.1.2-20 6.2.1.3-1 6.2.1.3-2 6.2.1.3-3 6.2.1.3-4 6.2.1.3-5A 6.2.1.3-5B 6.2.1.3-6 6.2.1.3-6A 6.2.1.3-7 6.2.1.3-8
 
6.2.1.3-9 6.2.1.3-10 6.2.1.3-11 6.2.1.3-12 . 6.2.1.3-13 6.2.1.3-14 6.2.1.3-15 6.2.1.3-16 6.2.1.3-17 6.2.1.3-18 6.2.1.4-1 STPEGS UFSAR LIST OF TABLES (Continued)
CHAPTER6 Regenerative Heat Exchanger Subcompartment Junction Description Radioactive Pipe Chase Subcompartment Nodal Description Radioactive Pipe Chase Subcompartment Junction Description RHRlA Valve Room Subcompartment Nodal Description RHRlA Valve Room Subcompartment Junction Description System Parameter Initial Conditions LOCA -Total Pumped ECCS Flow Rate for Two Trains of SI Operating LOCA -Total Pumped ECCS Flow Rate for Three Trains of SI Operating Double-Ended Hot Let Break Blowdown Mass and Energy Releases Double-Ended Pump Suction Break Mass and Energy Releases (Minimum SI) Double-Ended Pump Suction Break Mass and Energy Releases (Maximum SI) Decay Heat Data Based on ANS-51.1-1979 Plus 2 Sigma Uncertainty Decay Heat Based on Standard Review Plan ASB 9-2 Correlations Not Used Not Used NOC-AE-16003347 Enclosure Attachment Page 3 of77 6.2-114 6.2-115 6.2-116 6.2-117 6.2-118 6.2-119 6.2-120 6.2-121 6.2-122 6.2-125 6.2-132 6.2-141 6.2-142 Double-Ended Pump Suction Break Principal Parameters During Reflood (Minimum SI) 6.2-144 Double-Ended Pump Suction Break Principal Parameters During Reflood (Maximum SI) Not Used Not Used Double-Ended Pump Suction Break Mass Balance (Minimum SI) Double-Ended Pump Suction Break Mass Balance (Maximum SI) Double-Ended Hot Let Break Mass Balance Double-Ended Pump Suction Break Energy Balance (Minimum SI) Double-Ended Pump Suction Break Energy Balance (Maximum SI) Double-Ended Hot Leg Break Energy Balance Mass and Energy Release Rates for Main Steam Line Break -1.4 ft2 Double-Ended Rupture at 30% Power (MSIV Failure) 6.2-145 6.2-146 6.2-147 6.2-148 6.2-149 6.2-150 6.2-151 6.2-152 TC6-5 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 4 of77 conservative set of assumptions that maximize the heat removal effectiveness of ESF systems, structural heat sinks, and other potential heat removal processes.
The assumptions are discussed in Section 6.2.1.5. 6.2.1..1.2 Design Features:
Design features of the Contairunent and its internal structures are described in Sections 3.8.i" and 3.8.3, respectively.
6.2.1.1.2.1 Protection from the Dynamic Effects of Postulated Accidents
-The Containment structure, subcompartments, and ESF systems safety functions are protected from loss due to the dynamic effects of postulated accidents.
Contairunent design provides separation, barriers, or restraints as required to protect essential structures, systems, and components from accident-generated missiles, pipe whip, and jet impingement forces. Detailed criteria, locations, and descriptions of devices used for protection are given in Sections 3.5 and 3.6. 6.2.1.1.2.2 Codes and Standards
-Codes and standards applied to the design, fabrication, and erection of the Containment and internal structures are given in Sections 3.8.1 and 3.8.3. In each case, the codes and standards used are consistent with equipment safety function.
6.2.1.1.2.3 Protection Against External Pressure Loads'-No special provisions are required for protection against loss of Containment under external loacling conditions.
Inadvertent operation of CHRS and other possible modes of plant operation (e.g., Containment purging) that could potentially result in significant external structural loading, have resulted in pressure differentials lower than the design Containment pressure differential for external loading. Details of this evaluation are provided in Section 6.2.1.1.3
.. 6. 6.2.1.1.2.4 Potential Water Traps Inside the Containment-Drains from potential water traps discharge into the Containment sump. All significant water traps are thereby eliminated.
6.2.1.1.2.5 Containment Cooling and Ventilation Systems-During normal reactor operation, Containment atmosphere is maintained at or below the Technical Specification limit by continuous operation of the RCFC system. This system is describe,d in detail in Section 6.2.2.2. 6.2.1.L3 Design Evaluation:
6.2.1.1.3.1 Containment Pressure and Temperature Analysis -In the event of a postulated LOCA, MSLB, or main feedwater line break (FWLB), mass and energy will be released from the rupture and high-temperature, high-pressure fluid will flash to steam. This release of mass and energy raises Containment atmosphere pressure and temperature.
The magnitude of the resulting pressure and temperature peaks is a function of the nature, location, and size of the postulated rupture. To establish the controlling ruptute for Containment design, a range of primary and secondary breaks, as described in Table 6.2.1.1-1, was analyzed to determine the effect of each break on Containment.
The LOCA analysis is discussed in Section 6.2.1.3. The MSLB analysis is discussed in Section 6.2.1.4. As discussed in Section 6.2.1.4, the FWLB does not produce peak Containment pressure or temperature as severe as LOCA or MSLB cases. Therefore, the FWLB cases are not analyzed.
6.2-3 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 5 of77-The Containment analysis is performed in two stages. In the first stage, the mass and energy release is calculated for a spectrum of breaks (double-ended pump suction, DEPS; double-ended hot leg, DEHL; and double-ended and split break MSLBs). The mass and energy release models and break sizes are described in Section 6.2.1.3 (LOCA) and 6.2. 1.4 (MSLB). In the second stage, the mass and energy releases are used in the Containment rulalysis model for calculating the peak pressure and temperature.
The Containment analysis model is described below. (a) Contairunent Model The containment pressure and temperature transients are analyzed py using the GOTHIC code (References 6.2.1.1-11and6.2.1.1-13).
GOTHIC is an integrated, general purpose thennal hydraulics software for design, licensing, safety and operating analysis of nuclear power plant containments, confinement buildings and system components.
Applications of GOTHIC include evaluation of containment and sub-compartment response to the full .spectrum of high energy line breaks within the design basis envelope and systems evaluations involving multiphase flow and heat transfer, gas mixing and other thermal hydraulic behavior.
The LOCA and MSLB analyses use a single volµme (node) for the containment building with separate treatment given to the sump and containment atmosphere regions. Inherent in this lumped parameter approach is the assumption that within each region the fluid is well mixed. During a LOCA or MSLB, the mixing induced by the break jet is significant.
Later in the transient, containment sprays and/or reactor containment fan coolers (RCFCs) continue to promote mixing in the containment. (b) Containment Initial Conditions To determine the maximum containment pressure and temperature, the most resti;icting Containment normal operating pressure and temperature are assumed to be at the Technical Specification operating limit and. the outside atmosphere temperature is assumed to be at design maximum value. The initial conditions for the limiting Containment peak pressure case are given in Table 6.2.1.1-3.
For Containment LOCA peak pressure analysis, the Safety Injection System (SIS) and the CHRS (i.e., CSS and RCFC) are assumed to operate in the mode that maximizes Containment peak Pressure.
The initial conditions are listed in Table 6.2.1.1-5.
For calculating the Containment peak pressure, the minimum CHRS capacity is the conservative condition.
Thus, the CHRS equipment were assumed to be affected by the most restrictive single active failure, which is the loss of one SDG train coupled with one RCFC unit being out of sel'vice for maintenance.
The analyses show that a sustained loss of one safety-related electrical
* distribution train (i.e., one SDG) will minimize ESF response and maximize Contaimnent pressures.
The LOCA analysis gives the highest pressure, and the analysis is discussed in Section 6.2-4 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 6 of77 For Containment peak temperature analysis (due to MSLB }, a spectrum of single active failures and break sizes were considered.
The MSLBanalysis is discussed in Section 6.2.1.4. \ ( c) Mass and Energy Releases For LOCA, the mass and energy release analysis is discussed in Section 6.2.1.3. For MSLB, the mass and energy release analysis is discussed in Section 6.2. 1.4. (d) Heat Sinks (Thermal Conductors)
Containment structures are one of the major passive heat sinks for energy removal and are modeled as thermal conductors.
The thermal conductors are made of up a number oflayers of different materials.
The thermal conductors are divided into regions, one for each material layer, with an appropriate thiclmess and material thermos-physical properties for each region. One-. dimensional heat conduction solutions are used. The small air gap orcontactresistance between the containment liner and the concrete is modeled as a separate material layer at the nominal gap thickness with applicable material properties.
This approach conservatively overestimates the contact resistance because convection and radiation effects will be ignored. Concrete, Metal, and protective coating properties are typical values for the temperature range observed in the analyses.
Table 6.2-. 1.1-7 gives a summary of containment structural heat sinks used in the analysis.
Thermo-physical properties of these heat sinks are listed in Table 6.2.1.1-8. ( e) Passive Heat Sink Heat Transfer Coefficients The GOTHIC Direct heat transfer option with the DLM (Diffusion Layer Model) condensation option is used for all containment passive heat sinks except the sump floor. With the Direct option, all condensate goes directly to the liquid pool at the bottom of the volume. The effects of the condensate film on the heat and mass transfer are incorporated in the formulation of the DLM option. Under the DLM option, the condensation rate is calculated using a heat and mass transfer analogy to account for the presence of noncondensing gases. For a conductor representing the containment floor or sump walls that will eventually be covered with water from the break and condensate, the Split heat transfer.fa used to switch the heat transfer from* the vapor phase to the liquid phase as the liquid level in the containment builds up. For conductors with both sides exposed to the containment, the Direct heat transfer with DLM option is applied to both sides. If the conductor is symmetric about the center plane, a half thickness conductor is used with the total surface area of two sides and an insulated back side heat transfer option is used. The conductor face that is not exposed to the atmosphere is assumed insulated.
For the insulated side, the Specified Heat Flux option is used with the nominal heat flux set to zero. 6.2-5 Revision 18 STPEGS UFSAR NOC-AE-1600334 7 Enclosure Attachment Page 7 of77 Containment walls above grade and the contaimnent dome have a specified external temperature boundary condition with a heat transfer coefficient of 2.0 Btu/hr-ft 2-°F to model convective heat transfer to the outside atmosphere.
Surface heat transfer coefficients used in the analysis for LOCA and MSLB cases are shovm in Table 6.2.1.1-9. (f) RCFC Model. The reactor containment fan coolers (RCFCs} arc modeled by specifying input values using heat removal rate versus Containment atmosphere saturation temperature curve. This performance curve is based on the cooling coil design data including fouling and is shown in Figure 6.2.1.5-2.
Start times are based on SDG start time, loading sequencing time, and startup time for the various ESP systems. The start times are provided in Table 6.2.1.1-10 and the RCFC parameters are given in Table 6.2.1.1-5. , (g) Containment Spray Model For the contaimnent spray system (CSS), spray water is taken from the RWST during the injection phase and the liquid region of the containment eluting the stm1p recirculation phase. The spray flow is added directly to the containment vapor space. The analysis uses the general modeling practices for spray nozzles, spray pumps, spray system delivery times including pipirig fill time and pump start delays. The model calculates the sensible heat transfer between the spray drops and vapor and evaporation or condensation at the drop surface. (h) RWST Model The refueling water storage tank (R WST) liquid volume is used to detennine a reasonable prediction of inventory draw down for determining the time of transfer to the sump recirculation phase. The RWST parameters are shown in Table 6.2.1.1-3. (i) Sump Recirculation Model The sump recirculation phase starts after depletion of the RWST liquid inventory.
At the time of transfer to the sump recirculation phase, the safety injection system (HHSI and LHSI) and containment sprays* swap suction from the RWST to the contaimnent sump. During this phase, the LHSI is cooled by the RHR heat exchanger.
The HHSI and CSS flows are not cooled. Two* LHSI-RHR heat exchanger train combination are used to cool the recirculation flow to the RCS during the post-SG depressurizations phase (after 3600 seconds).
: 0) Heat Exchanger Model The RHR exchanger is modeled using the GOTIHC HEAT EXCHANGER option. Fouling factors and tube ph1gging are applied for conservatism . . 6.2-6 Revision 18 l :1 i :I 'I j i I I I !I STPEGS UFSAR 6.2.1.1.3.2 Long-Term Containment Performance NOC-AE-1600334 7 Enclosure Attachment Page 8 of77 The results of the most severe cases for primary and secondary side breaks were evaluated to verify the ability of the CHRS to maintain Containment conditions within design limits. These evaluations were based.upon conservative assumptions for ESF equipment performance.
The minimum CHRS operation was *based on loss'' of offsite power (LOOP) with one SDG failure. Thus, only two of three CHRS trains minus one additional RCFC tmit out for maintenance were assumed in the analysis.
During the sump recirculation phase, two LHSI-RHR.
heat exchanger train combination are used to cool therecirculation flow to the RCS. The containment sprays are not cooled by any' heat exchanger.
Hot leg recirculation is not considered since it has no significant impact on Containment analysis results. The .spectrum of accidents postulated for determining the Containment peak pressure and temperature, subcompartment peak pressure, and external pressure is summarized in Table 6 .2.1.1-1.
The calculated peak maximum pressure, design pressure, and margin between the calculated peak and design pressures are given in Table 6.2.1.1-2.
Containment parameters used in the analysis are given in Table 6.2.1.1-3.
For LOCA, the scenarios analyzed are the double-ended pump section (DEPS) and the ended hot leg (DEHL) breaks coincident with LOOP. These analyses were performed with both minimum safety injection (SI) and maxim.um SL The minimmn SI case includes flow from two SI trains (LHSI + HHSI). The maximum SI case includes flow from all three SI trains. For the analyzed LOCA cases, the pipe break locations, brealc areas, peak pressures and temperatures are smnmarized in Table 6.2.1.1-2.
Based on the results, the DEHL break provided the highest peak Containment pressme. For long-term analysis, all analyzed cases have similar pressure and temperature profiles.
A summary of the peak containment LOCA pressmes and temperatures is given in Table. 6.2.1.1-2. Figures 6.2.1.1-30 to 6.2.1.1-38 show the results of two representative LOCA analyses.
The long-term analysis shows that the Containment pressure is reduced below 50 percent of the pealc . calculated pressure within 24 hours. For MSLB, several double-ended and split break cases were analyzed at different power levels and different single-active failures.
A smnmary of the peak containment MSLB pressures and temperatures is given in Table 6.2.1.1-14.
The highest temperature occurs for a double-ended MSLB where no entrainment is included in the mass and energy releases (discussed in Section 6.2.1.4).
This is conservative since the Containment response to a mass and energy release with entrainment effects would result in lower temperatures at or near the saturated conditions.
Figures 6.2.1.1-25, 6.2.1.1-28 and 6.2.1.1-29 show plots of various parameters for the most limiting MSLB temperature case. 6.2.1.1.3.3 Accident Chronology -The accident chronology fo1' the most severe RCS break (LOCA) is provided in Table 6.2.1.1-10.
The chronology for the design basis MSLB is shown in Table 6.2.1.1-15.
6.2-7 Revision 18 ,.
STPEGS UFSAR NOC-AE-1600334 7 Enclosure Attachment Page 9 of77 Section 3.6.2. As discussed in Reference 3.6-14 and Section 3.6.2.1.1.1, item a, RCL ruptures and the associated dynamic effects are not included in the design bases. The accident that results in the maximum differential pressure across the walls of the respective compartment is designated as the subcompartment design basis. Calculated differential pressures are compared to the design pressure values used in the structural design of subcompartment walls and equipment to ensure that peak calculated values are less than design values. These design and calculated pressure differentials are presented under each subcompartment section below. 6.2.1.2.2 Design Features:
*6.2.1.2.2.1 Reactor Cavity -The reactor cavity is a heavily reinforced concrete structure that perforins the dual function of providing reactor vessel support and radiation shielding.
It is described in Section 3.8.3.1 and is shown in the general arrangement drawings listed in Table 1.2-1. At the elevation of the primary piping nozzles, the reactor vessel is surrounded by an inspection toroid. No pipe ruptures are postulated in the reactor cavity or inspection toroid. 6.2.1.2.2.2 Steam Generator Compartments -The SG and its supports have been described in Section 3."8.3.1, and the general arrangement of the SG and associated structural arrangement are listed as Figures 1.2-13 through 1.2-20 in Table 1.2-1. These general arrangement drawings have been used to define nodal boundaries.
The SG subcompartments consist of the entire free volume between the primary shield and the secondary shield walls and from El. 19 ft to 83 ft. Each quadrant o vents to the contairunent at the top of the SG compartment.
See Tables 6.2. l .2-5A, 6.2.1.2-5B, and 6.2.1.2.-6B for nodal volume and junction properties.
In addition to the above vent path, two more vent paths vent the break nodes to the Containment.
These are (a) the eight penetration paths that lead the hot and cold leg pipes to the reactor cavity and (b) the six heating, ventilation, and conditioning (HVAC) vents between the SG compartments above El. 19 ft and subpedestal region below EL 16 ft. Steam generator compaiiments A and D, and B and Care directly connected together while A and B, and C and Dare connected via a passage. No blowout panels are used, thus the flow area is assumed to be constant with respect to time. Some junctions are considered partially blocked by debris. 6.2.1.2.2.3 Pressurizer Compaiiment-The pressurizer subcompartment, shown in the general arrangement drawings listed in Table 1.2-1, consists of a vertical, rectangular, reinforced concrete structure surrounding the pressurizer which is supported at its base by a steel skirt. No blowout panels are used, thus the flow area is assumed to be constant with respect to time. 6.2.1.2.2.4 Surge Line Subcompartment-The surge line subcompartment consists of the area above the grating at EI. 37 ft-3 in., the area below El. 37 ft-3 in., and the vestibule where the surge line penetrates the secondary shield wall. These subcompartments are shown in the general arrangement drawings listed in Table 1.2-L See Section 6.2.1.2.3
.5 for elimination of surge line breaks due to leak-before-break.
6.2.1.2.2.5 Main Steam Line and Feedwater Line Subcompartments -The main steam line and feedwater line subcompartments are located between the secondaty shield wall and the Containment wall. The general arrangement drawings listed in Table 1.2-1 show the equipment and struchll'es in these locations.
The most confined spaces resulting in maximum local pressures from either break are near the pipe penetrations to the outside of the Containment.
Vent paths consist of a combination of series and parallel flow resistances joining major elevations of approximately Revision 18 STPEGS UFSAR RHR Line Break NOC-AE-16003347 Enclosure Attachment Page 10 of77 Double-ended ruptures of the RBR piping were assumed to occur between the hot leg piping and the first isolation valve in the 12" section of the RBR piping. The remainder of the RBR piping is not modeled because of break exclusion due to Arbitrary Intermediate Break (Ref. 6.2.1.2-10).
The mass and energy release rates from the isolated piping section was calculated using RETRAN-02 computer code. The mass and energy release rates for the RCS side of the break was calculated using the methodology from Reference 6.2.1.2-5.
The total mass and energy releases for the double-ended Q rupture are shown in Table 6.2.1.2-lP.
These releases are based on an initial RCS pressure of2,296 psia and a hot leg temperature of 629.9°F. Three break cases were investigated.
These were a break in Node 15 (at the hot leg junction), a break in Node 4 (at the first valve upstream of the RCS), and a break in Node 12 (at the hot leg junction, but artificially moved to the opposite side of the hot leg). The Node 12 break was modeled to conservatively envelop the results of the 8" Safety Injection line break case. The COMP ARE computer code (Ref. 6.2.1.2-9) was used to perform the SG subcompartment 2 pressurization analysis.
The nodalization of the SG subcompartment is shown on Figure 6.2.1.2-J and 6.2.1.2-11.
The node and junctiori.
parameters for the SG loop compartment are given on °' Table 6.2.1.2-6.
The flow parameters were evaluated to account for all obstmctions such as cable tray supports and various small-sized piping. The principal obstructions within the SG loop compartments are the SG and reactor coolant pumps. The flow from one node to the other was calculated using the homogeneous equilibrium model option for the analysis.
The peak differential pressures for each subcompartment are listed in Table 6.2.1.2-5A.
The pressure differential given on Table 6.2.l.2-5A is generally evaluated with respect to the containment (Node 41.) The pressure-time histories for all cases are presented in Figure 6.2.1.2-20A to -20C. These nodes are in the SG compartment in which the RHR breaks occur. Force and moment coefficients on the SG and reactor coolant pump have been evaluated to help facilitate determination of forces and moments due to the pressures generated by the analyzed breaks. Force coefficients represent the projections of the SG and RCP on three mutually perpendicular planes selected for this purpose (Figure 6.2.1.2-30}.
For the steam generator loop "C" compartment, the positive "Z" direction is north, the positive "X" direction is west, the positive "Y" direction is vertically up. The origin for the steam generator at the bottom center ofthe SG while the origin for the reactor coolant pump is at the bottom center of the reactor* coolant pump. Moment coefficients represent the force coefficients multiplied by the moment arm from the base of the steam generator or reactor coolant pump to the centers of the projected areas used in the development of the force coefficients.
The force and moment coefficients are presented in Table 6.2.1.2-7 A, -7B, -8A and -8B for the SG and RCP. The forces and moments plots versus time for the SG and the RCP are presented on Figures 6.2.1.2-2 lA and 6.2. l .2-22A for the specific break cases identified on the figures. Feedwater Line Break Analysis 6.2-12 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 11 of 77 addition, the reservoir of reverse flow is limited since high energy fluid conditions extend only to the letdown heat exchanger.
' 6.2.1.2.3.8 Radioactive Pipe Chase Subcompartment-A double-ended rupture of the CVCS letdown line is the limiting break in the radioactive pipe chase subcompartment.
See Figure 6 .2.1.2-8 for a detailed drawing of the area. A node and junction diagram is illustrated on Figure 6.2.1.2-16.
The flow model initial conditions, control volumes, inter-compartment flow paths, and corresponding flow coefficients and inertial terms are listed in Tables 6.2.1.2-17 and 6.2.1.2-18.
The calculated subcompartment pressure response is shown on Figure 6.2.1.2-28.
The calculated and design pressures are compared in Table 6.2.1.2-17.
The blowdown rate for the eves letdown line break is calculated using ANSI 58:2, Appendix E2 methodology and applying that to a dimensional Benry-Fauske model for saturated liquid. Mass and energy release rates are given in Table 6.2.1.2-lL (refer to Section 6.2.1.2.3.1 for more details).
Plant operation is assumed to be in the heatup mode. The break is assumed to occur at the Containment penetration.
The break area is 0.0884 ft 2 for each end of double-ended break (0.1768 ft 2 total area). A significant restriction to forwai*d flow is the eves letdown orifices (0.00166 ft2) located immediately downstream of the regenerative heat exchanger.
For reverse flow, the letdown heat exchanger reduces the line temperature to l 15°F and a pressure reducing valve immediately downstream of the letdown heat exchanger reduces the line pressure to 300 psig, thereby limiting the reservoir of high energy fluid downstream of the break. 6.2.1.2.3.9 RHR Valve Room Subcompartment-A double-ended rupture of the eves letdown line is the limiting break in the RHR lA and RHR lB valve rooms. See Figure 6.2.1.2-9 for a detailed drawing of the area. Because the valve rooms are identical, a break was analyzed for the RHR lA valve room. The results are representative for both valve rooms. A node and junction diagram is shown on Figure 6.2.1.2-17.
The nodal model initial conditions, control volumes, vent areas, and co11'esponding flow coefficients and inertial terms are listed in Table 6.2.1.2-19 and 6 .2.1.2-20.
The calculated subcompartment pressure response is shown on Figure 6 .2 .1.2-29. Calculated and design pressures are compared in Table 6.2.1.2-19.
The blowdown rate for the CVCS letdown line break is calculated using ANSI 58.2, Appendix E2 methodology and applying that to a one-dimensional Henry-Fauske model for saturated liquid (refer to Section 6.2.1.2.3 J for more details).
Mass and energy release rates are given in Table 6.2.1.2-lM.
Plant operation is assumed to be in the heatup mode. The break is assumed to occur at the penetration of the valve room wall. The break area is 0.0884 ft 2 for each end of the double-ended break (0.1768 ft 2 total area). Significant restrictions to forward flow are the eves letdown orifices (0.00166 ft 2) located immediately downstream of the regenerative heat exchanger.
For reverse flow, the letdown heat exchanger reduces the line temperature to l 15°F and the pressure reducing valve, hmnediately downstream of the letdown heat exchanger, reduces the line pressme to 300 psig, thereby limiting the reservoir of high energy fluid downstream of the break. 6.2.l.3 Mass and Energy Release Analyses For Postulated Loss of Coolant Accidents.
6.2.1.3. l Loss of Coolant Accident Mass and Energy Release Phases: The containment receives mass and energy releases following a postulated rupture of the RCS. These releases continue through blowdown and post-blowdown phases. 6.2-15 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 12 of77 The LOCA transient is divided into the following:
(1) Blowdown -which includes the period from accident initiation (when the reactor is at steady state operation) to the time that the RCS pressure reaches initial equilibrium with contaimnent.
(2) (3) Refill -the period of time when the fower plenum is being filled by accmnulator and ECCS water. At the end ofblowdown, a large amount of water remains in the cold legs, downcomer, and lower plenum. To conservatively consider the refill period for the purpose of containment mass and energy releases, this water is instantaneously transferred to the lower plenum along with sufficient accumulator water to completely fill the lowerplenum.
This allows an uninterrupted release of mass and energy to containment.
Thus, the refill period is conservatively neglected in the mass and energy release calculation.
Reflood -begins when the water from the lower plenum enters the core and ends when the core is completely quenched.
(4) Post-reflood
-*describes the period following the end ofreflood up to the time the steam generators are depressurized to atmospheric pressure at 3600 seconds. The post-reflood mass and energy releases follow the NRC-approved methodology of WCAP-10325 P-A (Ref. 6.2.1.3-1).
(5) Post-SG Depressurization-After 3600 seconds; the mass and energy release using the revised post-recirculation:
methodology is used. The mass and release calculation during this long-*term phase of the transient use the NRC approved methodology discussed in Reference 6.2.1.3-6.
This methodology is summarized in Section 6.2.1.3.4.5.
6.2.1.3.2 Break Size and Location:
Generic studies have been performed with respect to the effect on the LOCA mass and energy releases relative to postulated break size. The double-ended guillotine break has been found to be limiting due to larger mass flow rates during the blowdown phase of the transient.
During the reflood and froth phases, the break size has little effect on the releases.
Three distinct locations in the reactor coolant system loop can be postulated for pipe
-Hot leg (between vessel and steam generator)
-Cold leg (between pump and vessel) -Pump suction (between steam generator and pump) The breaks analyzed are the *double-ended hot (DEHL) guillotine break (9 .18 ft 2) and the fi double-ended pump suction guillotine (DEPS) break (10.48 ft2). Pump suction break releases have been calculated for the blowdown, reflood, and post-reflood phases of the LOCA. The following
°' information provides a discussion on each bteak location.
The DEHL guillotine break has been shown in previous studies to result in the highest blowdown mass and energy release rates. Although the core flooding rate would be highest for this break location, the amount of energy released from the steam generator secondary side is minimal because the majority of the fluid which exits the core bypasses the steam generators in venting to containment.
As a result, the reflood mass and energy releases are reduced significantly as compared 6.2-16 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 13 of77 to either the pump suction or cold leg break locations where the core exit mixture must pass through the steam generators before venting through the break. For the hot leg break, there is no reflood peak as determined by generic studies, i.e., from the end of the blowdown period the releases would continually decrease.
Therefore, the reflood and subsequent post-reflood releases are not calculated for a hot leg break. For the DEHL analysis, the DEPS mass and energy releases for the post-blowdown period were used. As discussed below for the DEPS. break, this assumption results in the highest release rates. The cold leg break (DECL) location has been found in previous studies to be much less limiting in terms of the overall containment peak pressure.
The cold leg blowdown is faster than that of the pump suction break and more mass is released into the contaimnent.
However, the core heat transfer is greatly reduced, resulting in considerably lower energy release into containment.
Studies have determined that the blowdown transient for the cold leg is, in general, less limiting than that for the pump suction break. During reflood, the flooding rate is greatly reduced and the energy release rate into the containment is reduced. Therefore, the containment peak pressure for a cold leg break occurs at the end of blowdown.
An analysis of the cold leg break is not usually performed because the hot leg break is expected to result in the highest blowdown peak pressure and the pump suction break results _in the highest post-blowdown energy releases into containment.
For the double-ended pump suction break (DEPS), a two-phase mixture exits the core, which passes through the hot legs, and is superheated in the steam generators.
After the broken loop steam generator cools, the break flow becomes two phase. The pump suction break combines the effects of the relatively high core flooding rate, as in the hot leg break, and the addition of the stored energy in the steam generators.
As a result, the pump suction break yields the highest energy flow rates during the post-blowdown period. 6.2.1.3.3 AQplication of Single Failure Criteria:
An analysi's of the effects of the single failure criteria has been performed on the mass and energy release rates for the DEPS break. For the DEPS break, an inherent assumption in the generation of the mass and energy release is loss of off site power (LOOP). This results in the.actuation of the standby diesel generators, required to power the ECCS. The effects of a single failure are considered with both minimum and maximum safeguards.
In the minimum safeguards case) the single failure postulated to occur is the loss of one train (out of a three train system) ofECCS equipment due to the failure ofa diesel generator to start. This is labeled as a "Two Train" case and it results in the loss of one pumped emergency core cooling train, thereby minimizing the ECCS flow. For the case analyzing maximum ECCS, all six SI pumps are assumed to be available and the limiting single failure occurs in one component of the CHRS (i.e., a spray pump and a fan cooler train). This maximizes ECCS flow by assuming operability of all ECCS pumps. The analysis of both maximum and minimum safeguards cases bounds the effects of credible single failures.
6.2.1.3.4 Mass and Energy Release Data: 6.2.1.3.4.1 Significant Modeling Assumptions -The following items are incorporated so that the mass and energy releases are conservatively calculated for maximum containment pressure:
6.2-17 Revision 18 w 0\ 0\ w -w 0\
STPEGS UFSAR
* Maximum expected operating temperature of the RCS
* Allowance in temperature for instrmnent error and dead band ( +5 .1°F) NOC-AE-16003347 Enclosure Attachment Page 14 of77
* Margin in volume of 3% (composed of 1.6% allowance for thermal expansion and 1.4% for uncertainty)
* Core power level of 3,876 MWt (includes caloi"imetric errors)
* Conservative coefficients of heat transfer (i.e., SG primary/secondary heat transfer and RCS metal heat transfer)
* Allowance in core stored energy effect of fuel densification
* Margin in core stored energy ( + 15%)
* Allowance for RCS pressure 1mcertainty
(+46 psi)
* Maximum containment backpressure equal to design pressure.
Nitrogen Injection During a LOCA, most of the reactor vessel water will be displaced by the steam generated by flashing.
The vessel is then refilled by the SI accumulators and the high and low head safety injection systems. For the blowdown, refill and reflood stages, the mass and energy release rates are obtained from the Westinghouse LOCA analysis using NR C-approved methods (Reference 6.2:1.3-1). The releases include water from the ECCS accumulators, but the compressed nitrogen release is modeled separately in the GOTHIC containment analysis.model.
In the model, a boundary condition injects the nitrogen:
gas volume into the containment atmo.sphere consistent with the timing in the mass and energy releases.
The nitrogen pressure, temperature, and volume are based on allowable operating ranges in the plant Technical Specifications with consideration of uncertainty.
Decay Heat Two decay heat models are used for calculating the mass and energy releases as discussed below. Up to 3600 Seconds After the initial depressurization, the mass and energy releases from the effect of decay heat are based on ANS-5 .1-1979 Decay Heat Power (Ref. 6.2.1.3-4
), which include the following:
* Decay heat sources considered are fission product decay and heavy element decay ofU-239 andNp-239.
* Decay heat power from fission isotopes other than U-235 and U-238 are assumed identical to that ofU-235. Fast fissions for U-238 are included in a conservative manner.
* Fission rate is constant-over the operating history of maximum power level.
* The factor accounting for neutron *capture in fission products is taken from Table 10 of ANS-5 .1-1979 Standard.
* The fuel is assumed to operate at full power for 10 8 seconds.
* The totaf recoverable energy associated with one fission is assumed to be 200 Me V.
* Two sigma uncertainty (two times the standard deviation) has been applied to the fission product decay. 6.2-18 Revision 18 ' 1 I \ l STPEGS UFSAR After 3600 Seconds NOC-AE-1600334 7 Enclosure Attachment Page 15 of77 After 3600 seconds, the mass and energy releases are calculated using the revised recirculation methodology approved by the NRC in Reference 6.2.1.3-:-6.
The core decay heat is calculated using BTP ASB 9-2 decay heat correlations as defined in Section 9.2.5 ofNUREG-0800 (Reference 6.2.1.3-8).
The BTP ASB 9-2 decay heat data is presented in Table 6.2.1.3-6A.
Table 6.2.1.3-6 shows the decay heat data used in this analysis.
6.2.1.3 .4.2 Blowdown Mass and Energy Release Data-The SATAN-VI code is used for computing the blowdown transient and is the same as that used for the ECCS calculation in Reference 6.2.1.3-2.
The methodology for the use of this model is described in Reference 6.2.1.3-1.
Tables 6.2.1.3-4 and 6.2.1.3-5 present the calculated mass and energy releases for the blowdown phase of the break analyzed for the DEHL and DEPS breaks, respectively.
The mass and energy release for the DEHL break and the DEPS break, given in Table 6.2.1.3-4 and Table 6.2.1.3-5, terminate within 25 seconds after the initiation of the postulated accident.
6.2.1.3 .4.3 Reflood Mass and Energy Release Data -The WREFLOOD code is used for computing the reflood transient and is a modified version of that used in the ECCS calculation in Reference 6.2.1.3-2.
The methodology for the use of this model is described in Reference 6.2.1.3-1.
Steam Water Mixing Even though the Reference 6.2.1.3-1 model credits steam/water mixing only in the intact loop, steam/water mixing in the broken loop has been included in this analysis.
This assumption is justified and is supported by test data. It is summarized as follows: The model assumes a complete mixing condition (i.e., thermal equilibrium) for the steam/water interaction.
However, the complete mixing process is made up of two distinct physical processes.
The first is a two phase interaction with condensation of steam by cold injection water. The second is a single phase mixing of condensate and injection water. Since the mass and energy of the steam released is the most important influence to the containment pressure transient, the steam condensation part of the mixing process is the only part that need be considered.
Any directly heats only the sump. The most applicable steam/water mixing test data has been reviewed for validation of the containment integrity reflood steam/water mixing model. These data were generated in 1/3 scale 2 tests (Ref. 6.2.1.3-3), which are the largest scale data available.
They most closely simulate the flow 18 regimes and gravitational effects that would occur in a pressurized water reactor (PWR). These tests were designed specifically to study the steam/water interaction for PWR reflood From the entire series of 1/3 scale tests, a group almost directly to contai;ment integrity reflood conditions.
The injection flow rates for this group cover all phases and mixing conditions calculated during the reflood transient.
The data from these tests were reviewed and discussed in detail in Reference 6.2.1.3-1.
FQr all of these tests, the data clearly indicates the occurrence of very effective mixing with rapid steam condensation.
Therefore, the mixing model used in the containment integrity reflood calculation is supported by the 1/3 scale steam/water mixing data. 6.2-19 Revision 18 STPEGS UFSAR Post-Blowdown Phase NOC-AE-16003347 Enclosure Attachment Page 16 of Tt_ The limiting break for the containment integrity peak pressure analysis during the post-blowdown phase is the DEPS break. For this break, two flow paths are available in the RCS by which mass and energy may be released to containment.
One is through the outlet of the steam generator, the other via reverse flow through the reactor coolant pump. Steam, which is not condensed by ECCS injection in the intact RCS loops,, passes around the downcomer and through the broken loop cold leg and pump in venting to containment.
This steam also encounters ECCS injection water as it passes through the broken loop cold leg, complete mixing occurs, and a portion of it is condensed.
Credit is taken in this analysis for that portion of steam which is condensed.
This assumption is justified by the postulated break location and the physical presence of the ECCS injection nozzle. A description of the test and test results is contained in References 6 .2 .1.3-1 and 6 .2 .1.3-3. Table 6.2.1.3-SA and Table 6.2.1.3-SB present the calculated mass and energy release for the reflood phase of the DEPS break, with minimum and maximum ECCS, respectively.
The principal parameters during reflood are given in Tables 6.2.1.3-9 and 6.2.1.3-10 for the minimum and maximum ECCS DEPS break cases. The temperature that was assumed for the RWST for these l.JJ transients, and therefore the pumped safety injection flow during the injection phase, was 130°F. °' 6.2.1.3.4.4 Post-Reflood Mass and Energy Release Data-The FROTH code (Ref. 6.2.1.3-5) is used for computing the post-reflood transient.
The methodology for the use of this model is described in Reference 6.2.L3-1.
The mass and energy release rates calculated by FROTH are used in the containment analysis until the time of containment depressurization.
Table 6.2.1.3-SA presents the two-phase (froth} mass and energy release data for the DEPS break with minimum ECCS. Table 6.2.1.3-SB presents the two-phase mass and energy release data for the DEPS break with maximum ECCS.
* 6.2.1.3.4.5 Post-Depressurization Phase-For the LOCA mass and energy release calculation, the steam generators are conservatively cooled and depressurized to the saturation temperature of 212°F at 14. 7 psia at approximately 3600 seconds after accident initiation.
In the post-SG depressurization sump recirculation phase (after 3600 seconds), the revised recirculation methodology is *used (Reference 6.2.1.3-6).
The safety injection (SI) flow into the reactor vessel is a mixture of the HHSI and LHSI flows. The HHSI pmnps take suction from the sump and injects directly into the reactor vessel. The LHSI pumps also take suction from the sump but the flow is cooled by the RHR heat exchanger and then injected into the reactor vessel. The STP LOCA containment analyses conservatively do not use the HHSI flows in this phase of the transient.
In this model, if the enthalpy of the water leaving the core is less than the liquid saturation enthalpy at the containment steam partial pressure, the water is returned to the smnp. If the pressure of the water leaving the core* is greater than the saturation pressure of the containment, a pressure flash model is used to determine the flow split that is returned to the sump and the steam that is released to the containment atmosphere.
During this phase of transient, the BTP-ASB 9-2 decay heat model is used as discussed in Section 6.2.1.3.4.l.
6.2.1.3.5 Sources of Mass and Energy: The sources of mass considered in the LOCA mass and energy release analysis for the DEPS breaks are given in Tables 6.2.1.3-13 and 6.2.1.3-14.
The 6.2-20* Revision 18 STPEGS UFSAR NOC-AE-1600334 7 Enclosure Attachment Page 17 of77 mass inventories for the DEHL break are given in Table 6.2.1.3-15.
These sources* are the RCS accumulators and pumped ECCS injection.
The energy inventories for the LOCA mass and energy release analysis for the DEPS breaks are given in Tables 6.2.1.3-16 and 6.2.1.3-17.
The energy inventories for the DEHL break are given in Table 6.2.1.3-18.
The energy sources include:
* reactor coolant system water e accumulator water
* pumped injection water * . decay heat
* core stored energy
* reactor coolant system metal
* steam generator metal
* steam generator secondary energy
* secondary transfer of energy (feedwater into and steam out of the steam generator secondary)
In the mass and energy release data presented, no Zirc-water reaction heat is presented because the clad temperature does not rise high enough for the rate of the Zirc-water reaction heat to be of any significance.
The consideration of the various energy sources in the mass and energy release analysis provides assurance that all available sources of energy have been included in this analysis.
Thus the review guidelines presented in Standard Review Plan Section 6 .2.1.3 have been satisfied.
The mass and energy inventories are presented at the following times, as appropriate:
* time zero (initial conditions)
., end ofblowdown time
* end of refill time
* end of reflood time o time of broken loop steam generator
., time of intact loop steam generator depressurization e one hour after accident initiation The methods and assumptions used to release the various energy sources are given in Reference 6.2.1.3-1, except as noted in section 6.2.1.3.4.3.
The sequence of events for the DEPS and the DEHL break transients are shown in Table 6.2.1.1-10
.. 6.2.1.4 . Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures Inside the Containment.
6.2-21 Revision 18" STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 18 of77 Following a postulated MSLB or a FWLB inside the Containment, the contents of one SG will be released to the Containment.
Most of the contents of the other SGs will be isolated by the main steam isolation valves (MSIVs), main feedwater isolation valves (MFIVs) and the feedwater flow control valves (FCV). Contaimnent pressurization following a secondary side rupture depends on how much of the break fluid enters the Containment atmosphere as steam. Main steam line break flows can be pure steam or two-phase, while FwLB flows are With a pure steam release, all of the break flow enters the Containment vapor space atmosphere.
With two-phase release, part of the liquid in the break flow boils off in the Containment and is added to the vapor space atmosphere, while the remaining liquid falls to the sump and contributes nothing to Containment pressurization.
For MSLB cases with large break area, steam cannpt escape fast enough from the tvvo-phase region of the ruptured SG, and the two-phase level rises rapidly to the steam line nozzle. A two-phase blowdown results. The duration of this release is short, thereby reducing primary-to-secondary heat transfer, and the break flow is largely liquid. For MSLB cases with small break areas, steam can escape fast enough from the two-phase region of the SG with the rnptured line that the level swell does not reach the steam line nozzle, and a pure steam blowdown results. Because of the pressure reducing effects of active and passive Containment heat sinks, the highest peak Containment pressure resulting from a MSLB for a given set of initial SG conditions occurs for that case where the break area is the maximum at which a pure steam blowdown can occur. For conservatism, the MSLB analysis assumed only pure steam blowdown for all break sizes and power levels. Main steam line isolation is initiated on the following signals:
Containment pressure, low steam line pressure (above P-11 setpoint), high negative steam line pressure rate (below the P-11 setpoint), and manual. Main feedwater line isolation is initiated by SG high-high water level, reactor trip in conjunction with low Tavg, and SL The MSIV and MFIV closure times are given in Table 16.1-1. The MSLB blowdown calculation conservatively used 8 seconds for MSIV closure and 13 seconds for JvIFIV closure from the time the isolation setpoint was reached. These values include signal delay and valve closure times. The Auxiliary Feedwater System (AFWS) functions automatically following a secondary system line break to assure that a heat sink is always available to the RCS by supplying cold feedwater to the SGs. For conservatism, it was assumed that the AFWS attains full flow to the SG immediately following the initiation of the event. Following feed water isolation, only AFW is available to supply feedwater to the SGs. The analysis assumes the following manual operator actions within 30 minutes of the break: (1) isolate the AFW to the faulted steam generator, (2) re-pressurize the RCS using normal pressure control, and (3) control AFW to the intact steam generators and control cooldown.
In addition, the analysis includes flashing of fluid located between the MFIV and the affected SG. This fluid then flows through the affected SG and into the Containment.
To determine the effect ofMSLB on Containment pressure and temperature response, a spectrum of break sizes.was assumed to occur inside the Containment, downstream from the integral steam line flow restrictors and upstream of the MSIVs. The analysis assumed critical flow from the rupture. Feedwater Line Break (FWLB) 6.2-22 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 19 of77 The feedwater enters the SG in the two-phase region; therefore, FWLB cases always result in two-phase blowdowns through smaller size lines and do not produce peak Containment pressures and temperatures as severe as MSLB cases. uJ °' 6.2.1.4.1 Long-Term MSLB Mass and Energy Release Data: The MSLB mass and energy release transient is analyzed by using the RETRAN-02 computer code (Ref. 6.2.1.4-2).
Safety analysis methods using this code are described in WCAP-14882 (Ref. 6.2.1.4-3).
The code simulates a multiloop system, neutron kinetics, the pressurizer, feedwater system, SG, and SG safety valves. The code computes pertinent plant variables including primary and secondary temperatures and pressures, steam flow, and power level during the cooldown.
The DER and split break MSLBs analyzed are listed in Table 6.2.1.1-1.
Table 6.2.1.4-1 presents the mass and energy release rate data for the limiting break for peak pressure, 1.4 ft 2 double-ended rupture at 30% power with failure of one MSIV. Table 6.2.1.4-2 presents the mass and energy release rate data for the peak-temperature case, 1.4 ft 2 double-ended rupture at 0% power with failure of one MSIV. All mass energy releases used in the analyses were conservatively assumed to consist of dry steam although considerable entrainment can be expected for double-ended breaks. Mass and Energy Release Through MSIV Above Seat Drain Line Flow Restriction Orifices Additional mass and energy are released through the above seat main steam line orifices, since the condensers are assumed not available for steam dump. This has negligible affect on the mass and energy release rates .. The significant parameters affecting the mass and energy releases to Containment following a steam line break are discussed below. 6.2.1.4.2 Plant Power Level: Steam line breaks can be postulated to occur with the plant in any operating condition ranging from hot shutdown to full power. Since SG water mass decreases with increasing power level, breaks occurring at a lower power generally result in a greater total mass release to the Containment.
However, because ofincreased energy storage in-the primary plant, increased heat transfer in the SGs, and the additional energy generation in the nuclear fuel, the energy release to the Containment from breaks postulated to occur during power operation may be .greater than for breaks occurring with the plant in a hot shutdown condition.
Additionally, the steam pressure and the dynamic conditions in the SGs change with incteasing powet and have significant influence on the rate of release following a steam line break event. The power generated in the core due to the cooldown effect from the negative moderator coefficient is included in the analysis for each power level since it adds to the energy teleased to Contairunent.
Because of the opposing effect of changing power level on steam line break mass and energy teleases, no single power level can be singled out as a worst case initial condition for a steam line break. Therefore, a spectrum of power levels spanning the operating range, as well as the hot zero power conditions, has been considered.
6.2.L4.3 Break Type, Atea, and Location:
: 1. Break Type 6.2-23 Revision 18 
: 2. STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 20 of77 There are two possible types of pipe ruptures which must be considered in evaluating steam line breaks. .
* The first is a split rupture in which a hole opens at some point on the side of the steam pipe or steam header but does not result in a complete severance of the pipe. A single, distinct break area is fed uniformly by all SGs until steam line isolation occurs. The releases from the individual SGs are not independent since fluid coupling exists between all steam lines. Because of the flow limiting orifices in each SG, the largest possible split rupture can have an effective area prior to isolation that is no greater than the throat area of the flow restrictor times the number of plant primary coolant loops. Following isolation, the effective break area for the SG with the broken line can be no greater than the flow restrictor throat area. The second break type is the double-ended guillotine rupture (DER) in which the steam pipe is completely severed and the ends of the break displace from each other. Guillotine ruptures are characterized by two distinct break locations, each of equal area but being fed by different SGs. The largest possible gitillotine rupture can have an effective area per SG no greater than the throat area of one steam line flow restrictor.
Break Area The breaks analyzed include a spectrum of break areas (full double-ended and split ruptures) at each of the four initial power levels, as follows: a. A full double-ended pipe rupture downstream of the steam line flow restrictor.
For this case, the actual break area equals the cross-sectional area of the steam line ( 4.2 ft 2), but the mass and energy release from the SG with the broken line is controlled by the flow restrictor throat area (1.4 ft 2). The reverse flow :from the intact SGs is controlled by. the smaller of the pipe cross section or the total flow restrictor throat area in the intact loops. b. Split breaks that represent the largest break which will not generate a steam line isolation signal from the primary protection equipment.
Stearn and feedwater line isolation signals with be generated for these cases by high Containment ptessure signals. 3. Bteak Location Break location affects steam line blowdown by virtue of the pressure losses which would occur in the length of piping between the SG and the break. The effect of the pressure loss is to reduce the effective break area seen by the SG. Although this would reduce the rate of I mass and energy release, it would not significantly change the total energy release to the Containment.
Pipiilg loss effects have been considered in the MSLB mass and energy release calculation.
6.2.1.4.4 Main Feed water Addition Prial' to Feed water Line Isolation:
All of the double-ended ruptures generate main steam and feedwater isolation signals very quickly following the break. Isolation of the steam lines due to low steam line pressure is assumed to: be complete following a time delay sufficiently long to allow for instrument response time and signal processing delay and valve closing time (total of 8 seconds).
The total delay time assumed for feedwater isolation is 13 seconds. 6.2-24 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 21of77 3. During the transient, the SG pressure and temperature are assumed to remain constant at the initial conditions.
This is conservative, because the actual SG pressure would decrease during this event. 4. The quality of the moisture carryover is conservatively assumed to be 4% and is assumed to continue until the mass of the affected steam generator (including AFW flow) is depleted.
The 4% quality assumption is taken from Appendix E of ANSI 58.2M1980.
: 5. The analysis continues until the water mass in the affected steam generator(included AFW flow) is depleted.
After the mass in the affected steam generator is depleted, the mass and energy release from this generator is significantly reduced. At this time, the MSIV s are also assumed to close. This is conservative because MSIV closure is expected to occur at approximately 15 seconds based on a low steam line pressure signal. 6. AFW flow begins at the time of the break at the runout flow 1250 gal/min. 7. A sink volume is maintained at a constant pressure of 14.7 psia. 8. A throat with an area of 1.38 8 ft 2 is assumed to limit the MSLB mass and energy release from the SGside. The feedwater line break short-term mass and energy release analysis was performed using the RETRAN-03 (Ref. 6.2.1.2-8) computer program. Assumptions used in this analysis include: 1. F eedwater inlet nozzle area of 1.1175 ft 2 2. One millisecond break opening time. 3. Break junctions releasing mass into an environment that is maintained at a constant temperature and pressure of 120°F and 14.7 psia. 4. Feedwater pump characteristics are not included in this analysis 5. The mass and energy release analysis was evaluated for three bounding plant operating conditions.
* at hot zero power (1350 psia and 211°F feedwater conditions),
* at hot full power (1150 psia and 448°F feedwater conditions), and
* at hot full powel' (1194 psia and 390°F feedwater conditions).
The short-term mass and energy release rates were used in subcompartment pressurization analysis discussed in Section 6.2.1.2. 6.2.1.5 Miniimun Containment Pressure Analysis for Performance Capability Studies lo of Emergency Core Cooling System. The Containment backpressure used for the limiting case Cn=0.8 (Min. SI, High Tavg), double-ended cold leg guillotine break for the ECCS analysis presented.
°' in Section 15 .6.5 is presented on Figure*
: 1. Containment backpressure is calculated using the 6.2-28 Revision 18 STPEGS UFSAR REFERENCES Section 6.2: NOC-AE-16003347 Enclosure Attachment Page 22 of77 References 6.2.1.1-1 through 6.2.1.1-7 are not used. 6.2.1.1-8 6.2.1.1-9 6.2.1.1-10 6.2.1.1-11 6.2.1.1-12 6.2.1.1-13 6.2.1.2-1 6.2.1.2-2 6.2.1.2-3 6.2.1.2-4 6.2.1.2-5 6.2.1.2-6 Peterson, C.E. et al, "RETRAN-03-A Program or Transient Thermal-Hydraulic' Analysis of Complex Fluid Flow Systems, MOD 00 l ," developed by Computer Simulation and Analysis, Inc. for the Electric Power Research Institute, July 1991. R.G. Gido, CJ. Grimes, R.G. Lawton and J.A. Kurdick, "COMPARE:
A Code for the Transient Analysis of Volumes with Heat Sinks, Flowing Vents and Doors,'' Los Alamos Scientific Laboratory, LA-7199-MS, March 1978. R.E. Schwirian and C.H. Boyd, "Justification for Increasing Postulated Break Opening Times in Westinghouse Pressurized Water Reactors," WCAP-147 48, Revision 0, October 1996. George, T.L., et al, GOTHIC 7.2h, Containment Analysis Package; developed by Numerical Application, Inc. for the Electric Power Research Institute, March, 2009. Not Used GOTHIC Thermal Hydraulic Analysis Package, Version 8.0 (QA), EPRI, Palo Alto, CA: 2012 . .Bechtel Power Corporation, "COPDA Compartment Pressure Design Analysis,'' (Bechtel computer code), 1973. Bechtel Power Corporation, "Subcompartment Pressure and Temperature Transient Analysis," Topical Report No. BN-TOP-4, Rev. 1, October 1977. Crane Co., "Flow of Fluids," Technical Paper No. 410, 1969. Idel'chik, I.E., "Handbook of Hydraulic Resistance Coefficients of Local Resistance of Friction," AEC-TR-6630, 1966. Shepard, R.M., H.W. Massie, R.H. Mark and P.J. Doherty, "Westinghouse Mass and Energy Release Data for Containment Design," WCAP-8264-P-A (Proprietary), June 1975 and WCAP-8312-A Revision 1 (Nonproprietary), June 1975. RELAP 5/MOD 1 Code Manual Volume 1: System Models and Numerical Methods, NUREG/CR:.1826, EGG-2070, 1980. 6.2-54 Revision 18 j. J *i 1 :1 j j :j .,
STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 23 of77 REFERENCES (Continued)
Section 6.2: 6.2.1.3-7 6.2.1.3-8 6.2.1.4-2 6.2.1.4-3 6.2.1.5-1 6.2.5-1 6.2.5-2 6.2.5-3 6.2.5-4 6.2.5-5 6.2.5-6 6.2.5-7 0 Westinghouse Mass and Energy Release Data for Containment Design, "WCAP--8264-P-A Rev. 1 (Proprietary) and WCAP-8312-A (Non-Proprietary), August 1975. NUREG-0800, Standard Review Plan, Rev 2, 1981. McFadden, J.H., et al., "RETRAN-02:A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems," EPRI NP-1850-CCM-A.
Huegel, D.S., et al., "RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses,''
WCAP-14882-P-A, April 1999 Bordelon, F.M., Massie, H.W., Jr., Zordon T.A., "Westinghouse Emergency Core Cooling System Evaluation Model Summary," WCAP-8339, Jtme 1974.
* Wilson, J. F., "Qualification Testing for Model B Electric Hydrogen Recombiner," WCAP-9346 and WCAP-7709L, Supplements 1to7. Cottrell, W. B., "ORNL Nuclear Safety Research and Development Program, Bimonthly Report for July-August 1968,'' Report No. ORNL-TM-2412, Part 3, November 1968. Cottrell, W. B., "ORNL Nuclear Safety Research and Development Program, Bimonthly Report for September-October 1968," Report No. ORNL-TM-2425, January 1969, p. 53. Burchell, R. C., and D. D. Whyte, ."Corrosion Study for Determining Hydrogen Generation from Aluniinum and Zinc during Post-Accident Conditions," WCAP-8776, April 1976. 10CFR50.44, Combustible Gas Control for Nuclear Power Reactors (1-1-04 Edition).
Regulatory Guide 1.7, Control of Combustible Gas Concentrations in Containment, Revision 3, May 2003. Jaffee, D.R., "Issuance of Amendment Re: Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors (TAC Nos. MC4229 and MC4230),''
November 30, 2004 (ST-AE-NOC-04001311).
6.2-56 Revision 18 . ... -*
STPEGS UFSAR TABLE 6.2.1.l-1 NOC-AE-16003347 Enclosure Attachment Page 24 of77 CONTAINMENT DESIGN ACCIDENTS CONTAINMENT DESIGN PARAMETER POSTULATED ACCIDENTS ANALYZED Containment Peak Pressure/Temperature Containment Peale Pressure/Temperature Sub-compartment Peak Pressure Sub-compartment Peak Pressure Loss-of-Coolant Accidents (LOCA) DEPS, Min. SI, Min. CHRS DEPS, Max. SI, Min. CHRS DEHL, Min. SI, Min. CHRS DEHL, Max. *SI, Min. CHRS Secondary System Breaks CMSLB) 1.4 ft 2 DER@HFP, Minimum CHRS 1.4 ft 2 DER@HFP, MSIV Failure 1.4 ft 2 DER@HFP, MFIV Failure 1.4 ft 2 DER@ 70% Power, Minimum CHRS 1.4 ft 2 DER @ 70% Power, MSIV Failure 1 A ft 2 DER@ 70% Power, MFIV Failure 1.4 ft 2 DER@30% Power, Minimum CHRS 1.4 ft 2 DER@30% Power, MSIV Failure 1.4 ft 2 DER@ 30% Power, MFIV Failure 1.4 ft 2 DER @ 0% Power, Minimum CHRS 1.4 ft 2 DER@O%Power, MSIVFailure 1.4 ft 2 DER @ 0% Power, Jv!FIV Failure 1.08 ft 2 Split Break @HFP, Minimum CHRS 1.08 ft 2 SplitBreak@HFP, MSIV Failure 1.08 ft 2 Split Brealc@HFP, MFIV Failure 1.22 ft 2 Split Break@ 70% Power, Minimum CHRS 1.22 ft 2 Split Brealc@ 70% Power, MSIV Failure 1.22 ft 2 Split Break@ 70% Power, MFIV Failure 1.43 ft 2 Split Break @30% Power, Minimum CHRS 1.43 ft 2 Split Break@ JO% Power, MSIV Failure L43 ft 2 Split Break@ 30% Power, MFIV Failure 1.47 ft 2 Split Brealc@ 0% Power, Minimum CHRS 1.4 7 ft 2 Split Break @ 0% Power, MSIV Failure 1.4 7 ft 2 Split Brealc @ 0% Power, MFIV Failure SG Loop Compartment DER -RHR 12" Line DER -FW 16" Line at SG N0zzle Pressurizer Subcompartment Spray Line Brealc on Pressurizer Side Surge Line Subcompartments Sub-compartment Peak Pressure Surge Line Break in Pressurizer Skirt Area Surge Line Bl'eak in Vestibule Steam Line Subcompartment Sub-compartment Peak P1*essure Double-ended MS Line Break at Containment Wall Revision 18 l g w 0\
STPEGS UFSAR TABLE 6.2.1.1-1 (Continued)
CONTAINMENT DESIGN ACCIDENTS NOC-AE-1600334 7 Enclosure Attachment Page 25 of77 CONTAINMENT DESIGN PARAMETER POSTULATED ACCIDENTS ANALYZED Feedwater Line Subcompartment Sub-compartment Peak Pressure Double-ended FW Line Break at Containment Wall Miscellaneous High Energy Lines Sub-compartment Peak Pressure CVCS Line Break in Regenerative HX Compartment CVCS Letdown Line Break in Radioactive Pipe Chase Compartment External Pressure NOTES: DER CHRS eves DEHL DEPS FWLB MFIV MSIV MSLB RHR SI CVCS Letdown Line Break in RHR Valve Room Sub-compartment Inadvertent Spray Actuation Double-ended Rupture Containment Heat Removal System Chemical Volume and Control System Double-ended Hot Leg Break Double-ended Pump Suction Break Feedwater Line Break Main Eeedwater Line Isolation Valve Main Stearn Line Isolation Valve Main Steam Line Break Residual Heat Removal Safety Injection 6.2-58 Revision 18 w 0\
NOC-AE-16003347 Enclosure Attachment Page 26 of77 STPEGS UFSAR TABLE 6.2.1.1-2 DESIGN BASIS ACCIDENT CALCULATED PRESSURES IN CONTAINMENT
*Time of Peak Design Peale Peak Pressure Peak Parameter f 5 l Design Basis Accident [ll Pressure Pressure Pressure Margin Temperature Peale Internal LOCA-Double-Ended Pressure Hot Leg Break (DEHL) with 56.5 psig 40.1 psig 2*1.5 sec 29% 258°F Minimum Safety Injection
[2, 3, 4] and Minimum Contaimnent Heat Removal Systems (CHRS) in Operation Peak Internal LOCA -DEHL with Pr.essure Maximum Safety Injection 56,5 psig 40.l psig 21.5 sec 29% 258°F and Minimum [2,3,4] CHRS. Peale Internal LOCA-Double-Ended Pressure Pump Suction Break (DEPS) with Minimum 56.5 psig 38.6 psig 22sec 32% 256°F Safety Injection and Minimum CHRS Peale Internal LOCA-DEPS with Pressure Maximum Safety Injection 56.5 psig 38.6 psig 22 sec 32% 256°F and Minimum CHRS External Inadvertent Operation of (-) 3.5 (-)3.l 11.4% Pressure the Containment Spray psid
* psid System 1. DEHL Break Area= 4.587 :ft2per side (9.18 ft 2 total), Pipe inside diameter=
2.42 ft. DEPS Break Area= 5.241 ft 2 per side (10.48 ft 2 total), Pipe inside diameter=
2.58 ft. 2. STP uses a conservative value of 41.2 psig as the peak calculated internal containment pressure in Technical 6.8.3j, Technical Specification Bases 3/4.6.1.2 and 3/4.6.1.4, and UFSAR Tables 3 .11-1 and 6.5-2. 3. At 24 hours, the Contaimnent pressure is less than 50% of the peak. 4. Section 6.2.1.3 provides a discussion ofpost-blowdown period mass and energy release rates for this case. 5, For each LOCA case, two analyses were performed by selecting inputs to give either a high pressure or a high temperature in the *containment.
6.2-59 Revision 18 j I j' j I I I I i .J *I l 1 l i c ! ! I ' l i i l l I. (J i t: l w ! ,__. , w ! 0\ I I STPEGS UFSAR NOC-AE-16003347
* Enclosure Attachment Page 27 of77 TABLE 6.2.1.1-3 CONTAINMENT DATA USED IN PIT ANALYSIS General Information Internal Design Pressure External Design Pressure Structural Design Temperature Free Volume Design Leak Rate Initial Conditions for M&E and P/T Analyses Reactor Coolant System (at design overpower and at normal liquid levels) Reactor Power Level Nominal SG Outlet Coolant Temperature Nominal I}eactor Vessel Outlet Temperature Reactor Coolant Mass Liquid Plus Steam Energy Containment LOCA Peak Pressure Case LOCA Peak Temperature Case MSLB Peak Pressure Case MSLB Peak Temperature Case Essential Cooling Water Temperature Refueling Water Temperatlli*e Outside Temperature*
Stored Water (as applicable)
Refueling Water Storage Tank / Pressure [2] 15.1 psia 15.1 psia 15.1 psia 14.5 psia All Accumulators (safety injection tanks) 56.5 psig H3.5 psig 286°F 3.41E6 ft 3 0.3% per day [l] 3,876 Mwt [2] 549.4 to 560.8°F 614.8 to 624.8°F See Tables 6.2.1.3-13 to -18 See Tables 6.2.1.3-13 to -18 Temperature 61.8°F [2] 114°F [2] 114°F [2] 114°F [2] 103°F [2] 130oF 1 l0°F 360,000 gal 3,600 ft 3 Humidity 20% 100% 20% 20% [2] I. An error band of+0.1%, -0.85% applies to the calculated free volume. A volume of3.3xl0 6 ft 3 was used in the analysis.
: 2. Includes uncertainties.
6.2-60 Revision 18 ,_,, 0\
STPEGS UFSAR TABLE 6.2.1.1-5 NOC-AE-16003347 Enclosure Attachment Page 28 of77 ENGINEERED SAFETY FEATURES SYSTEM INFORMATION USED IN CONTAINMENT ANALYSIS Design/ Capacity A. Passive Safety Injection System 1. No. of Accumulators 3 2. Pressure Setpoint (psig) M&E (liquid release) 670 M&E (nitrogen gas release) 670 B. Active Safety Injection Systems B.l Up To End ofSG Depressurization (3600 seconds) 1. High Head Safety Injection System a. Number of Lines 3 b. Number of Pumps 3 2. Low Head Safety Injection System a. Number oflines 3 b. Number of Pumps 3 3. High Head +Low Head Safety Injection Minimum SI a. Total SI Flow 7851 gpm (1049.5 lbm/sec) Flow for 2 SI trains Maximum SI 12717gpm (1757 lbm/sec) Flow for3 Sltrains B.2 After 3600 seconds 1. High Head Safety Injection System a. Number.ofLines 3 b. Number of Pumps 3 2. Low Head Safety Injection System a. Number of lines 3 b. Number of Pumps 3 6.2-61 Used for Containment Mass & Energy Release and Pressure/
Temperature Analysis (Minimum SI) 3 585 710 2 2 2 2 Function of RCS Pressure See Table 6.2.1.3-2 0 0 2 2 Used for Containment Mass & Energy Release and Pressure/
Temperature Analysis (.Maximum SI) 3 585 710 3 3 3 3 Function of RCS Pressure See Table 6.2.1.3-3 0 0 2 2 Revision 18 t.J) ,._. w 0\ I I l ;I 'i I I :i 1 I 'I I I * ,i :! *' :1 !! *i . j !I STPEGS UFSAR TABLE 6.2.1.1-5 (Continued)
NOC-AE-16003347 Enclosure Attachment Page 29 of77 ENGINEERED SAFETY FEATURES SYSTEM INFORMATION USED IN CONTAINMENT ANALYSIS C. Containment Spray System (CSS) [1] 1. Number of Lines 2. Number of Pumps 3. Flow Rate (gpm) D. Reactor Containment Fan Coolers (RCFC) [1] 1. Number of Units 2. Air Side Ffow Rate, cfm 3. Heat Removal rate, Btu/hr Function of CCW temperature .and Containment atmosphere saturation temperature. (Value shown is at 125'F CCW, 0.0005 fouling factor, and 235°F containment saturation temperature)
E. Recirculation Systems RHR Heat Exchanger
[l] a. Number b. Type c. Overall Heat Transfer Coefficient U, Btu/hr-ft 2-°F d. Heat Transfer Area (A), ft2 f. Flow rates/Unit
: 1) Recirculation side {LHSI), lbm/hr (each) 2) Exterior side (CCW), (lbm/hr) g. Source of Cooling Water h. Recirculation Cooling Begins, (sec) F. Others Component Cooling Water Heat Exchanger
: a. Number Design/ Capacity 3 3 3,863 [2] 6 53,500 77.8e6 3 Vert. U-tube 387 5440 1.5xl0 6 (3000 gpm) 2.<5xl0 6 ccw [3] NIA 3 Used for Containment Pressure & Temperature Analysis (Minimum SI) 2 2 3,663 [2] 3 53,500 62.2e6 [3] 2 Vert. U-tube Calculated by GOTHIC 4532 2531 gpm 2.6xl0 6 ccw [3] 1465 Not Modeled Used for Containment Pressure & Temperature Analysis (Maximum SI) 2 2 3,663 [2] 3 53,500 62.2e6 [3] 2 Vert. U-tube Calculated by GOTffiC 4532 2531 gpm 2.6xl0 6 ccw [3] 1000 Not Modeled NOTES: 1. CSS and RCFCs were not used in M&E release analysis, but were used inP/T analysis.
RHR.HeatExchangers were used in both M&E and P/T analysis after 3600 seconds. 2. Data for 2 trains. 3. CCW supply temperatures used in P/T analysis:
125&deg;F from 0-5 hrs ll5&deg;F from 5 -10 hrs 110&deg;F after 1 0 hrs 125&deg;F for MSLB PIT analysis 6.2-62 Revision 18 !,;) ...... (.;) &deg;'
NOC-AE-16003347 Enclosure Attachment Page 30 of77 STPEGS UFSAR TABLE 6.2.1.1-7 MODELING OF STRUCTURAL HEAT SINKS FOR CONTAINMENT ANALYSES Heat Sink Exposed No. Passive Heat Sinks Material Thickness Surface (ft2) Containment Dome Amercote 90 Paint 8 mils 35300 Dimetcote 6 Paint 4 mils Carbon-Steel Liner 0.375in Air 2mils Concrete 36.0 in 2 Containment Wall Amercote 90 Paint 16 mils. 76800 Carbon-Steel Liner 0.375in Air 2 mils Concrete 48.0 in 3 Containment Floor Nutech Paint SO mils 14700 *Concrete 20 ft 2 I w 4 Concrete Internal Structure Nutech Paint SO mils 123400 ,__. w Concrete 15.36 in &deg;' 5 Concrete Intemal Wall Nutech Paint 50 mils 8800 (4.39 ft) Concrete 52.68 in 6 Internal Wall Amercote Paint 8 mils 24700 Dimetcote Paint 6 mils .Carbon-Steel 0.475 in Air 2 mils Concrete 27.29 In 7 Internal Walls Amercote Paint 8 mils 12800 Dimetcote Paint 6 mils Carbon-Steel 0.786 in Air 2mils Concrete 17.64 in 8 Stainless Steel Walls Stainless Steel O.S76 in 400 9 Carbon Steel Wall Amercote Paint 8 mils 301500 Dimetcote Paint 6 mils Carbon-Steel 0.35 in 10 Carbon Steel Components Amercote Paint 8 mils 6800 t< 0.125 in Dimetcote Paint 6 mils *Carbon-Steel 0.109 in 11 Carbon Steel Components Amercote Paint 8 mils 800 0.125 in. < t <
in Dimetcote Paint 6 mils Carbon-Steel o.156 in 12 Carbon Steel Components Amercote Paint 8 mils 8100 0.25 in. < t < 0.5 in Dimetcote Paint 6 mils C!U'bon*Steel 0.409 in 6.2-63 Revision 18 STPEGS UFSAR TABLE 6.2.1.1-7 (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 31of77 MODELING OF STRUCTURAL HEAT SINKS FOR CONTAINMENT ANALYSES Heat Sink No. 13 14 15 16 17 18 19 20 21 22 23 NOTE: Passive Heat Sinks Carbon Steel Components
* \ 0.5 in. < t < 1.0 in Carbon "Steel Components 1.0 in. < t < 2.5 in Carbon Steel Components t>2.5 in. Amercote Paint Dimetcote Paint Carbon*Steel Amercote Paint Dimetcote Paint Carbon-Steel Amercote Paint Dimetcote Paint Carbon-Steel Stainless Steel Components Stainless Steel Stainless Steel Piping Stainless Steel Carbon Steel Piping Electrical Components (not painted) Electrical Components (painted)
Carbon Steel Components thickness
<0.125 in Carbon Steel Components 0.125 in, < t < 0.25 in Carbon Steel *Compone11ts t>0.25 in Amercote Paint Dimetcote Paint Carbon-Steel Carbon-Steel (galvanized)
Amercote Paint Carbon*Steel Carbon Steel Carbon Steel Carbon Steel Thickness 8 mils 6 mils 0.827 in 8 mils 6 mils 1.859 in 8 mils 6 mils 3.696 in 0.40 in 0.264 in 8 mils 6 mils 0.231 in 0.11 in 16 mils 0.117 in 0.075 in 0.23 ht 0.458 in TOTAL Exposed Surface (ft2) 10900 9500 2000 1700 3900 700 115300 15200 15400 29500 4400 822600 This table provides passive heat sink data used in containment peak pressure/temperature response analyses.
In peak PIT analyses*, it is conservative to ignore additional heat sinks since it will give higher containment pressures and temperatures.
6.2-64 Revision 18 STPEGS UFSAR TABLE 6.2.1.1-8 NOC-AE-16003347 Enclosure Attachment Page 32 of77 THERMOPHYSICAL PROPERTIES OF STRUCTURAL HEAT SINK MATERIALS FOR CONTAINMENT ANALYSIS Thermal Material Density Conductivity Specific Heat .abmlffJ {Btu/hr-ft-
&deg;F) (Btu/lbm-&deg;F) Paint (Amercote, Organic, Topcoat) 109.8 0.375 0.454 Paint (Dimetcote, Inorganic Primer) 293.0 0.633 0.074 Paint (Nutech) 121.7 0.126 0.232 Air 0.0523 0.0174 0.174 Carbon Steel 490.0 25.0 0.110 Concrete 144.0 0.8 0.208 Stainless Steel 488.0 9.4 0.111 Copper 558.0 200 0.092 6.2-65 Revision 18 I w ...... w &deg;' ) . '
1 2 3 4 STPEGS UFSAR TABLE 6.2.Ll-9 NOC-AE-1600334 7 Enclosure Attachment Page 33 of77 CONTAINMENT HEAT SINK SURFACE HEAT TRANSFER MODEL Convective Condensation Heat Transfer Heat Transfer.
Interface Coefficient Coefficient Notes Containment Structure Heat transfer coefficient to (Dome, Wall) to Ambient Air 2.0 Btu/hr-ft2-&deg;F NIA outside atmosphere.
Containment Vapor & Liquid The DLM model calculates the to Containment Structures Natural Convection Diffusion Layer Model condensation rate and sensible (except Sump Floor) (DLM) heat transfer rate. GOTHIC Correlation Set with Split.option heat transfer model. The Split option switches heat transfer from the vapor to the liquid phase as the liquid level in the containment floor builds up. The Correlation Set is Natural Containment Vapor & Liquid Natural Convection Convection.
It allows sensible to Sump Floor for LOCA NIA heat transfer by convection to the liquid or vapor phase based on the liquid volume fraction and the Split option settings.
The Correlation Set with Split Option excludes any direct condensation .on the floor before it is covered with water. Natural Convection and DLM condensation Split option. Containment Vapor & Liquid Natural Convection Difftision Layer Model The Split option switches heat to Sump Floor for MSLB (DLM) transfer from the vapor to the liquid phase as the liquid level in the floor builds up. 6.2-66 Revision 18 lJJ l-' lJJ C\
STPEGS UFSAR TABLE 6.2.1.1-10 NOC-AE-16003347 Enclosure Attachment Page 34 of77 ACCIDENT CHRONOLOGY FOR DBA LOCA ANALYSIS [IJ , ' DEHL [l, 2 J DEHL[1*2 l DEPS [l, 2 J DEPS ri.2 J Min.SI Max.SI Min. SI Max. SI (3, 4, 5] [3,4, 5] [3,4] [3;4] EVENT Time (sec) Time {sec) Time (sec) Time (sec) Accident Initiation
-Pipe Break Cofocident 0.0 0.0 0.0 0.0 with LOOP Pressurizer Low Pressure Reactor Trip 2.4 2.4 3.0 3.0 Setpoint Reached ' Accumulators Begin to Inject 15.7 15.7 18.9 18.9 End ofBlowdown Phase 24.8 24.8 25;2 25.2 Pumped SI Begins 33.0 33.0 33.0 33.0 RCFCs at Full Speed 45.0 45.0 45.0 45.0 Accumulator Injection Ends 46.9 47.2 46.9 47.2 Containment Spray Flow Delivered to 85.0 85.0 85;0 85.0 Containment Atmosphere End of Reflood Phase 173.l 220.0 173.1 220.0 Broken Loop SG Depressurizes to 640.0 1045.7 640.0 1045.7 Containment Design Pressure Switchover to Smnp Recirculation Occurs 1465 1000 1465 1000 Intact Loop SGs Depressurize to Containment 1613.1 1754.4 1613.1 1754.4 Design Pressure All SGs Forced to Depressurize to 14.7 psia 3600.0 3600.0 3600.0 3600.0 and 212&deg;F Transient Simulation Ends 3.6xl0 6 3.6x10 6 3.6xl0 6 3.6x10 6 Notes: 1. DEHL= double-ended hot leg break. DEPS = double-ended pump suction break. 2. All cases analyzed with minimum containment heat removal systems in operation (3 RCFC units and 2 Containment Sprays). 3. Minimum SI= 2 LHSI + 2.HHSI flow up to end of SG depressurization phase (3600. seconds).
Maximum 3 LHSI + 3 HHSI flow up to end ofSG depressurization phase (3600 seconds).
: 4. 2 LHSI 12 RHR trains during post-SG depressurization phase (3600+ seconds).
: 5. For the DEHL cases, the calculated ,mass and energy release data ends at 24. 8 seconds and the DEPS M&E releases for the post-blowdown period were used. As discussed in Section 6.2.1.3.2, this results in the highest release rates. 6.2-67 Revision 18 w ,__. u.> &deg;' 
\ NOC-AE-16003347 Enclosure Attachment Page 35 of77 STPEGS UFSAR TABLE 6.2.1.2-5A STEAM GENERA TOR LOOP COJYIP ARTMENT PEAK PRESSURE
 
==SUMMARY==
FOR RHR LINE BREAK ANALYSIS Maximum Differential Margin Volume Pressure Design Pressure (percent)
Elevation Node No. am .(l2filfil Break Node Break Type mlliU Lhl 1 715.4 4.4 # 12 12"RHR 7.125 63 2 1369.0 5.7 # 12 12"RHR 7.125 25 3 1918.4 4.4 # 12 12"RHR 7.125 64 19' O" 4 1920.6 6.2 # 4 12"RHR 7.125 15 5 1920.6 4.6 # 4 12"RHR 7.125 55 to 6 4002.8 2.2 # 4 12"RHR 7.125 230 7 6020.7 1.7. # 4 12"RHR 7.125 325 28' 0 1/2" 8 4594.7 0.9 # 12 12"RHR 7.125 719 9 4409.2 0.7 # 4 12"RHR 7.125 915 10 4594.7 0.9 # 12 12"RHR 7.125 712 11 3021.8 3.2 # 12 12"RHR 7.125 123 12 1419.5 6.8 # 12 12"RHR 13.0 92 13 757.6 3.5 # 4 12"RHR 13.0 279 28' 0 1/2" 14 2159.1 3.6 # 4 12"RHR 13.0 267 15 2166.4 5.7 # 15 12"RHR 13.0 128 to 16 2186.6 2.8 # 4 12"RHR 13.0 365 17 4372.1 2.1 # 4 12"RHR 13.0 521 38' 4" 18 4372.1 0.9 # 12 12"RHR 13.0 1450 19 4373.l 0.7 # 12 12"RHR 13.0 1869 20 4372.1 0.9 # 12 12"RHR 13.0 1429 21 2052.4 2.4 # 12 12"RHR 3.625 55 22 3669.0 3.1 # 12 12"RHR 3.625 18 (':l 38' 4" 23 6103.0 2.6 # 15 12"FW 3.625 39 24 5312.3 2.3 # 15 12"RHR 3.625 62 to 25 5312.3 2.1 # 15 12" RI-IR 3.625 80 26 11792.4 2.0 # 12 12''RHR 3.625 89 66' 7 1 12'' 27 11792.4 0.9 # 12 12" RI'IR '-3.625 340 28 10646,0 0.8 # 4 12"RHR 3.625 387 29 11792.4 D.7 # 4 12"RHR 3.625 490 6.2-95 Revision 18 STPEGS UFSAR TABLE 6.2.J.3-1 NOC-AE-16003347 Enclosure Attachment Page 36 of77 SYSTEM PARAMETER INITIAL CONDITIONS (LOCA MASS AND ENERGY ANALYSIS)
Parameter Core Thermal Power (MWt) (with uncertainty}
Reactor Coolant System Total Flowrate (lbm/sec)
[IJ Vessel Outlet Temperature
(&deg;F) [!J Core Inlet Temperature
(&deg;F) [l] Vessel Average Temperature
(&deg;F) Initial Steam Generator Steam Pressure (psia) Steam Generator Design Steam Generator Tube Plugging (%) Initial Steam Generator Secondary Side Mass {lbm) [IJ Assumed Maximum Containment Backpressure (psia) Accumulator Water Volume (ft 3) per accumulator N1 Cover Gas Pressure for liquid release (psia) Temperature
(&deg;F) RWST Temperature
(&deg;F) Safety Injection Delay, total (sec} from beginning of event Two Trains of SI Three Trains of SI Flow: Minimum SI Maximum SI Time to cold leg recirculation (switchover to sump) (sec) [l] Includes appropriate uncertainty and/or allowance.
6.2-120 Value 3,876 40,366 629.9 565.4 597.7 1102.0 Ll94 0 178,761 71.2 1,200 600.0 120 130 30 24.1 Table-6.2.1.3-2 Table Tables 6.2.1.3-2, 6.2.1.3-3 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-2 NOC-AE-16003347 Enclosure Attachment Page 37 of77 LOCA-TOTAL PUMPED ECCS FLOW RATE FOR TWO TRAINS OF SI OPERATING INJECTION MODE CREFLOOD PHASE) RCS Pressure (psia) 14.7 Total Flow (lbm/sec) 1049.5 114.7 871.9 214.7 601.0 Time (sec) 1465 3600 >3600 RECIRCULATION MODE Enthalpy (BTU/lbm) 239.0 239.0 At transient Sump temperature Figures 6.2.1.1-31 and 6.2.1.1-37 6.2-121 Flow 656.69 lbm/sec 659.96 Ihm/sec 5062 gpm (2 LHSI} Revision 18 STPEGS UFSAR TABLE 6.2.1.3-3 NOC-AE-1600334 7 Enclosure Attachment Page 38 of77 LOCA-TOTAL PUMPED ECCS FLOW RATE FOR THREE TRAINS OF SI OPERATING (JJ INJECTION MODE (REFLOOD PHASE) RCS Pressure (psia) 14.7 Total Flow Obm/sec) 1757.0 114.7 1479.0 214.7 1152.0 314.7 664.0 RECIRCULATION MODE Time (sec) Enthalpy (BTU/Ibm)
Flow 1000 239.0 1649.8 lbm/sec 3600 239.0 1649.8 lbm/sec >3600 At transient 5062 gpm Sump temperature (2LHSI) Figures 6.2.1.1-31 and 6.2.1.1-37 6.2-122 &deg;' w ...... w &deg;' Revision 18 . i j I ' j Time (seconds) 0.00 0.001118 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 LOO 1.10 1.20 1.30 1.40 1.50 1.60 1.70 1.80 1.90 2.00 2.10 2.20 2.30 2.40 2.50 2.60 2.70 2.80 2.90 3.00 3.10 3.20 3.30 3.40 3.50 3.60 3.70 3.80 3.90 4.00 4.20 4.40 4.60 4.80 5.20 5.40 5.60 5.80 6.00 6.20 6.40 6.60 6J!O 7.00 STPEGS UFSAR TABLE 6.2.1.3-4 NOC-AE-16003347 Enclosure Attachment Page 39 of77 DOUBLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Break Path No. 1 Flow (Ihm/sec) 0.0 48,161.3 43,479.9 37,455. 1 36,887.7 36,127.8 35,740.4 35,453.0 35,161.5 34,748.6 34,219.4 33,679.8 33,229.5 32,837.3 32,452.0 32,124.8 31,704.0 31,296.5 30,973.2 30,711.6 30,428.7 30,068.4 29,694.8 29,351.0 29,043.3 28,724.0 28,351.9 27,968.5 27,656.0 27,390.1 . 27,113.3 26,805.4 26,516.3 26,294.9 26,110.3 25,92.9.1
* 25,776.7 25,674.9 25,610.1 25,578.7 25,622.7 25,749.0 15,546.7 17,784.1 18,349.4 18,984.7 20,896.6 30,394.4 28,621.I 28,594.7 29,735.9 30,986.6 31,9HU 32,569.4 33,008.l 33,293.7 I (SG Side) Thousand <Btu/sec) 0.0 31,617.2 29,082.3 25,208.7 24,896.8 24,441.2 24,222.2 24,065.9 23;906.5 23,669.2 23,358.l 23,043.6 22,793.8 22,585.7 n,382.2 22,222.2 21,986.7 21,742.6 21,544.3 21,381.6 21,200.4 '20,959.8 20,706.8 20,476.2 20;273.0 20;060.4 19,804.0 19,534.0 19,316.2 19,133.3 18,937.3 18,709.1 18,486:9 18,313.2 18,163.l 18,007.0 17,863.0 17,749.9 17;656.4 17,575.2 17,541.6 17,557.l 12,991.0 13,682.5 13,806.4 14,075.3 14,901.7 21,316.2 19,694.3 19,284.6 19,668.9 20,173.2 20,547.4 20,827.6 21,013.7 21,127.3 I Enthalpy <Btu/Ihm) 0 656.5 668.9 673.0 674.9 676.5 677.7 678.8 679.9 681.2 682.6 684.2 686.0 687.8 689.7 691.7 693.5 694.7 695.6 696.2 696.1 697.1 697.3 697.6 698.0 698.4 698.5 698.4 698.4 698.5 698.4 698.0 697.2 696.5 695.6 694.5 693.0 691.3 689.4 687.1 684.6 681.9 835.6 769.4 752.4 741.4 713.1 701.3 688.1 674.4 661.5 651.0 643.8 639.5 636.6 634.6 Break Path No. 2 Flow (lbm/sec)
I 0.0 48,159.3 29,157.0 25,850.5 23,217.8 21,962.5 21,260.8 20,731.5 20,406.3 20,121.9 19,942.l 19,785.l 19,657.1 19,557.7 19,500.8 19,424.8 19,394.0 19,379.8 19,383.7 19,409.1 19,447.4 19,487.0 19,526.6 19,564.8 19,601.0 19,633.2 19,659.7 19,678.6 19,693.5 19,706.0 19,712.2 19,710.9 19,701.3 19,687.l 19,667.6 19,641.3 19,607.4 19,567. r 19,521.5 19,467.7 19,406.9 19,339.6 19,174.3 18,983.0 18,734.9 18,476.4 17,886.4 17,575.3 17,236.0 16,890.6 16,513.4 16,084.4 15,686.5 15,287.0 14,851.0 14,399.0 (Reactor Side) Thousand (Btu/sec) 0.0 31,614.5 19,106.3 16,855.8 14;996.2 14,004.1 13,380,2 12,888.5 12,547.9 12,047.4 11,869.8 11,721.9 11,601.1 11,513.3 11,421.7 11,361.1 11,314.3 11,281.8 11,264.8 11,257.6 11,253.3 11,251.5 11,250.5 11,250.4 11,250.0 11,248.0 11,243.3 11,238.0 11,232.6 11,225.3 11,214.9 11,201.1 11,185.8 11,168.6 11,148.5 11,125. 1 11,098.9 11,070.6 11,038.3 11,002.8 10,964.3 10,871.7 10,766.5 10,631.0 10,491.6 10,175.7 10,010.1 9,829.6 9,646.5 9,445.8 9,216.2 9,006.3 8,796.6 8,566.6 8,328.4 I Enthalpy (Btu/lbm) 0 656.5 655.3 652.-0 645.9 637.6 629.3 621.7 614.9 609.J 604.l 599.9 596.3 593.2 590.4 588.0 585.8 583.8 582.0 580.4 578.9 577.5 576.2 575.0 574.0 573.0 572.l 57T.3 570.6 570.0 569.5 569.0 568.5 568.2 567.9 567.6 567.4 567.2 567.1 567.0 567.0 566.9 567.0 567.2 567.4 567.8 568.9 569.6 570.3 571.1 572.0 573.0 574.l 575.4 576.8 578.4 6.2-123 Total Mass From Both Sides (Ihm/sec) 0.0 96,320.5 72,636.9 63,305.5 60,105.5 58,090.3 57,001.2 56,184.5 55,567.9 54,870.4 54,161.5 53,464.9 52,886.7 52,395.0 51,952.7 51,549.5 51;098.0 50,676.3 50,356.9 50,120.8 49,876.1 49,555.4 49;221.3 48,915.8 48,644.3 48,357.2 48;011.6 47,647.l 47,349.6 47;096.l . 46;825.5 46,516.3 45,982.0 45;777.9 45,570.4 45,384.l 45,242.0 45,131;7 45,046.4 45,029.6 45,088.6 34,721.0 36,767.1 37,084.3 37,461.0 38,783.1 47,969.7 45,857.1 45,485.3 46,249.3 47,071.0 47,604.5 47,856.4 47,859.1 47,692.6 Total Energy From Both Sides Thousand !Btu/sec) 0.0 63,231.7 48,188.6 42;064.4 39,893.0 38,445.3 37,602.4 36,954.4 36,454.4 35,924.6 35,405.5 34,913.4 34,515.7 34,186.8 33,895.5 33,643,9 33;347.7 33,056.9 32,826.2 32;646.4 32,458.0 32,213.1 31,958.3 31,726.7 31,523.4 31,310.3 31,052.0 30,777.2 30,554.2 30,365.9 30,162.5 29,924.0 29,688.0 29,499.0 29,331.7 29,155.5 28,988.1 28,848.8 28,727.0 28,613.5 . 28,544.5 28,521.4 23,862.7 24,449.0 24,437.5 24,566.9 25,077.4 31,326.3 29,523.9 28,931.l 29,114.8 29,389.4 29,553.7 29,624.2 29,580.3 29,455.7 Revision 18 Time (seconds) 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10.60 10.80 11.00 11.20 11.40 11;60 11.80 12.00 12.20 12.40 12.60 12.80 13.00 13.20 13.40 13.60 13.80 14.00 14.20 14.40 14.60 14.80 15.00 15.20. 15.40 15.60 15.80 16.00 16.20 16.40 16.60 16.80 17.00 17.20 17.40 17.60 17.80 18.00 18.20 18.40 18.60 18.80 19.00 19,20 19.40 STPEGS UFSAR TABLE 6.2.1.3-4 Continued) t NOC-AE-1600334 7 Enclosure Attachment Page 40 of77 DOUBLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Break Path No. 1 Flow Break Patil No. 2 Flow (SG Side) (Reactor Side) (lbm/scc)
I Thousand I Enthalpy (lbm/sec)
I Thousand I Enthalpy (Btu/sec)
{Btu/lbm) (Btu/sec) (Btu/lbm) 33,488,8 33,619.0 33,707.9 33,784.6 33,808.6 33,810.8 33,756.0 33,627.f 33,420.0 33,138.5 32,795.4 32,398.9 31,594.2 30,463.6 28,855.6 18,648.6 12,416.3 12,484.2 11,600.l 11,834.8 11,727.9 12,284.0 12,771.6 13,273.6 14,145.7 16,007.3 16,333.8 15,926.3 15,838.9 15,794.9 15,712.7 15,563.5 15,352.0 12,307.7 12,898.5 13,470.2 8,500.2 9,004.6 9,205.6 9,310.4 9,706.9 10,793.8 9,215.3 8,411.9 8,048.6 5,900.9 5,260.1 5,018.9 4,775.4 4,529.6 4,256.9 3,964'.5 3,686.S 3,4455 3,272.4 3,120.2 2,955.l 2,775.9 2,581.4 2,412.6 2,298.2 2,225.l 21,200.7 21,247.0 21,276.7 21,303.l 21,288.7 21,260.6 21,200.4 21,098.l 20,951.7 20,766.5 20,541.2 20,291.1 19,778.5 19,042.9 17,997.2 11,318.0 8,786.5 8,797.3 8,643.0 8,691.0 8,617.7 8,821.4 9,043.4 9,307.5 9,806.5 11,129.5 11,425.4 11,101.4 11,001.4 10,945.5 10,885.1 10,802.0 10,705.7 8,493,9 8,570.7 8,706.0 6,722.1 6,938.0 7,102.4 7,258.9 7,649.1 8,776.6 8,085.6 7,691.3 7,393.2 5,600.4 5,189.5 5,046.9 4,887.3 4,704.8 4,491.0 4,297.9 4,123.6 3,960.7 3,824.7 3,667.9 3,489.4 3,294.8 3,074.8 2,884.0 2,757.9 2,690.2 633.l 13,913.6 632.0 13,421.4 631.2 12,936.2 630.6 12,451.8 629.1 11,977.4 628.8 11,515.8 628.0 11,061.l 627.4 10,628.3 626.9 10,218.8 626.7 9,833.6 626.3 9,472.0 626.3 9; 130.6 626.0 8,807.7 625.1 8,502.2 623.7 8,219.2 606.9 7 ,962.3 707.7 7,701.0 704.7 7,490.3 745.1 7,337.4 734.4 7,195.4 734.8 7,095 .2 718.1 7,022.3 708.l 6,967.7 701.2 6,928.1 693.3 6,889.6 695.3 6,848.6 699.5 6, 791.0 697.0 6,713.8 694.6 6,604.6 693.0 6,473.3 692.8 6,323.2 694.l 6,157.0 697.4 5,982.5 690.1 S,799.4 664.5 5,617.3 646.3 5,439.4 790. 8 5,278 .5 770.5 5,143.5 771.5 5,035.0 779.7 4,948.3 788.0 4,887.4 813. 1 4;839.4 877.4 4,795.6 914.3 4,739.7 918.6 4,657:0 949.1 4,534.7 986.6 4,375.5 1,005.6 4,181.0 1,023.4 3,965.9 1,038.7 3,735.6 1,055.0 3,492.3 1,084.1 3,245.9 1,118.6 3,004.0 1,149.5 2,775.3 1,168.8 2,544.4 1,175.5 2;323.7 1,180.8 2,123.1 1,186.9 1,931.4 1,191.1 1,771.9 1,195.4 1,613.8 1,200.0 1,461.9 1,209.0 1,329.7 6.2-124 8,072.0 7,812.7 7,558.3 7,305.0 7,057.9 6,818.4 6,582.7 6,359.3 6,148.9 5,951.9 5;767.8 5,594.8 5,431.9 5,278.5 5,137J .5,010.9 4,881.2. 4,782.I 4,713.9 4,643.8 4,593.2 4,551.3 4,514.7 4,484.0 4,452.4 4,420.1 4,379.7 4,330.8 4,267.3 4,197.5 4,123.3 4,045.7 3,967:6 3,887.6 3,810.0 3,735.5 3,670.0 3,616.5 3,572.8 3,530.3 3,494.2 3,458.4 3,423.l 3,382.2 3,330.9 3,266.5 3,195.4 3,121.5 3,052.8 2,982.4 2,904.4 2,820.l 2,736.4 2,662.3 2,589.7 2,515.5 2,430.4 2,302.7 2,165.7 1,992.1 1,813.1 1,654.9 580.2 582.1 584.3 586.7 589.3 592.1 595.1 598.3 601:7 605.3 608.9 612*.8 616.7 620.8 625.0 629.3 633.8 638.4 642.5 645.4 647.4 648.l 647.9 647.2 646.2 645.4 644.9 645.1 646.J 648.4 652.l 657.l 663.2 670.3 678.3 686.7 695.3 703.1 709.6 713.4 714;9 714:6. 713.8 713.6 715.2 720.3 730.3 746.6 769:8 79M 831.7 868.8 910;9 959.3 1,017.8 1,082.6 1,144.8 1,192.2 1,222.2 1,234.4 1,240.2 1,244.6 Total Mass From'Both Sides (lbm/sec) 47,402.4 47,040.4 46;644.I 46,236.4 45,786.0 45,326.6 44,817.l 44,255.4 43,638.8 42,972.2 42,267.4 41,529.5 40,401.9 38,965.8 37,074.8 26,611.0 20,117.3 19,974.5 18,937.4 19,030.2 18,823.l 19,306.3 19,739.3 20,201.7 21,035.3 22,855.9 23,124.7 22,640.l 22,443.5 22,268.2 22,035.9 21,720.5 21,334.4 18,107.0 18,515.8 18,909.6 13,778.8 14,148.l 14,240.6 14,258.6 14,594.3 15,633.2 14,010.9 13,151.6 12,705.5 10,435.6 9,635.7 9,199.9 8,741.3 8,265.2 7,749.2 7,210.3 6,690.4 6,220.7 5,816.8 5,443.9 5,078.2 4,707.3 4,353.4 4,026.4 3,760.1 3,554.8 Total Energy From Both Sides Thousand (Btu/sec) 29;272.7 29,059.6 28,835.0 28,608.1 28,346.6 28,079.0 27,783.0 27,457.3 27,100.5 26,718.4 26,308.9 25,885.9 25,210.4 24,321.4 23,134.3 16,328.9 13,667.7 13,579.3 13,356.9 13,334.8 13,211.0 13,372.7 13,558. 1 13,791.5 14,258.9 15,549.6 15,805. 1 15,432.3 15,268.7 15,143.0 15,008.4 14,847.8 14;673.3 12,381.5 12,380.7 12,441.5 10,392.1 10,554.5 10,675.3 10,789.2 11,143.3 12,235.0 11,508.7 11,073.6 10,724.1 8,866.8 8,384.9 8;168A 7,940.1 7,687.2 7,395.4 7,118.0 6,860.0 6,622.9 6,414.4 6,183.4 5,919..9 5,597.4 5,240.5 4,876.J 4,571.0 4,345.l Revision 18 STPEGS UFSAR TABLE 6.2.1.3-4 Continued)
NOC-AE-16003347 Enclosure Attachment Page 41 of77 DOUBLE-ENDED HOT LEG BREAK MASS AND ENERGY RELEASES Time (seconds) 19.60 19.80 20.00 20.20 20.40 20.60 20.80 21.00 21.20 21.40 21.60 21.80 22.00 22.20 22.40 22.60 22.80 23.00. 23.20 23.40 23.60 23.80 24.00 24.20 24.40 24.60 24.80 24.84 NOTES: Break Path No. I Flow Break Path No. 2 Flow (SG Side) (Reactor Side) (lbm/sec)
I Thousand j Enthalpy (lbm/sec)
I Thousand I Enthalpy (Btu/sec) (Btu/lbm) (Btu/sec) (Btu/lbm) 2,043.l 1,942.8 1,853.2 1,770.0 1,646.3 1,511.6 1,369.3 1,235.6 1,137.2 1,054.6 922.8 796.1 692.5 584.4 454.9 375.7 270.6 201.7 70.2 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2,466.3 2,363.9 2,264.2 2,177.2 2,032.S 1,865.7 1;686.9 1,517.5 1,394.5 1,294.2 1,131.9 975.2 849.2 716.9 555.6 460.l 330.1 245.l 84.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,207.1 1,228.1 1,532.9 1,216.7 1,160.4 1,451.8 1,221.8 1,109.3 1,390.0 1,230,0 1,065.0 1,336.2 1,234.6 1,022.2 1,284:3 1,234.3 985. l 1,239.0 1,231.9 949.0 1,194.7 1,228.l 914.0 1,151.7 1,226.2 883.9 1,114.7 1,227.1 855.3 1,079.5 1,226.5 827.3 1,045.0 1,225.1 800.6 1,011.9 1,226.2 766.3 969. I 1,226.7 723.8 915.9 1,221.5 680.2 861.5 1,224.9 654.4 830,0 1,220.l 642.8 815.:S 1,215.1 625.0 793.3 1,196.7 600.3 762.2 0 555.7 705.7 o* 506.3 643.5 0 457.1 581.7 0 405.4 516.3 0 339.3 432.6 0 260.4 . 332.6 0 185.2 237.2 0 77.7 100.l 0 66.4 85.7 End ofBlowdown
[2, 3, 4, 5] 1,248.2 1,251.2 1,253.l 1,254.7 1,256.3 1,257.8 1,259.0 1,260.1 1,261.1 1,262.2 1,263.1 1,263.9 1,264.6 1,265.3 1,266.5 1,268.4 1,268.6 1,269.3 1,269.6 1,270.0 1,271.1 1,272.4 1,273.6 1,275.0 1)77.3 1,280.5 1,287.8 1,290.2 1. Hot Leg Break Area= 4.587 m, Pipe inside diameter=
2.42 ft Total Mass From Both Sides (lbm/sec) 3,271.2 3,103.2 2,962.4 2,835.0 2,668.6 2,496.7 2,318.3 2,149.6 2,021.l 1,909.9 1,750.1 1,596.6 1,458.9 1,308.2 1,135.1 1,030.1 913.4 826.7 670.5 555.7 506.3 457.1 405.4 339.3 260.4 185.2 77:7 66.zl Total Energy From Both Sides Thousand (Btu/sec)'
3,999.l 3,815.8 3,654.2 3,513.4 3,316.8 3,104.8 2,881.6 2,669.2 2,509.2 2,373.7 2,176.9 1,987.1 1,818.3 1,632.8 1,417.1 1,290.2 1,145.6 1;038.4 846.1 705.7 643.5 581.7 516.3 432.6 332.6 237.2 JOO.I .85.7 2 The blowdown phase mass and energy releases are the same for Minimum and Maximum SI cases. 3. For DEHL Minimum SI post-blow down phase, the DEPS Min. SI post-blowdown M&E releases are used (Table 6.2.l.3*5A), as discussed in Section 6.2.1.3.2.
: 4. For DEHL Maxhnum SI post-blowdown phase, the DEPS Max. SI post-blowdown M&E releases are used (Table 6.2.1.3-5B), as discussed in Section 6.2.1.32.
5 After 3600 seconds, the revised post recirculation methodology is used, as discussed in Section 6.2.1.3.4.5.
6.2-125 Revision 18 Time STPEGS UFSAR TABLE 6.2.1.3-SA NOC-AE-16003347 Enclosure Attachment Page 42 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Minimum SI) Break Path No. 1 Flow Break Path No. 2 Flow Total Mass Total Energy From Both (SG Side) (PnmpSide)
Sides From Both Sides (seconds) (lbm/scc)
I Thousand
* 1 Enthalpy (Ihm/sec)
I Thousnnd I Enthalpy (lbm/scc)
Tllonsand (Btu/sec) (Btullbm) (Btu/sec) (Btullbm) (Btn/scc) 0.00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.00114 97,158.3 54,746.8 563..5 43,339.6 24,348.l 561.8 140,497.9 79,094.8 0.10 43,480.5 24,471.9 562.8 21,547.8 12,088.3 561.0 65,028.3 36,560.2 0.20 51,982.9 29,373.7 565.1 24,528.6 13,777.6 561.7 76,511.5 43,151.3 0.30 51,633.9 29,3.19.5 567.8-25,873.5 14,546.5 562.2 77;507.4 43,866.0 0.40 51,282.7 29,294.9 571.2 25,649.9 14,432.9 562.7 76,932.6 43,727.8 0.50 50,920.4 29,294.0 575.3 24,960.9 14,057.0 563.2 75,881.3 43,351.0 0.60 50,719 29,407.1 579:9 24,416.8 13,760.3 563.6 75,131.l 43,167'.3 0.70 49,896.9 29,180.0 584.8 24,052.4 13,561.7 563.8 73,949.4 42,741.7 O.llO 48,045.5 28,330.9 589.7 23,753.6 13,396.9 564.0 71,799:1 41,727.8 0.90 47,471.7 28,211.3 594.3 23,440.1 13,222.'0 564.1 70,911.8 41,433.3 1.00 47,553.0 28,462.2 598.5 23,099.6 13,030.6 564.1 70,652.7 41,492-.8 1.10 47,301.6 28,504.7 602.6 22,771.3 12,845.l 564.1 70,072.9 41,349.8 l.20 46,713.0 28,337.7 606.6 22,488.7 12,685.9 564.1 69;201.7 41,023.6 1.30 45,879.3 28,014.4 610.6 22,307.8 12,584.1 564.1 68,187.1 40,598.6 1.40 44,977.2 27,652.8 614.8 22,153.8 12,497.8 564.1 67,131.0 40,150.5 1.50 44,069.3 27,288.9 619.2 22,023.9 12,425.0 564.2 66,093.2 39,713.9 1.60 43,087.0 26,882.9 623.9 21,910.8 12,361.3 564.2 64,997.8 39,244.1 1.70 42,038.7 26,434.8 628.8 21,829.6 12,315.5 564.2 63,868.3 38,750.J 1.80 40,932.5 25,950.6 634.0 21,785.3 12,290.8 564.2 62,717.8 38,241.4 1.90 39,839.5 25,469.8 639.3 21,742.5 12,267.2 564.2 37,737.0 2,00 38,715.4 24,965.0 644.8 21,660.5 12,221.l 564.2 60,375.9 37,186.J 2.10 37,556.9 24,426.6 650.4 11,545.6 12,156.0 564.2 59,102.4 36,582.6 2.20 36,371.7 23,856.7 655.9 21,371.8 12,057.1 564.2 57,743.5 35,913.8 2.30 35,147.2 23,250.1 661.5 21,088.3 11,896.7 564.J . 56,235.5 35,146.8 2.40 34,060.0 22,718.5 667.0 20,894.6 11,787.9 564.2 54,954.6 34,506.4 2.50 32,996.1 22,186.4 672.4 20,712.4' I 1,685.5 564.2 53,708.6 33,871;9 2.60 31;939.8 21,643.l 677.6 20,514.2 11,573.9 564.2 52,454.0 33,217.0 2.70 30;932.3 21,118.9 682.7 20,313.0 11,460.6 564.2 51,245.3 32,579.6 2.80 29,765.0 20,472.0 687.8 20,113.0 11,348.2 564.2 49,878.0 31,820.2 2.90 27,445.6 18,995.3 692.l 19,902.8 . 11,230.2 564.2 47,348.4 30,225,5 3.00 25,766.4 17,965.5 697.2 19,688.4 11,109.8 564.3 45,454,8 29,075.2 3.10 24,813.9 17,434.4 702.6 19,480.3 10,993.1 564.3 44,294,2 28,427.6 3.20 23;807-.7 16,826.2 706.8 19,276.4 10,879.0 564.4 43,084.1 27,705.1 3.30 22,807.1 16,193.0 710.0 19,070.0 10,763.4 564.4 41,877.1 26,956.4 3.40 22,078.1 15,737.9 712.8 18,852.2 10,641.4 564.5 40,930.3 26,379.3 3.50 21,448.8 15,339.9 715.2 18,6432 10,524.4 564.5 40,092.0 25,864.3 3.60 20,878.1 14,972.0 717.1 18,453.8 10,418.7 564.6 39,331.9 25,390.8 3.70 20,389.7 14,654.9 718.7 18,266.8 10,314;4 564.7 38,656.5 24,969.4 3.80 ]*9,938.4 14,356.3 720.0 18,076.3 10,208.l 564.7 38,014.7 24,564.4 3.90 19,505.0 14,064.6 721.l 17,883.0 10,100.1 564.8 37,388.l 24,164.7 4.00 19,114.4 13,799.7 722.0 17,705.0 10,000.9 564.9 36;819.4 23,800.6 4.20 18,464.4 13,353.2 723.2 17,375.2 9,817.4 565.0 35,839.6 23,170,6 4.40 17,903.6 12,954.7 723.6 17,046.4 9,634.3 . 565.2 34,950.0 22,589,0 4.60 17,483.5 12,645.2 723.3 16,753.7 9,471.7 565.3 34,237.2 22,IJ6.9 4.80 17,144.9 12,380.3 722.l 16,458.5 9,307.4 565.5 33,60'.l.4 21,687.7 5.20 17,002.0 12,201.1 717.6 15,778.8 8,926.8 565.7 32,780.7 21,127.8 6.2-126 Revision 18 2 I w >-' w 0\ 'I I i i 'I _:\ j STPEGS UFSAR TABLE 6.2.1.3-SA (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 43 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Minimum SI) Break Path No. 1 Flow Break Path No. 2 Flow Total Mass Total Ene1*gy Time From Both (SGSide) (PumpSicle)
Sides From Both Sides (seconds) (lbm/sec)
I Thousand \ Enthalpy (lbm/sec)
I Thousand I Enthalpy (lbm/scc)
Thousand (Btu/sec) (lltu/lbm) (Btu/sec) (Btu/lbm) (Btu/sec) 5.40 17,031.9 12,141.1 712.8 15,592.9 8,826.8 566.l 32,624.8 20,967.8 5.60 16,900.2 12,240:9 724.3 15,241.3 8;629.2 566.2 32,141.5 20,870.0 5.80 15;466.8 11,897.2 769.2 15,053.8 8,528.0 566.5 30,520.6 20,425.2 6.00 14,376.0 11,430.7 795.l 16,196.3 9,180.7 566.8 30,572.3 20,611.4 6.20 14,657.9 11,492.0 784.0 15,895.2 9,009;6 566.8 30,553.2 20,501.7 6.40 15,346.8 11,800.3 768.9 15,813.2 8,967.1 567-.l 31,160.l 20,767.5 6.60 15,997.4 12,107.9 756.9 15,629.5 8,865.9 567.3 31,626.9 20,973.8 6.80 16,544.7 12,356.4 746.9 15,430.<5 8,756.7 567.5 31,975.3 21,113.1 7.00 16,993.7 12,521.2 736.8 15,310.6 8,692.4 567.7 32,304.3 21,213.6 7.20 17,301.2 12,567.4 726.4 15,127.2 8,590.1 567.9 32,428.4 21,157.5 7.40 17,454.4 12,526.1 717.6 14,903.7 8,463.6 567.9' 32,358.1 20,989.7 7.60 17,610.0 12,526.9 711.4 14,723.3 .8,361.1 . 567.9 32,333.3 20,888.0 7.80 17,829.7 12,592.3 706.3 14,506.8 8,237.2 567.8 32,336.4 20,829.6 8.00 17,924.5 12,575.6 701.6 14,289.4 8,113.0 567.8 32,213.9 20,688.6 8.20 17,836.0 12,454.6 698.3 14,107.1 8,009.0 567.7 31,943.1 20,463.6 8.40 17,825.2 12,420:5 696:8 13;922.3 7,903.6 567.7 31,747.5 20,324.1 8.60 17,956.9 12,483.S 695.2 13,698.3 7,775.5 567.6 31,655:2 20,259.0 8.80 17,676.8 12,241.5 692.5 13,487.0 7,655.0 567.6 31,163.8 19,896.5 9.00 17,077.6 11,811.4 691.6 13,366.6 7,586.8 567.6 30,444.2 19,398.2 9.20 16,898.6 11,709.6 692.9 13,192.2 7,486.7 567.5 30,090.8 19,196.3 9.40 17,090.6 11,826.0 692.0 12,944.4 7,344.6 567.4 30;035.J 19,170.6 9.60 16,910.7 11,644.8 688.6 12,7582 7,238.8 567.4 29,668.9 18,883.5 9.80 14,830.5 10,196.8 687.6 12,709,0 7,211;9 567.5 27,539.5 17,408.8 10.00 12,649.1 8,828.0 697.9 13,118.2 7,446.2 567.6 25,767.3 16,274.2 10.20 12,658.6 9,020.5 712.6 12,514.9 7,092.9 566.8 25,173.5 16,113.4 10.40 12,79'.7.8 9,094.0 710.6 12,318.5 6,983.1 566.9 25,116.3 16,077.l 10.60 11,922.0 8,448.1 708.6 12;796.2 7,260.6 567.4 24,718.1 15,708.6 10.80 11,736.9 8,446.7 719.7 12,339.2 ' 6,994.l 566.8 24,076.0 15,440.8 11.00 12,081.0 8,773.4 726.2 12,043.5 6,825.4 566.7 24,124.5 15,598.8 11.20 11,784.2 8,497.8 721.1 12,135.5 6,881.3 567.0 23,919:7 15,379.l 11.40 11,410.l 8,242.3 722.4 12,060.5 6,838.9 567.l 23,470.5 15,081.3 11.60 12,022.0 8,705.2 724.1 11,676.4 6,616.5 566.7
* 23,698.5 15,321.8 11.80 12,800.0 9,129.8 713.3 11,454.4 6,491.8 566.7 24,254.4 15,621.5 12.00 11,778.0 8,305.9 705.2 11,582.3 6,569.0 567.2 23,360.3 14,874.9 12.20 10,425.l 7,479.6 717.5 11,903.4 6,749.6 567.0 22,328.4 14,229.3 12.40 10,397.9 7,613.8 732.2 11,064.1 6,264.2 566.2 21,462.1 13,877.9 12.60 10,018.5 7,345.8 733.2 11,629.6 6,594.0 567.0 2*1,648J 13,939.8 12.80 9,73'3.9 7,184.7 738.1 11,276.7 6,388,8 566.5 21,010.6 13,573.5 13.00 9,876.1 7,359.2 745.2 11,100.7 6,292.2 566.8 20,976.8 13,651.4 13.20 9,734.1 7,235.4 743.3 11,058.9 6,270.0 567.0 20,792.9 13,505.4 13.40 9,607.8 7,128.7 742.0 10;975.5 6,225.1 567.2 20,583.3 13,353.7 13.60 9,972.8 7,373.l 739.3 10,604.9 6,014.2 567.1 20,577.6 13,387.3 13.80 9,909.5 7,230.9 729.7 10,672.5 6,057:1 567.5 20,582.0 13,288.1 14.00 9,201.4 6,740.9 732.l 10,751.l 6,104.7 567.8 19,958.S 12,845.6 14.20 9,198.0 6,827.9 742.3 10,242.6 5,817.7 568.0 19,440.7 12,645.5 14.40 8,859.7 6,572.9 741.9 10,609.9 6,035.7 568.9 19,469.6 12,608.5 14.60 8,566,4 6,402.9 747.4 10;296.8 5,861.4 569.2 18,863.2 12,264.3 14.80 8;533.4 6,474.8 758.8 10;211.7 5,827.7 570.7 18,745.l 12,302.5 15.00 8,216.2 6,319.6 769.2 10,063.9 5,745.5 570.9 18,280. l 12,065.l 15.20 8,116.9 6,272.4 772.8 9,886.0 . 5,654.2 571.9 18,002.9 11,926.6 15.40 8,111.4 6,214.l 766.1 9,718.4 5,562.7 572.4 17,829.8 11,776.8 15.60 7,997.5 6,067.5 758.7 9,736.5 5,583.5 573.5 17,734.0 11,651.0 15.80 7,981.8 6,028.7 755.3 9,444.5 5,428.5 574.8 17,426.2 11,457.2 6.2-127 Revision 18 w ..... w "' ' j I 1 l I I ! I !
STPEGS UFSAR TABLE 6.2.1.3-SA (continued)
NOC-AE-16003347 Enclosure Attachment Page 44 of77 I DOUBLE-ENDED PUM:P SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 16.00 16.20 16.40 16.60 16.80 17.00 17.20 17.40 17.60 17.80 18.00 18.20 18.40 18.60 18,80 19.00 19.20 19.40 19.60 19.80 20.00 20.20 20.40 20.60 20.80 21.00 21.20 21.40 21.60 21.80 22.00 22.20 22.40 22.60 22.80 23.00 23.20 23.40 23.60 23.80 24.00 24.20 24.40 24.60 24.80 25.00 25.20 25.65 25.75 25.85 25.95 Break Path No. 1 Flow (Ibm/sec) 7,827.7 7,670.7 7,560.1 7,435.8 7,286.3 7,157.4 7,050.4 6,958.0 6,849.1 6,723.1 6,585.5 6,430.2 6,261.9 6,107.3 5,941.4 5,702.7 5,251.8 4,598.8 3,926.3 3,408.6 3,024.3 2,731.6 2,468.3 2,239.0 2,048.2 1,892.3 1,796.6 1,711.4 1,619.6 1,501.7-1,388.1 1,275.2 1,171.6 1,045.0 946.3 877.3 831.S 802,0 775.7 727.1 557.7 453.5 &deg;375.8 279.1 168:9 31.6 o.o 0.0 0.0 0.0 0.0 I (SGSide) Thousand (Btu/sec) 5,894.1 5,794.8 5,759.4 5,732.5 5,686.3 5,633.2 5,571.8 5,516.4 5,460.8 5,414.2 5,382.0 5,356.2 5,327.1 5,301.0 5,251.4 5,205.0 5,128.4 4,953.8 4,649.5 4,188.7 3,747.2 3,399.5 3,081.6 2,803.8 2,571.6 2,381.5 2,265.5 2,160.7 2,046.9 1,899.3 1,758.3 1,617.3 1,487.4 1,328.9 1,204.8 1,118.2 l,060.7 1,023.6 990.4 928.6 712.0 579.7 480.8 357*.3 216.5 48.4 Q;O 0.0 0,0 0.0 0,0 [ Enthalpy (Btu/lbm) 753.0 755,4 761.8 770.9 780.4 787.0 790.3 792.8 797.3 805.3 817.3 833.0 850.7 868.0 .883.9 912.7 976.5 1,077.2 1,184.2 J,228.9 1,239.0 1,244.5 1,248.5 1,252.3 1,255.6 1,258.5 1,261.0 1,262.5 1,263.8 1,264.8 1,266,8 1,268.2 1,269.6 1,271.7 1,273. I 1,274.7 1,275.6 1,276.4 1,276.9 1,277.1 1,276.5 1,278.3 1,279.4 1,280.4 1,281.9 l,285.8 0;0 0,0 0.0 0.0 0.0 (Minimum SI) Break Path No. 2 Flow (lbm/sec)
I 9,559.1 9,331.2 9,310.0 9,144.5 8,976.l 8,762;9 8,538.6 8,327.4 8,119.3 7,902.6 7,668.1 7,441.3 7,187.l 6,981.9 6,470.9 5,996.7 5,581.4 5;082.1 4,413.1 2,536:6 1,724.2 1,504.4 1,351.9 1,229.0 1,110.7 1,480.9 2,572.9 2,837.4 3,167.8 3,156.0 2,799.3 2,433.4 2,162.1 1,952.0 1,774.9 1,635.9 1,731.5 2;058,5 2,539.4 3,217.9 3,471.3 2,353.0 1,269.5 543.6 91.9 0.0 0.0 (Pump Side) Thousand (Btu/sec) 5,508.9 5,405.3 5,419.4 5,356.4 5,287.4 5,196.7 5,097.8 5,015.3 4,942,0 4,875.6 4,807.5 4,749.7 4,681.0 4,661.7 4,522;9 4,374.5 4,262,8 4,145.8 4,052.0 2,869.I 2,095.5 1,859.6 1,681.7 1,535,2 1,392.9 1,611.7 1,432.5 1,364.0 1;4062 1,336.7 1,149.5 977.0 850.7 751.4 666.0 597.7 613.6 696.1 819.5 995.9 1,035.2 685.2 365.6 156.0 26.4 0.0 0.0 End ofBlowdown 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 I Enthalpy (Btu/lbm) 576.3 579.3 582.1 585.8 589.0 593.0 597.0 602.3 608.7 617.0 626.9 *638.3 651.3 667.7 699.0 729.5 763.7 815.8 918.2 1,131.I 1,215.3 1,236.2 1,243.9 1,249.l 1,254.1 1,088.4 556.7 480.7 443.9 423.5 410.6 401.5 393.5 385.0 375.2 365.3 354.4 338,2 322.7 309.5 298.2 291.2 288,0 286.9 287.1 0.0 o.o 0.0 0.0 0.0 0.0 6.2-128 Total Mass From Both Sides (lbm/sec) 17,386.9 17,001.9 16,870.1 16,580.2 16,262.4 15,920.4 15,589,0 15,285.4 14,968.4 14,625.7 14,253,6 13,871.6 13,448.9 13,089.2 12,412.3 11,699.4 10,833. 1 9,680.9 8,339.4 5,945.1 4,748.5 4,236.0 3,820.2 3,468.0 3,158.9 3,373.2 4,369.5 4,548.9 4,787.4 4,657.7 4,187.4 3,708.6 3,333.7 2,996.9 2,721.2 2,513.1 2,563.0 2,860.5 3,3 IS.I 3,945.l 4,029.0 2,806.5 1,645.3 822.6 260.8 37.6 o.o 0.0 0.0 0.0 0.0 Total Energy From Both Sides Thousand (Btu/sec) 11,403,l 11,200.0 11,178.8 11,088.9 10,973.6 10,829.9 10,669.6 10,531.7 10,402.8 10,289.8 10,189.5 10,105.9 10,008.0 9,962.7 9,774.3 9,579.5 9,391.I 9,099.6 8,701.5 7,057.8 5,842.7 5,259.l 4,763.3 4,339.0 3,964.5 3,993.2 3,698.0 3,524.7 3,453.0 3,236.0 2,907.8 2,594.3 2,338.2 2,080.3 1,870.8 1,715.9 1,674.3 1,719.8 1,810.0 1,924.5 1,747.1 1,264.9 846.4 513.3 242,9 48.4 0.0 0,0 0.0 0.0 0.0 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-5A (continued)
NOC-AE-16003347 Enclosure Attachment Page 45 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 26.05 26.28 26.38 26.48 26.58 26.68 26,78 26.85 26;88 26,98 27.08 27.18 27.28 27.38 27.48 27:58 27.68 27.78 27.88 27.98 28.08 28.18 28.28 29.28 30.00 30.30 31.30 32.30 32.70 33.30 34.30 35.30 35.90 36.30 37.30 38.30 39.30 39.50 40.30 41.30 42.30 43.30 43.40 44.30 45.30 46.30 47.30 48.30 49.30 50.30 51.30 52.30 53.30 (Minimum SI) Break Path No, 1 Flow Break Path No. 2 Flow (lbm/sec) 0.0 56.5 58:3 66.1 73.8 81.1 88.1 93.1 94.7 101.0 107.0 112.7 118.2 123.6 128.7 133.7 138.6 143.3 147.8 152.3 156.6 160.9 165.0 202.1 768.7 808.8 806.1 795.6 790.1 847.2 826.4 815.3 808.9 804.7 794.1 782.1 770.7 768.5 759.7 749.2 739.2 729.5 728.6 720.2 711.3 702.7 409.3 409.9 409.6 409.4 409.2 409,0 408.9 I (SGSide) Thousand (Btu/sec) 0.0 66.7 68.9 78.0 87.2 95.8 104.0 109.9 111.8 119.2 126.3 133.1 139.7 146.0 152.1 158.0 163.7 169.2 174.6 179.9 185.0 190.1 195.0 238.9 915.4 963.9 960.8 948J 941.4 1,010.1 985.3 971:9 964.1 959.1 946.3 931.9 918.1 915.4 904.9 . 892.2 880.l 868.5 867.4 857.3 846.6 836.3 485.0 485.7 485.3 485.I 484.9 484.7 484.5' I Enthalpy (Btu/Ibm) (lbm/sec)
I 0.0 0.0 1,180.8 0.0 1,180.8 0.0 1,180.9 0.0 1,180.9 -o.o 1,180.9 0.0 1,181.0 0.0 1,181.0 0.0 1,181.0 0.0 1,181.1 0.0 1,181.1 0.0 1,181.1 0.0 1,181.2 0.0 1,181.2 0.0 1,181.3 0.0 1,181.3 0.0 1,181.3 0.0 1,181.4 0.0 1,181.4 0.0 1,181.5 0.0 1,181.5 0.0 1,181.5 0.0 1,181.6 0.0 1,182.0 0.0 1,190.8 6,636.7 1,191.8 6,942.3 1,191.9 6,925,2 1,191.7 6;828.4 1,191.6 6,786,0 1,192.3 7,265.8 1,192.3 7,140.1 1,192:1 7,034.1 1,191.9 6,971.1 1,191.9 6,929.5 1,191.6 6,827.9 1,191.4 6,730.T 1,191.2 6;636.5 1,191.2 6,618.0 1,191.l. 6,545.4 1,190.9 6,457.2 . 1,190.7 6,371.9 1,190.5 6,289.4 1,190.5 6,281.3 1,190.4 6,209.6 1,190.2 6,132.3 1,J 90. l 6;057.5 1,184.9 220,8 1,185.0 218.8 1,185.0 219.9 1,184.9 221.1 1,184.9 222.3 1,184.9 223.6 1,184*9 224.8 6.2-129 (Pump Side) Thousand I Enthalpy (Btu/sec) (Btn/lbm) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,{) 0,0 0.0 0.0 0:0 0.0 O,O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 910.3 137.2 988.6 142.4 997.7 144.1 986.0 144.4 980.9 144.5 1,044.6* 143.8 1,026.7 143.8 1,013.3 144.1 1,005.3 144.2 1,000.1 144.3 987.4 144.6 975.5 144.9 964.1 145.3 961.8 145.3 953.1 145,6 942.5 146.0 932.3 146.3 922.5 146.7 921.5 146.7 913.0 147.0 903.8 147.4 894.9 147.7 198.5 899.3 199.2 910.6 198.8 903.9 198.4 897.2 198.0 890A 197.6 883.8 197.2 877.2 Total Mass Total Energy From Both Sides From Both Sides (Ihm/sec)
Thousand (Btu/sec) 0.0 0.0 56.5 66.7 58.3 68.9 66.1 78.0 73.8 87.2 81.l 95.8 88.l 104.0 93.1 109.9 94.7 111.8 101.0 119.2 107.0 126.3 112.7 133.1 118.2 139,7 123.6 146.0 128.7 152.1 133.7 158.0 138.6 163.7 143.3 169.2 147.8 174.6 152.3 179.9 156.6 185.0 160.9 190.1 165.0 195.0 202.l 238.9 7,405.4 1,825.7 7,75-1.1 1,952.5 7,731.3 1,958.5 7,624.0 1,934.l 7,576.1 J,922.3 8,113.0, 2,054.7 7,966.5 2,012.0 7;849.4 1,985.2 7,780.0 1,969.5 7,734.2 1,959.1 7,622.0 1,933,6 7,512.8 1,907.4 7,407.2 1,882.2 7,386.5 1,877.2 7,305.l 1,858.0 7,206.4 1,834.7 . 7,111.1 1,812.4 7,018.9 1,791.0 7,009.9 1,788.9 6,929.8 1,770.3 6,843.6 1,750.4 6,760.2 1,731.2 630.1 683.5 628.6 684.9 629.5 684.1 630.5 683.4 631.5 682.8 632.6 682.2 633.7 681.7 Revision 18 &sect; ...... w 0\
STPEGS UFSAR TABLE 6.2.1.3-5A (continued)
NOC-AE-16003347 Enclosure Attachment Page 46 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 53.90 54.30 55.30 56.30 57.30 58.30 59.30 6030 6.J.30 62.30 63.30 64.30 65.30 66.30 66.40 67.30 68.30 69.30 70.30 71.30 12.30 73.30 74.30 75.30 76.30 77.30 78.30 79.30 79.70 80.30 81.30 82.30 83.30 84.30 85.30 86.30 88.30 90.30 92.30 94.20 94.30 96.30 98.30 100.30 102:30 104.30 106.30 108.30 lW.00 110.30 112.30 114.30 116.30 (Minimum SI) Break Path No. I Flow Break Path No. 2 Flow (lbm/scc)
I 408.8 408.7 408.6 408.4 408.3 408.1 408.0 407.8 407.7 407.5 407.4 407.2 407.0 406.8 406.8 406.6 406.4 406.2 406.0 405.8 405.5 405.3 405.0 404.8 404.5 404.2 403.9 403.5 403.4 403.2 402.8 402.4 402.0 401.5 401.0 400.5* 399.5 398.3 397.1 395.9 395.8 394.4 393.0 391.4 389.8 388.1 386.3 384.5 382.8 382.5 380.6 378.5 376.4 (SGSide) Thousand (Btu/sec) 484.4 484.3 484.1 483.9 483.8 483.6 483.4 483.3 483.1 482.9 482.7 482.5 482.3 482.0 482.0 481.8 481.6 481.3 481.1 480.8 480.5 480.2 479.9 479.6 479.2 478.9 478.5 . 478.1 478.0 477.7 477.2 476.8 476.2 475.7 475.l 474.6 473'.3 471.9 470.5 469.0 468.9 467.3 465.5 463.7 461.7 459.7 457.6 455.4 453.5 453.1 450.8 448.3 445.8 I Enthalpy (Btu/Ibm) (Ihm/sec)
I 1,184.9 225.6 1,184.9 226.1 1,184.9 227.3 1,184.9 228.6 1,184.9 229.9 1,184.9 231.2 1,184.9 232.6 1,184.9 233.9 1,184.9 235.3 1,184.9 236.7 1,184.9 238.2 l,184.9 239.6 1,184.9 241.l 1,184.9 242.7 1,184.9 242.8 1,184.9 244.2 1,184.9 245.8 1,184.9 247.4 1,184.<;l 249.1 1,184.9 250.8 1,184.9 252.5 l;l 84.9 254.3 1,184.9 256.l 1,184.9 257.9 1,184.9 259.7 1,184.9 261.7 1,184.9 263.6 1,184.9 265.5 1,184.8 266.3 1,184.8 267.5 1,184.8 269.5 1,184.8 271.6 1,184.8 273.6 1,184.8 275.7 1,184.8 277.8 1,184.8 279.9 1,184.8 284. I 1,184.8 288.5 1,184.7 292.9 1,184.7 297.2 1,184.7 297.4 1,184.7 302.0 1,184.7 306.6 J,i84.7 311.3 1,184.6 316.I 1,184.6 320.9 1,184.6 325.9 l, 184.5 330.9 1,184.5 335.1 1,184.5 335.9 1,184.5 341.0 1,184.4 346.2 . 1,184.4 35L4 6.2-130 (Pump Side) Thousand I Enthalpy (Btu/sec) (Btu/lbm) 197.0 873.2 196.8 870.6 196.4 864.1 196.l 857.7 195.7 851.2 195.3 844.8 195.0 838.4 194.6 832.1 194.3 825.6 193.9 819.2. 193.6 812.8 193.2 806.3 192.9 '799,9 192.5 793.4 192.5 792.8 192.2 ; 786.9 19L8 780.4 191.5 773.9 191.1 767.4 190.8 760:8 190.5 754.3 190.1 747.7 189.8 741.1 189.4 734.6 189.1 728.0 188.8 721.5 188.4 714.9 188.1 708.4 188.0 705.8 187.8 701.9 187.4 695.4 187.1 689.0 186.8 682.6 186.4 676.2 186.l 669'.9 185.7 663.7 185.l 651.3 184.4 639.1 183.7 627.1 183.1 616.0 183.0 615.4 182.4 603.9 181.7 592.6 181.l 581.6 180.4 570.8 179.8 560.3 179.2 550.0 178.6 539.9 178.2 531.6 178.1 530.2 177.5 520.6 177.0 511.4 176.5 502.4 Totn!Mass From Both Sides (lbm/scc) 634.3 634.8 635.9 637.0 638.2 639,3 640.5 641.7 643.0 644.2 645.5 646.8 648.1 649.5 649.6 650.8 652.2 653.6 655.1 656.5 658.0 659.5 661.1 662.6 664.2 665.8 667.5 669.1 669.7 670.7 672.3 673.9 675.6 677.2 678.8 680.4 683.6 686.8 690.0 693.0 693.2 696.4 699.6 702.7 705.9 709.0 712.2 715.3 718.0' 718.4 721.6 724.7 727.8 Total Energy From Both Sides Thousand (Btu/sec) 681.3 681.1 680.5 680.0 679.5 678.9 678.4 677.9 677.3 676.8 676.3 675.7 675.l 674.6 674.5 674.0 673.4 672.8 672.2 671.6 671.0 670.3 669.7 669.0 668.3 667.7 667.0 666.2 665.9 665.5 664.7 .663.9 .663.0 662.1 661.2 660.3 658.3 656.3 654.2 652.0 651.9 649.6 647.2 644.8 642.2 639.5, 636.8 634.0 631.6 631.2' 628.3 625.4 622.3 Revision 18 i G.l *:j ..... w O'I STPEGS UFSAR TABLE 6.2.1.3-SA (continued)
NOC-AE-16003347 Enclosure Attachment Page 47 of77 PUMP SUCTION BREAK MASS AND ENERGY RELEASES. (Minimum SI) Break Path No. 1 Flow Break Path No. 2 Flow Total Mass Total Energy Time From Both (SGSide) (PnmpSide)
Sides From Both Sides (seconds) (Ihm/sec)
I Thousand I Enthalpy (lbm/scc)
I Thousand I Enthalpy (lbm/sec)
Tl1011sand (Btu/sec) (Btu/lbm) (Btu/sec) (Btu/lbm) (Btu/see) 118.30 374.2 443.2 1,184.4 356.7 176.1 493.7 730.9 619.3 120.30 372.0 440.6 1,184.3 362.0 175.6 485.2 734.0 616.2 122.30 369.7 437.8 1,184.3 367.4 175.2 476.9 737.l 613.1 124.30 367.3 435.0 1,184.3 372.9
* 114.8 468.9 740.2 609.9 126.30 364.9 432.l 1,184.2 378.4 174.5 461.2 743.3 606.6 127.70 363.2 430.l 1,184.2 382.3 174.3 455.9 745.5 604.3 128.30 362.4 429.2 1,184.2 384.0 174.2 453.6 746.4 603.4 130.30 359,9 426.2 1,184.2 389.6 173.9 446.3 749.5 600.0 132.30 357.3 423.1 1,184.1 395.3 173.6 439.2 752.6 596.7 134.30 354.6 419.9 1,184.1 401.l 173.4 432.3 755.7 593.3 136.30 351.9 416.6 1,184.0 406.9 173.2 425.7 758.8 589.9 138.30 349'.I 413.3 1,184.0 412.9 173.1 4192 762.0 586.4 140.30 346.2 409.9 1,183.9 418.9 173.0 412.9 765.1 582.9 142.30 343.3 406:4 1,183.9 424.9 172.9 406.8 768.2 579.3 144.30 340,3 402.9 1,183.8* 431.1 172.8 400.9 771.4 575.7 146.30 337.3 399.3 1,183.8 437.3 172.8 395.2 774.6 572.1 148.20 334.3 395.7 1,183.8 443.4 172.9 389.9 777.7 568.6 148.30 334.2 395,6 1,183.8 443.7 172.9 3&9.6 777.8 568.4 150.30 331.0 391.8 1,183.7 450.I 173.0 384.3 781.1 564.7 152.30 327.7 387.9 1,183.7 456.7 173.l 379,0 784.4 560.9 154.30 324.3 383.9 1,183.6 463.4 173.3 373.9 787.7 557.1 156.30 320.9 379.8 1,183.6 470.2 173.5 369.0 791.0 553.3 158.30 317.4 375.6 1,183.5 477.1 173.7 364.2 794.5 549.4 160.30 313.8 371.4 1,183,S 484.1 174.1 359.6 797.9 545.4 162.30 309.9 366.8 1,183.4 491.0 174.3 355.o* 801.0 541.1 164.30 305.8 361.9 1,183.3 497.1 174.4 350,8 802.9 536.3 166.30 301.7 357.0 1,183.3 503.2 174.5 346.8 804.9 531.5 168.30 297.6 352.l 1,183.2 509.3 174.7 342.9 806.9 526;8 170.30 293,2 346.9 1,183.2-515.5 174.8 339.l 808.8 521.7 172.30 288.6 341.5 1,183.l 521.0 174.8 335.5 809.7 516.3 173.10 286.8 339.3 1,183.1 523.3 174.8 334.1 810.1 514.1 End ofReflood 173.20 324.5 404.1 1,245.4 622.7 204.6 328.6 947.1 608.7 178.20 300.8 374.5 1,245.4 646.4 202.7 313.7 947.f 577.3 183.20 300.l 373.7 1,245.4 647.1 202.7 313.2 947.1 576.4 188.20 298.2 371.3 1,245.4 649.0 202.9 312.7 947.1 574.2 193.20 297.4 370.4 1,245.4 649.7 202.9 312,2 947.1 573.3 198.20 296.7 369.5 1,245.4 650.5 202.8 311.8 947.1 572.3 203.20 296.1 368.8 1,245.4 651.0 202.7 311.4 947.1 571.5 208.20 295.6 368.l 1,245.4 651.5 202.6 311.0 947.1 570.7* 213.20 293.8 365.9 1,245.4 653.3 202.8 310.5 947.1 568.8 218.20 293.3 365.2 1,245.4 653.9 202.8 310.1 947.1 568,0 223.20 292.7 364.5 1,245.4 654.5 202.7 309.7 947.l 567.1 228.20 292.0 363.6 1,245.4 655.2 202.6 309.3 947.1 566.2 233.20 291.3 362.8 1,245.4 655.9 202.6 308.8 947.1 565.3 238.20 289.4 360.4 1,245.4 657.8 202.8 308.4 947.1 563.2 243.20 288.6 359.4 1,245.4 658.5 202,8 307.9 947.1 562.2 248.20 287.8 358.4 1,245.4 659.4 202.8 307.5 947J 561.2 253.20 286.9 357.3 1,245.4 660.2 202,8 307.1 947.1 560.1 258.20 286.0 356.1 1,245.4 661.2 202.8 306.7 947:1 558.9 263.20 285.0 354.9 1,245.4 662.1 202.8 306.3 947.1 557.7 268.20 284.0 353,7 1,245.4 663.2 202.8 305,8 947.1 556.5 6.2-131 Revision 18 l,JJ ,__. w 0\
STPEGS UFSAR TABLE 6.2.l.3-5A (continued)
NOC-AE-16003347 Enclosure Attachment Page 48 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Minimum SI) Bl'cak Path No. 1 Flow Break Path No. 2 Flow Total Mass Total Energy Time From Both (SGSide) (Pump Side) Sides From Dotl1 Sides (seconds) (lbm/sec)
I Thousand I Enthalpy (lbm/sec)
I Thousand I Enthalpy (lbm/sec)
Thousand (Bin/sec) (Btu/Ihm). (Btu/sec) (Btu/Ihm) (Btu/sec) 273.20 284.0 353.6 1,245.4 663.2 202.6 305.4 947.1 556.2 278.20 282.8 352.2 1,245.4 664.3 202.6 305.0 947.1 554.8 283.20 281.6 350.7 1,245.4 665.6 202.7 304.6 947.1 553.4 288.20 280.3 349.1 1,245.4 666.9 202.8 304.1 947.1 551.9 293.20 280.0 348.7 1,245.4 667.2 202.7 303.7 947.1 551.3 298.20 278.5 346.9 1,245.4 668.6 202.8 303.3 947.1 549.7 303.20 278.0 346.2 1,245.4 669.I 202.7 302.9 947.1 548.9 308.20 276.4 344.2 l,245.4 670.8 202.9 302.4 947.I 547*.1 313.20 275.7 343.3 1,245.4 671.5 202.8 302.0 947.1 546.1 318.20 274.9 342.3 1,245.4 672.3 202.8 301.6 947.1 545.1 323.20 273.9 341.1 1,245.4 673.3 202.8 301.2 947.1 543.9 328.20 272.8 339.7 1,245.4 674.3 202.8 300.8 947.1 542,6 333.20 271.6 338.2 1,245.4 675.6 202.9 300.3 947.1 541.1 338.20 271.1 337.6 1,245.4 676.0 202:8 300.0 947.1 540.4 343.20 269.6 335.7 1,245.4 677.6 202.9 299.S 947.1 538.6 348.20 268.7 334.6 1,245.4 678.4 202.9 299.1 947.1 537.6 353.20 267.6 *333.3 1,245.4 679.5 203.0 298.7 947.1 536.3 358.20 266.3 331.7 1,245.4 680.8* 203.1 298.2 947:1 534.7 363.20 265.6 330.7 1,245.4 681.6 203.0 297.8 947.I 533.7 368.20 264.5 329.4 1,245.4 682.7 203.0 297.4 947.1 532.4 373.20 263.8 328.5 1,245.4 683.4 203.0 297.0 947.1 531.5 378.20 262.7 327.I 1,245.4 684.5 203.'0 296.6 947.l 530.1 383.20 261.0 325.1 1,245.4 686.1 203.2 296.2 947.l 528.3 388.20 260.2 324.I 1,245.4 686.9 203.2 295.8 947.1 527.3 393.20 258.7 322.2 1,245.4 688.4 203.3* 295.3 947.1 525.5 398.20 257.6 320.8 1,245.4 689.6 203.4 294.9 947.1 524.2 403.20 256.6 319.6 1,245.4 690.5 203:4 294.5 947.1 523.0 408.20 255.3 317.9 1,245.4 691.9 203.5 294.1 947.1 521.4 413.20 254.0 316.3 1,245.4 693.2 203.6 293.7 947.1 519.9 639.85 254.0 316.3 1,245.4 693.2 203.6 293.7 947.1 519.9 639.95 106.3 131.2 I,235.2 840.9 239.7 285.1 947.1 371.0 643.20 106.2 131.1 1,235.2 841.0 239.6 284.8 947.l 370.7 1,464.90 106.2 131.1 1,235.2 841.0 239.6 284.8 947.l 370.7 Start of sump recirculation 1,465.00 89.1 109;9 1,233.3 567.6 295.3 520.3 656.7 405.2 1,613.06 89.1 109.9 1,233.3 567.6 295.3 520.3 656.7 405.2 1,613.16 85.5 98.3 1,150.6 571.2 175.3 306.9 656.7 273.6 3,600.00 70.0 80.6 1,150.6 586.6 178.1 303.6 656.7 258.7 Start of revised post-recirculation methodology C 4 l NOTES: 1. Pump Suction Break Area=; 5 .24 ft 2* Pipe inside* diameter=
2.58 ft. 2. The blowdown phase mass and energy releases are the same for Minimum and Maximum SI cases. 3. Blowdown ends at 25.2 seconds. Reflood ends at 173.1 seconds. Sump recirculation begins at 1465 seconds. All SGs depressurized to atmosphedc pressure at 3600 seconds. 4. After 3600 seconds, the revised post recirculation methodology is used, as discussed in Section 6.2.1.3.4.5.
6.2-132 Revision 18 ...... w* &deg;'*
STPEGS UFSAR TABLE 6.2.1.3-SB NOC-AE-16003347 Enclosure Attachment Page49 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Maximum SI) Time. (seconds) 0.00 0.00114 0.10 0.20 0.30 '0.40 0.50 0.60 0.70 0.80 0:90 1.00 1.10 120 1.30 1.40 1.50 1.60 1.70 1.80 1.90 2.00 2.10 2.20 2.30 2.40 2.50 2.60 2.70 2.80 2.90 3.00 3.10 3.20 3.30 3.40 3.50 3.60 3.70 3.80 3.90 4.00 4.20 4.40 4.60 Break Path No. 1 Flow {lbm/sec)
I 0,0 97,158.3 43,480.5 51,982.9 51,633.9 51,282.7 50,920.4 50,714.3 49,896.9 4.8,045.5 47,471.7 47,553.0 47,301.6 46,713.0 45,879.3 44,977.2 44,069.3 43,087.0 42,038.7 40,932.S 39,839.5 38,715.4 37,556.9 36,371.7 35,147:2 34,060.0 32,996.1 31,939.8 30,932.3 29,765.0 27,445.6 25;766.4 24,813.9 23,807.7 22,807.1 22,078.1 21,448.8 20,878.1 20,389.7 19,938A 19,505.0 19,114.4 18,464.4 17,903.6 17,483.5 (SG Side) Thousand (Btu/sec) 0.0 54,746c8 24,471.9 29,373.7 29,319.5 29,294.9 29,294.0 29,407.1 29,180:0 28,330;9 28,211.3 28,462.2 28,504.7 28,337.7 28,014.4 27,652.8 27,288.9 26,882.9 26,434.8 25,469.8 24,965:0 24,426.6 23,856.7 23,250.1 22,718.5 22,186.4 21,643.l 21,118.9 20,472.0 18,995.3 17,965.5 17,434.4 16,826.2 16,193.0 15,737.9 15,339.9 14,972.0 14,654.9 14,356.3 14,064.6 13,799.7 13,353.2 12,954.7 12,645.2 I Enthalpy (Btu/lbm) 0.0 563.5 562.8 565.l 567.8 571.2 575.3 579.9 584.8 589.7 594.3 598.5 602.6 606.6 610.6 614.8 619.2 623.9 628.8 634.0 639.3 644.8 650.4 655.9 661.5 667:0 672.4 677.6 682.7 687.8 692.l 697.2 702.6 706.8 710.0 712.8 715.2 717:1 718.7 720.0 721.1 722.0 723.2 723.6 723.3 Break Path No. 2 Flow (Ihm/sec)
I o:o 43,339.6 21,547.8 24,528.6 25,873.5 25,649.9 24,960.9 24,416.8 24,052.4 23,753.6 23,440.1 23,099.6 22,771.3 22;488.7 22,307.8 22,153.8 22,023.9 21,910.8 21,829.6 21,785.3 21,742.5 21,660.5 21,545.6 21,371.8 21;088.3 20,894.6 20,712.4 20,514.2 20,313.0 20,113.0 19;902.8 19,688.4 19,480.3 19;276.4 19,070.0 18,852.2 18,643.2 18,453.8 18,266.8 18,076.3 17,883.0 17,705.0 17,375.2 17,046.4 16,753.7 6.2-133 (Pulnp Side) Thousand (Btu/sec) 0.0 24,348.1 12,088.3 13,777.6 14,546.5 14,432:9 14,057.0 13,760.3 13,561.7 13;396.9 13,222.0 13,030.6 12,845.1 12,685.9 12,584.1 12,497.8 12,425.0 12,361.3 12,315.5 12,290.8 12,267.2 12,221.1 12,156.0 12,057.1 11,896.7 11,787.9 11,685.5 11,573.9 11,460.6 11,348.2 11,230.2 11,109.8 10,993.1 10,879.0 10,763.4 10,641.4 10,524.4 10,418.7 10,314.4 10,208.1 10,100.l 10,000.9 I 9,817.4 9,634.3 9,471.7 I Enthalpy (Btu/lbm) 0.0 561.8 561.0 561.7 562.2 562.7 563.2 563.6 563.8 564,0 564.1 564.l 564.1 564.1 564.1 564.I 564.2 564.2 564.2 564.2 564.2 564.2 564.2 564.2 564.1 564.2 564.2 564.2 564.2 564.2 564.2 564.3 564.3 564.4 564.4 564.5 564.5 564.6 564.7 564.7 564.8 564.9 565.0 565.2 565.3 Total Mass From Both Sides (lbm/sec) 0.0 140,497.9 65;028.3 76,511.5 77,507.4 76,932.6 75,881.3 75,131.1 73,949.4 71,799.1 70,911.8 70,652.7 70,072.9 69,201.7 68,187.1 67,131'.0 66,093.2 64,997.8 63,868.3 62,717.8 60,375.9 59,102.4 57,743.5 54,954.6 53,708.6 52;454.0 51;245.3 49,878.0 47,348.4 45;454.8 44,294.2 43,084.l 41,877.1 40,930.3 40;092.0 39,331.9 38,656.5 38,014.7 37,388. l 36,819.4 35,839.6 34,950.0 34,237.2 Total Energy From Both Sides Thousand (Btu/sec) 0.0 79,094.8 36,560.2 43,151.3 43,866.0 43,727.8 43,351.0 43,167.3 42,741.7 41,727.8 41,433.3 41,492.8 41,349.8 41,023.6 40,598.6 40,150.5 39,713.9 39,244.1 38,750.3 31l,241.4 37,737.0 37,186.1 36,582.6 35,913.8 35,146.8 34,506.4 33,871.9 33,217.0 32,579.6 31,820.2 30,225.5 29,075.2 28,427.6 27,705.1 26,956.4 26,379.3 25,864.3 25,390.8 24,969.4 24,564.4 . 24,164.7 23,800.6 23,170.6 22,589.0 22,116.9 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-5B (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 50 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 4.80 5.20 5.40 S.60 5.80 6.00 6.20 6.40 6.60 6.80 7.00 7.20 7.40 7.60 7.80 8.00 8.20 8.40 8.60 8.80 9.00 9.20 9.40 9.60 9.80 10.00 10.20 10.40 10,60 10.80 11.00 11.20 11.40 11.60 11.80 12.00 12.20 12.40 12.60 12,80 13.00 13.20 13.40 13.60 13.80 14.00 14.20 14.40 14.60 14.80 Break Path No. 1 Flow (lbm/sec)
I 17,144.9 17,002.0 17,031.9 16,900.2 15,466.8 14,376.0 14,657.9 15,346.8 15,997.4 16,544.7 16,993.7 17,301.2 17,454.4 17,610.0 17,829.7 17,5f24.S 17,836.0 17,825.2 17,956.9 17,676.8 17,077.6 16,898.6 17,090.6 16,910.7 14,830.5 12,649.1 12,658.6 12,797.8 11,922.0 11,736.9 12,081.0 11,784.2 11,410.1 12,022.0 12,800.0 11,778.0 10,425.1 10,397.9 10,018.5 9,733.9 9,876.1 9,734.l 9,607.8 9,972.8 9,909.5 9,207.4 9,198.0 8,859.7 8,566.4 8,533.4 (SGSide) Thousand (Btu/sec) 12,380.3 12,201.1 12,141.1 12,240.9 11,897.2 11,430.7 11,492.0 11,800.3 12,!()7.9 12,356.4 12,521.2 12,567.4 12,526.1 12,526.9 12,592.3 12,575.6 12,454.6 12,420.5 12,483.5 12,241.5 11,811.4 11,709.6 11,826.0 11,644.8.
10,196.8 8,828.0 9,020.5 9,094.0 8,448.l 8,446.7 8,773.4 8.,497.8 8,242.3 8;705.2 9,129.8 8,305.9 7;479.6 7,613.8 7,345.8 7,184.7 7,359.2 7,235:4 7,128.7 7,373.l 7,230.9 6,740.9 6;827.9 6,572.9 6,402.9 6,474.8 I Enthalpy (Bh1/lbm) 722.1 717.6 712.8 724.3 769.2 795.1 784.0 768.9 756.9 746.9 736.8 726.4 717.6 711.4 706.3 70L6 698.3 696.8 695.2 692.5 691.6 692.9 692.0 688,6 687.6 697.9 712.tS 710,6 708:6 719.7 726.2 721.1 722.4 724.1 713.3' 705.2 717.5 732.2 733.2 738.l 745.2 743.3 742.0 739.3 729.7 732.l 742.3 741.9 747.4 758.8 (Maximum SI) Break Path No. 2 Flow (lbm/sec)
I 16,458.5 15,778.8 15,592.9 15,241.3.
15,053.8 16,196.3 15,89.5.2 15,813.2 15,629.5 15,430.6 15,310.6 15,127.2*
14,903.7 14,723.3 14,506.8 14,289.4 14,107.1 13,922.3 13,698.3 13,487.0 13,366.6 13,192.2 12,944.4 12,758:2 12,709,0 13,118.2 12,514.9 12,318.5 12,796.2 12,339.2 12,043.5 12,135.5 12,060,5 11,676.4 11,454.4 11,582.3 11,903.4 11,064.1 11,629.6 11,276.7 11,!00.7 11,058.9 10,975.5 10,604.9 10,672.5 10,751.l 10,242.6 10,609:9 10,296.8 10,211.7 (Pump Side) Thousand (Btu/sec) 9,307.4 8,926.8 8,826.8 8,629.2 8,528.0 9,180.7 9,009.6 8,967.1 8,865.9 8,756.7 8,692.4 8,590.1 8,463.6 8,361.l 8,237.2 8,113.0 8,009.0 7,903.6 7,7.75.5 7,655,0 7.,586.8 7,486.7 7,344.6 7,238.8 7 ,211.9 7,446.2 7,092.9 6,983.I 7,260.6 6,994.l 6,825.4 6,881.3 6,838.9 6,616.S 6,491.8 6,569.0 6,749.6 6,264.2 6,594.0 6,388.8 6,292.2 6,270.0 6,225.l 6,01'4.2 6,057.1 6,104.7 5,817.7 6,035.7 5,861.4 5;827.7 I Enthalpy (Btullbm) 565.5 565.7 566.1 566.2 566.5 566.8 566.8 567.1 567.3 567.5 567.7 567.9 567.9 "567.9 567.8 567.8 567.7 567.7 567.6 567.6 567.6 567.5 567.4 567.4 567.5 567.6 566.8 566.9 567.4 566.8 566.7 567.0 567.1 566.7 566.7 567.2 567.0 566.2 567.0 566.5 566.8 567.0 567.2 567.1 567.5 567:8 568.0 568.9 569.2 570.7 Total Mass From Both Sides (lbm/sec) 33;603.4 .32,780.7 32,624.8 32,141.5 30,520.6 30,572.3 30,553.2 3.1,160.1 31,626.9 31,975.3 32,304.3 32,428.4 32,358.1 32,333.3 32,336.4 32,213.9 31,943.1 31,747.5 31,655.2 31,163.8 30,444.2 30,090.8 30,035.1 29,668.9 27,539.5 25,767.3 25,173.5 25,116.3 24,718.l 24,076.0 24,124.5 23,919,7 23,470.5 23,698.5 24,254.4 23,360.3 22,328.4 21,462.1 21,648.l 21,010.6 20,976.8 20,792.9 20,583.3 20,577.6 20,582.0 19,958,5 19,440.7.
19,469.6 18,863.2 18,745.1 Total Energy From Both Sides Thousand "(Btu/sec) 21,687.7 21,127.8 20,967.8 20,870.0 20,425.2 20,611.4 20,501.7 20,767.5 20,973.8 21,113.T 21,213.6 21,157.5 20;989.7 20,888.0 20,829.6 20,688.6 20,463.6 20,324.1 20,259.0 19,896.5 19,398.2 19,196.3 19,170.6 18,883.5 17,408.8 16,274.2 16,113.4 16,077.1 15,708.6 15,440.8 15,598.8 15,379.1 15,081.3 15,321.8 15,621.5 14,874.9 14,229.3 13,877.9 13,939.8 13,573.5 13,651.4 13;505.4 13,353.7 13,387.3 13,288. I 12,845.6 12,645.5 12,608.5 12,264.3 12,302.5 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-5B (continued)
NOC*AE*16003347 Enclosure Attachment Page 51 of 77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Maximum SI) Break Path No. 1 Flow Break Path No. 2 Flow Total Mass Total Energy From Time From Both (SG Side) (Pump Side) Sides Both Sides (seconds) (lbtn/sec)
I Thousand I Enthalpy (lbm/sec)
I Thousand I Enthalpy (lbm/sec)
Thousand (Btu/sec) (Btu/sec) (B!LJ/lbm) (Btu/sec) (Btu/lbm) 15.0ff 8,2!ip 6,319.6 769.2 10,063.9 5,745.5 570.9 18,280.1 12,065.1 15.20 8,116.9 6,272.4 772.8 9,886.0 5,654.2 571.9 18,002.9 11,926.6 15.40 8,J 11.4 6,214.1 766.1 9,718.4 5,562.7 572.4 17,829.8 11,776.8 15.60 7,997.5 6,067.5 758.7 9,736.5 5,583.5 573.5 . 17,734.0 11,651.0 15 .so-7,981.8 6,028.7 755.3 9,444.5 5,428.5 574.8 17,426.2 11,457.2 16.00 7;827.7 5,894.1 753.0 9,559.1 5,508.9 576.3 17;386.9 11,403.1 16:20 7,670.7 5,794.8 755.4 9,331.2 5;405.3 579.3 17,001.9 11,200.0 16.40 7,560.1 5,759.4 761.8 9,310.0 5,419.4 582.l 16,870.l 11,178.8 16.60 7,435.8 5,732.5 770.9 9,144.5 5,356.4 585.8 16,580.2 11,088.9 16.80 7,286.3 5,586.3 780.4 8,976.1 5,287.4 589.0 16,262.4 10,973.{)
17.00 7,157.4 5,633.2 787.0 8,762.9 5,196.7 593.0 15,920.4 10,829.9 17.20* 7,050.4 5,571.& 790.3 8,538.6 5,097.8 597.0 15,589.0 10;669.6 17.40 6,958.0 5,516.4 792.8 8,327.4 5,015.3 602.3 15;285.4 10,531.7 17.60 6,849.1 5,460.8 797.3 8,119.3 4;942.0 608.7 14,968.4 10,402.8 17.80 6,723.l 5,414.2 805.3 7,902.6 4,875.6 617.0 14,625.7 10,289.8 18.00 6,585.5 5,382.0 817.3 7,668.1 4,807.5 626.9 14,253.6 10,189.5 18.20 6,430.2 5,356.2 833.0 7,44.1.3 4,749.7 638.3 13,871.6 10,105.9 18.40 6,261.9 5,327.l 850.7 7,187.1 4,681.0 651.3 13,448.9 10,008.0 18.60 6,107.3 5,301.0 868.0 6,981.9 4,661.7 667.7' 13,089.2.
9,962.7 18.80 5,941.4 5,251.4 883.9 6,470.9 4,522.9 699:0 12,412.3 9,774.3 19.00 5,702.7 5,205.0 912.7 5,996.7 4,374.5 729.5 11,699.4 9,579.5 19.20 5,251.8 5,128.4 976.5 5,581.4 4,262.8 763.7 10;833.l 9,391.1 19.40 4,598.8 4,953.8 1,077.2 5,082.1 4,145.8 815.8 9,680.9 9;099.6 IMO 3,926.3 4,649.5 1,184.2 4,413.1 4,052.0 918.2 8,339.4 8,701.5 19:80 3,408.6 4,188.7 1,228.9 2,536.6 2,869.l 1,131.J 5,945.1 7;057.8 20.00 3,024.3 3,747.2 1,239.0 1,724.2 2,095.5 1,215.3 4,748.5 5,842.7 20.20 2,731.6 3,399.5 1,244.5. 1,504.4 l,859.6 1,236.2 4,236.0 5,259.1 20.40 2,468.3 3,081.6 1,248.5 1,351.9 1,681.7 1,243.9 3,820.2 4,763.3 20.60 2,239.0 2,803.8 1,252.3 1,229.0 1,535.2 1,249.1 3,468.0 4;339.0 20.80 2,048.2 2,571.6 1,255.6 1,110.7 1,392.9 1,254.1 3;158.9 3,964.5 21.00 1,892.3 2,381.5 1,258.5 1,480.9 1,611.7 1,088.4 3,373.2 3,993.2 21.20 1,796.6 2,265.5 1,26LO 2,572.9 1,432.5 556.7 4,369.5 3,698.0 21.40 1,711.4 2,160.7 1,262.5 2,837.4 1,364.0 480:7 4,548.9 3,524.7 21.60 1,619.6 2,046.9 1,263.8 3,167.8 1,406.2 443.9 4,787:4 3;453.0 21.80 1,501.7 1,899.3 1,264.8 3,156.0 1,336.7 423.5 4,657.7 3,236.0 22.00 1,388.1 1,758.3 1,266.8 2,799.3 1,149.5 410.6 4,187.4 2,907.8 22.20 1,275.2 1,617.3 1,268.2 2,433.4 977.0 401.5 3,708.6 2,594.3 22.40 1,171.6 1,487.4 1,269.6 2,162.1 850.7 393.5 3,333.7 2,338.2 22.60 1,045.0 1,328.9 1,271.7 1,952.0 751.4 385.-0 2,996.9 2,080.3 22.80 946.3 1,204.8 1,273.1 1,774.9 666.0 375.2 2,721.2 1,870.8 23.00' 877.3 1,118.2 1,274.7 1,635.9 597.7 365.3 2,513.1 1,715.9 23.20 831.5 1,060.7 1,275.6 1,731.5 613.6 354A 2,563.0 1,674.3 23.40 802.0 1,023.6 1,276.4 *2,058.5 696.1 338.2 2,860.5 1,719.8 23.60-775.7 990.4 1,276.9 2,539.4 819.5 322.7 3,315.1 1,810.0 23.80 727.1 928.6 1,277.1 3,217.9 995.9 309.5 3,945.1 1,924.5 24.00 557.7 712.0 1,276.5 3,471.3 1;035.2 2982 4,029.0 1,747.1 24.20' 453.5 579.7 1,2783 2;353.0 685.2 291.2 2,806.5 1,264.9 24.40 375.8 480.8 1,279.4 1,269.5 365.6 288.0 1,645.3 846.4 24.60 279.1 357.3 1,280.4 543.6 156.0 285.9 822.6 513.3 24.80 168.9 216.5 1,281.9 91.9 26.4 287.1 260.8 242.9. 25.00 37.6 48.4 1,285.8 0.0 0.0 0.0 37,6' 48.4 25.20 o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 6.2-135 Revision 18 w ..... w 0\ I j 1. I I ' I STPEGS UFSAR TABLE 6.2.l.3-5B (continued)
NOC-AE-16003347 Enclosure Attachment Page 52 of77 . DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Maximum SI) Break Path No. 1 Flow Break Path No. 2 Flow Tota!Mass Total Energy From Time From Both (SGSide) (Pump Side) Sides Both Sides (seconds)
(!bm/sec)
I Thousand 1
* Enthalpy (lbm/seo)
I Thousand I Enthalpy (lbm/scc)
Thousand (Btu/sec) (Btu/sec) (Btu/lbm) (Btu/sec) (Btu/lbm)
End ofBlowdown 25.65 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 25.75 0.0 0.0 0.0 0.0 0;0 o.o 0.0 0.0 25.85 0,1) 0.0 0.0 0.0 0.0 0.0 0.0 0.0 25.95 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.1) 26.05 0.0 0.0 0;0 0.0 0.0 0.0 o,o 0.0 26.28 56.5 66.7 . 1,180.8 0.0 0:0 0.0 56.5 66.7 26.38 58.3 68.9 1,180.8 0.0 0.0 0.0 58.3 68.9 26.48 66.I 78.0 1,180.9 0.0 0.0 0.0 66.1 78.0 26.58 73.8 87.2 1,180.9 0.0 0.0 0.0 73.8 87;2 26.68 81.I 95.8 1,180.9 0.0 0.0 0.0 &1.1 95.8 26.78 88.I 104.0 1,181.0 0.0 0.0 0.0 88.1 104.0 26.85 93.1 109.9 1,181.0 0.0 .0.0 0.0 93.1 109.9 26.88 94.7 111.8 1,181.0 0.0 0.0 0.0 94.7 111.8 26.98 lOLO 119.2 1,181.I 0.0 0.0 0.0 IOLO 119.2 27.08 107.0 126.3 1,181.l 0.0 0.0 0.0 107.0 126.3 .27.18 112.7 133.1 1,181.1 0.0 0.0 0.0 112,7 133.1 27.28 118.2 139.7 1,181.2 0.0 0.0 0.0 118.2 139.7 27.38 123.6 146.0 1,181.2 0.0 0:0 0.0 123.6 146.0 27.48 128.7 152.1 1,181.3 0.0 0.0 0.0 128.7 152.I 27.58 133.7 158.0 1,181.3 0.0 0.0 0.0 133.7 158.0 27.68 138.6 163.7 1,181.3 0.0 0.0 0.0 138.6 163.7 27.78 143.3 169.2 1,181.4 0.0 0.0 0.0 143.3 169.2 27.88 147.8 174.6 1,181.4 0.0 0 .. 0 0.0 147.8 174.6 27.98 152.3 179.9 1,181.5 0.0 0.0 0.0 152.3 179.9 28.08 156.6 185.0 1,181.5 0.0 0.0 0.0 156.6 185.0 28.18 160.9 190.1 1,181.5 0,0 0.0 0.0 160.9 190.I 28.28 165.0 195.0 l,181.6 0.0 0.0 0.0 165.0 195,0 29.28 202.I 238.9 1,182.0 0.0 0.0 0.0 202.1 238.9 30.00 768.7 915.4 1,190.8 6,636.7 910.3 137.2 7,405.4 1,825.7 30.30 808.8 963.9 1,191.8 6,942.3 988.6 142.4 7,751.I 1,952.5 31.30 806.1 960.8 1,191.9 6,925.2 997.7 144.1 7,731.3 1,958.5 32.30 795.6 948.1 1,191.7 6;828.4 986.0. 144.4 7,624.0 1,934.1 32.70 790.1 941.4 1,191.6 6,786.0 980.9 144.5 7,576.J 1,922.3 33.30 895.8 1,068.6 1,192.9 7,651.0 1,096.6 143.3 8,546.8 2,165.2 34.30 865.2 1,032.2 1,193.1 7,506.6 1,074.0 143.1 8,371.8 2,106.3 35.30 854.0 1,018.7 1,192.9 7,404.2 1,061.0 143.3 8,258.2 2,079.7 35.80 848.6 1,012.1 1,192.8 7,353.3 1,054.6 143.4 8,201.8 2,066.7 36.30 843.2 1,005.7 1,192.7 7,302.8 1,048.2 143.5 8,146.0 2,053,g 37.30' 832.9 993.2 1,192.4 7;203.6 1,035.8 143.8 8,036.5 2,029.0 38.30 823.1 981.3 1,192.2 7,107.1 1,023.7 H4.0 7,930.2 2,005.1 39.30 813.8 970.l 1,192.0 7,013.3 1,012.I 144.3 7,827.1 1,982.2 40.30 805.0 959.4 1,191.9 6,922.5 1,001.0 144.6 7,727.5 1,960.4 41.30 796.6 949:2 1,191.7 6,834.6 990.3 144.9 7,631.l 1,939.5 42.30 786.7 937.3 1,191.5 6,751.1 980.3 145.2 7,537.8 1,917.6 43.00 780.0 929.3 1,191.4 6,694.3 973.6 145.4 7,474.2 1,902.9 43.30 777.2 925.9 1,191.3 6,670.3 970.8 145.5 7,447.4 1,896.6 44.30 768.0 914.9 1,191.2 6,592.0 961.5 145.9 7,360.l 1,876.4 45.30 759.3 904.3 1,191.0 6,516.2 952.6 146.2 7,275.5 1,856.9 46.30 750.8 894.1 1,190'.9 6,442.8 943.9 146.5 7,193.6 1,838.0 47.30 562.3 669.5 1,190.8 1,683.5 491.7 292.1 2,245.7 1,161.2 48.30 346.6 410.4 1,184.0 953.2 280.8 294.5 1,299.8 691.l 6.2-136 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-SB (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 53 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 49.30 50.30 51.30 52.30 53.30 53.40 54.30 55.30 56.30 57.30 58.30 59.30 60.30 61.30 62.30 63.30 64.30 65.30 66.30 67.30 68.30 69.30 69.60 70.30 71.30 72.30 73.30 74.30 75.30 76.30 77.30 78.30 79.30 80.30 81.30 82.30 83.30 84.30 85.30 86.30 87.40 88.30 90.30 92.30 94.30 96.30 98.30 100.30 102.30 104.30 106.30 106.90 108.30 Break Path No. 1 Flow (SG Side) I Thousand (lbm/sec)
* (Btu/sec)
I Enthalpy (Btu/lbm) 326.1 315.5 306.6 297.9 288.7 287.7 278.9 268.3 256.8 244.4 234.3 227.1 226.1 225.7 225.3 224.8 224.4 224.0 223.6 223.2 222.8 222.4 222.3 222.0 221.6 221.3 220.9 220.5 220.1 219.7 219.3 219.0 218.6 218.2 217.8 217.5 217.1 216.7 216.3 216.0 215.6 215.2 214.5 213.8 213.0 212.3 211.6 210.9 210.2 209.5 208.8 208.6 208.l 386.0 373.4 362.9 352.4 341.5 340.4 329.9 317.4 303.7 289.0 277.1 2685 267.3 266.8 266.3 265.8 265.3 264.9 264.4 263.9 263.4 263.0 262.8 262.5 262.0 261.6 261.1 260.7 260.2 259.7 259.3 258.8 258.4 258.0 257.5 257.1 256.6 256.2 255.7 255.3 254.8 254.4 253.5 252.7 251.8 251.0 250.1 249.3 248.4 247.6 246.8 246.5 245.9 1,183.7 1,183.5 1,183.4 1,183.2 1,183.1 1,183.1 1,183.0 1,182.8 1,182.7 1,182.5 1,182.4 1,182.3 1,182.3 1,182.3 1,182.3 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 1,182.2 l,182.2 1,182.1 1,182.1 f,182.l 1,182.1 1,182.1 f,182.1 1,182.1 1,182.1 1,182.l 1,182.l l,182.l 1,182.1 1,182.1 1,182.1 1,182.0 (Maximum SI) Break Path No. 2 Flow .. ,.. (Pump Side) (lbm/sec)
I Thousand I Enthalpy. (Btu/sec) (Btlll'lbm) 986.4 285.7 289.6 1,003.5 288.4 287.4 1;017.8 290.7 285.6 1,031.9 293.0 284.0' 1,046.6 295.5 282.4 1,048.1 295.8 282.2 l,062.1 298.2 280.8 1,078.8 301.2 279.2 1,096.7 304.5: 277.7 1,116.9 308.4 276.1 1,132.4 311.5 275.0 1,143.9 313.4 274.0 1,145.9 313.5 273.6 1,147.1 313.4 273.2 1,148.2 '3133 272.9 1,149.4 313.2 272.5 1,150.6 313.1 272.1 1,151.8 313,0 271.8 1,153.0 312.9 271.4 1,154.1 312.9 271.l 1,155.3 312.8 270.7 1,156.6 312.7 270.4 1,156.9 312.7 270.3 1,157.8 312.6 270.0 1,159.0 312.5 269.7 1,160.2 312.5 269.3 1,161:5 312.4 269.0 1,162.7 312.3 268.6 1,163.9 312.2 268.3 1,165.2 312.2 267.9 1,166.4 312.l 267.5 1,167.7 312.0 267.2 1,169.0 311.9 266.8 1,170.3 311.9 266.5 1,171.5 311.8 266.1 1,172.8 311.7 265.8 1,174.1 311.7 265.4 1,175.5 311.6 265.l 1,176.8 311.5 264.7 1,178.1 311.5 264.4 1,179.6 311.4 264.0 1,180.8 311.3 263.7 1,183.4 311.2 263.0 1,186.0 311.0 262.3 1,188.6 310:9 261.5 1,191.1 310.7 260.8 1,193.7 310.5 260.l 1,196.2 310.4 259.4 l,198.7 310.2 258.7 1,201.2 310.0 258.0 1,203.7 309.8 257.3 1,204.4 309.7 257.1 f,206.2 309.6 256.6 6.2-137 Total Mass Fr01hBoth Sides (Ihm/sec) 1,312.5 1,319.0 1,324.4 1,329.7 1,335.2 1,335.8 1,341.0 1,347.1 1,353.5 1,361.3 1,366.8 1,371.0 1,372.0 1,372.( 1,373.5 1,374.2 1,375.0 1,375.8 1,37.6.6 1,377.4 1,378.2 1,379.0 1,379.2 1,37.9.8 1,380.6 1,381.5 1,382.3 1,383.2 1,384.0 1,384.9 1,385.8 1,386.7 1,387.6 1,388.5 1,389.4 1,390.3 1,391.2 1,392.2 1,393.1 f,394.1 1,395.l 1,396.0 1,397.9 1,399.7 1,401.6 1,403.4 1,405.3 1,407.1 1,408.9 1,410.7 1,412.5 1,413.0 1,414.2 Total Energy From Both Sides Thousand (Btu/sec) 671.7 661.7 653.5 M5.5 637-.1 {;36.2 628.1 618.6 608.2 597.4 588.5 581.9 580.8 580.2 579.6 579.0 578.5 577.9 577.3 576.8 576.2 575.7 575.5 575.1 574.6 574.0 573.5 573.0 572.4 571.9 571.4 570.9 570,3 569.8 569.3 568.8 568.3 567.8 567.3 566.7 566.2 565.7 564.7 563.7 562.7 561.7 560.6 559.6 558.6 557.6 556.5 556.2 555.5 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-5B (continued)
NOC-AE-16003347 Enclosure Attachment Page 54 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 110.30 112.30 114.30 116.30 118.30 120.30 i22.30 124.30 126.30 128.30 128.70 130.30 132.30 134.30 136.30 138.30 140.30 142.30 144.30 146.30 148.30 150.30 152.30 153.60 154.30 156.30 158.30 160.30 162.30 164.30 166.30 168.30 170.30 172.30 174.30 176.30 178.30 180.30 182.30. 183.80 184.30 186.30 188.30 190.30 192.30 194.30 196.30 198.30 200.30 202.30 204.30 206.30 208.30 Break Path No. 1 Flow (lbm/sec)
I 207.4 206.7 206.0 205.4 204.7 204.l 203.4 202.8' 202.2 201.6 . 201.5 201.0 200A 199.8 199.3 198.7 198.1 197.6 197..1 196.5 196.0 195.5 195.0 194.7 194.5 194.0 193.6 193.1 192.6 192.2 191.8 191.3 190.9 190.5 190.1 189.7 189.4 189.0 188.7 188.5 188.4 188.I 187.8 187.5 187.1 186.6 186.2 185.8 185.3 184.8 184.2 183.7 183.3 (SG Side) Thousand I Enthalpy (Btu/sec) (Btu/lbm) 245.1 244.3 243.5 242.8 242.0 241.2 240.5 239.7 239.0 238.3 238.1 237.6 236.9 236.2 235.5 234.8 234.2 233.5 232.9 232.3 231.7 231.1 230.5 230.1 229.9 229.3 228.8 228.2 227.7 227.I 226.6 226.I 225.6 225.2 224.7 224.3 223.8 223.4 223.0 222.7 222.6 222.3 221.9 22-J.6 221.l 220.6 220.I 219.6 219.0 218.4 217.7 217.I 216.6 1,182.0 1,182.0 1,182.0 1,182.0 1,182.-0 1,182.0 1,182.0 1,182.0 1,182.0 1,182.0 1,182.0 1,182.0 1,182.0 1,182.0 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181;9 1,181.9 1,181.9 1,181.9 1,181:9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.9 1,181.8 1,181.8 1,181,8 1,181.8 1,181.8 1,181.8 1,181.8 1,181.8 1,181.8 1, 181.8 1,181.8 1,181.8 1,181.8 1,181.8 1,181.8 1,181.8. 1,181.8 1,181.8 1,181.8 (Maximum SI) Break Path No. 2 Flow (lbm/sec)
I 1,208.6 1,211.0 1,213.5 1,215.9 1,218.2 1,220.6 1,222.9 1,225.3 1,227.6 1,229.9 1,230.4 1,232.2 1,234.5 1,236.8 1,239.0 1,241.3 1,243.6 1,245.8 1,248.0 1,250.3 l,252.5 1,254.8 1,257.0 1,258.5 1,259.3 1,261.5 1,263.8 1,266.l 1,268.4 1;270.7 1,273.0 1,275.3 1,277.7 1,280.0 1,282.4 1,284.9 1,287.4 1,289.9 1,292.5 1,294.5 1,295.1 1,297.9 1,300.7 1,303.6 1,304.2 1,304.7 1,305.3 1,305.8 1,305.4 1,304.0 1,303.0 1,302.2 1,301.7 6.2-138 (Pump Side) Thousand (Btu/sec) 309.4 309.1 308.9 308.7 308.5 308.2 308.0 307.8 307.5 307.3 307.3 307.1 306.8 306.6 306.4 306.1 305.9 305.7 305.4 305.2 305.0 304.7 304.5 304.4 304.3 304.1 303.9 303.7 303.5 303.3 303.1 302.9 302.7 302.6 302.4 302.3 302.2 302.1 302,0 301.9 301.9 301.9 301.9 301.9 301.3 300.8 300.3 299.8 299.0' 298.0 297.1 296.3 295.5 I Enthalpy (Btu/lbm) 256.0 255.3 254.6 253.9 253.2 252.5 251.9 251.2 250.5 249.9 249.7 249.2 248.6 247.9 247.3 246.6 246.0 245.4 244.7 244.1 243.5 242.9 242.3 241.9 241.6 241.0 240.4 239.8 239.2 238.7 238.1 237.5 236.9 236.4 235.8 235.3 234.7 234.2 233.6 233.3 233.1 232.6 232.l 231.6 231.l 230.6 230.l 229.6 229.0 228.5 228.0 227.5 227.0 Total Mass From Both Sides (Ibmlsec) 1,416.0 1,417.8 1,419.5 1,421.2 1,423.0 1,424.7 1,426.4 1,428.l 1,429.8 1,431.5 1,431.8 1,433.2 1,434.9 1,436.6 1,438.3 1,440.0 1,441.7 1,443.4 1,445.1 1,446.8 1,448.5 1,450.3 1,452.0 1,453.2 1,453.8 1,455.6 1,457.3 1,459.2 1;461.0 1,462.8 1,464.7 1,466.6 1,468.6 1,470.6 1,472.6 1,474.6 1,476.8 1,478.9 1,481.2 1,482.9 1,483.5 1,485.9 1,488.5 1,491.1 1,491.2 1,491.4 1,491.5 1,491.6 1,490.7 1,488.8 1,487.2 1,486.0 1,485.0 Total Energy From Both Sides Thousand (Btu/sec) 554.5 553.5 552.5 551.5 550.5 549.5 548.5 547.5 546.5 545.6 545.4 544.6 543.7 542.8 541.9 541.0 540.1 539.2 538.3 537.5 536.7 535.8 535.0 534.5 534.2 533.4 532.6 531.9 531.l 530.4 529.7 529.0 528.4 527:7 527.1 526.5 526.0 525.5 525.0 524.7 524.6 524.2 523.8 .523.5 522.4 521.4 520.4 519.4 518.0" 516.4 514.9 513.4 512.1 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-SB (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 55 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 210.30 212.30 214.30 216.30 218.30 220.00 220.10 225.10 230.10 235.10 240.10 245.JO 250.10 255.10 260.10 265.10 270.10 275.10 280.10 285.10 290.10 295.10 300.10 305.10 310.10 315.10 320.10 325.10 330.10 335.10 340.10 345.10 350.10 355.10 360.10 365.10 370.10 375.10 380.10 385.10 390.10 395.10 400.10 405.10 410.10 415.10 420.10 425.10 430.10 435.10 440.10 Break Path No. 1 Flow (lbm/sec)
I 182.8 182.3 181.8 181.4 180.9 180.5 201.8 202.9 202.3 201.6 202.7 202.0 201.4 202.4 201.8 201.Z. 202.l 201.5 200.8 201.8 201.1 200.5 201.4 200.7 200,0 200,9 200,2 201.1 200.4 199.7 200.S 199.8 200.6 199.9 199.1 199.9 199.2 199.9 199.1 198.4 199.l 198.3 199.0 198.3 199.2 198.5 197.9 198;6 198.0 198.7 198.0 (SG.Side)
Thousand I Enthalpy (Btu/sec) (Btu/lbm) 216.0 215.4 214;9 214.3 213.8 213.3 254.2 255.5 254.7 253.9 255.2 254.4 253.7 254.9 254.1 253.3 254.5 253.7 252.9 254.1 253.3 252.4 253,6 252.7 251.9 253.0 252.1 253.2 252,3 251.5 252.5 251.6 252.6 251.7 250.8 251.7 250.8 251.7 250.8 249.8 250.7 249.7 250.6 249.8 250 .. 8 250.0 249.2 250.1 249.3 250.2 249.3 1,181.8 1,181.8 1,181.8 1,181.8 1,181.8 1,181.7 1;259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259,3 1,259.3 1,259,3 1,259.3 1,259.3 1,259.3 1,259,3 1,259,3 1,259.3 1,259.3 1,259.3 1,259,3 1,259.3 1,259.3 1,259.3 1,259.3 1,259,3 1,259.3 1,259.3 1,259,3 1,259,3 1,259.3 1,259.3 1,259,3 1,259.3 1,259,3 1,259.3 1,259.3 1,259.3 1,259.3 1,259,3 1,259;3 1,259.3 1,259.3 1,259,3 1,259,3 1,259.3 (Maximum SI) Break Path No. 2 Flow Total Mass From Both (Pwnp Side)* (Ibm/sec)
I Thousand (Btu/sec) 1,301.4 294.8 1,301.2 294.0 1,301.2 293.3 1,301.3 292,7 1,301.6 292.0 1,301.9 291.5 End ofReflood 1,395,0 290.2 1,394.0 289.7 l,394.6 289.6 1,395.2 289.6 1,394.2 289,0 1,394.8 289.0 1,395.4 288.9 1,394.4 288.4 1,395.1 288.3 1,395.7 288.2 1,394.7 287.7 1,395.4 287.7 1,396.0 287;6 1,395.1 287.1 1,395.7 287.0 1,396.4 287.0 1,395,5 286.5 1,396,2 286.4 1,396.8 286.4 1,395,9 285,9 1,396,6 285,8 1,395.8 285.3 1,396.5 285.3 1,397.2 285.2 1,396,3 284.7 1,397.f 284.7 1,396.3 284.2 1,397.0 \ 284.2 1,397.7 284.1 1,397.0 283.7 1,397.7 283,6 1,397.0 283.2 1;397.7 283.1 1,398.5 283,I 1,397.8 282.6 1,398.6 282.6 1,397.9 282.I 1,398.5 282.1 1,397.7 281.6 J,398.3 281.5 1,399.0 281.5 1,398.2 281.0 1,398.9 280.9 1,398.2 280.5 1,398.8 280.4 6.2-139 I Enthalpy (Btu/lbm) 226.5 226,0 225.4 224.9 224.4 223,9 Sides (lbm/sec) 1,484.1 1,483,5 1,483.0 1,482.7 1,482,5 1,482.5 208.0 1,596.9 207.8 1,596.9 207.7 1,596.9 207.5 1,596;9 207.3 1,596.9 207.2 1,596.9 207.0 1,596.9 206.8 1,596.9 206.7 1,596.9 206.5 1,596.9 206.3 1,596,9 206.2 1,596;9 206.0 1,596.9 205.8 1,596.9 205.7 1,596.9 205.5 1,596.9 205.3 1,596.9 205. l 1,596.9 205,0 1,596.9 204. 8 1,596.9 204.6 1,596.9 204.4 1,596.9 204.3 1,596.9 204.1 1,596.9 203.9 1,596.9 203.8 1,596.9 203.6 1,596.9 203.4 1,596.9 203.3 1,596.9 203.1 1,596,9 202.9 1,596,9 202.7 1,596.9 202.6 1,596.9 202.4 1,596.9 202.2 1,596.9 202.1 1,596.9 201.8 1,596.9 201.7 1,596.9 201.5 1,596.9 201.3 1;596.9 201.2 1,596.9 201.0 1,596.9 200.8 1,596.9 200.6 1,596.9 200.5 1,596.9 Total Energy From Both Sides Thousand (Btu/sec) 510.8 509.5 508.2 507,0 505.8 504.9 544.4 545.2 544.3 543.5 544.3 543.4 542.5 543.3 542.4 541.6 542.3 541.4 540.5 541.2 540.3 539.4 540.1 539.2 538.2 538.9 537..9 538.5 537.6 536.7 . 537.2 536.3 536.8 535.9 534.9 535.4 534.4 534.9 533.9 532.9 5333 532.3 532.7 531.8 532.4 531.5 530,6 531.l 530.2 530.7 529.8 Revision 18 Q 0.i* ...... (.;.) 0\
STPEGS UFSAR TABLE 6.2.l.3-5B (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 56 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES Time (seconds) 445.10 450.10 455.lo 460.10 465.10 470.10 475.10 4ilo.io 485.10 490.10 495.10 500.10 . 505.10 510.10 515.10 520.10 525.10 530.10. 535.10 540.10 545.10 550.10 555.10 560.10 565.10 570.10 575.10 580.10 585.10 590.10 595.10 600.10 605.10 610.10 615.10 620.10 625.10 630.10 635.10 640.10 645.10 650.10 655.10 660.10 665.10 670.10 675.10 680.10 685.10 690.10 695.10 995.10 Break Path No. l Flow {lbm/sec)
I 197.3 198.0 197.3 198.0 197.2 197.S 197.1 197.7 196.9 197;5 196.7 197.2 196.3 196.8 195.9 196.4 196.8 195.9 196.2 196.5 195.5 195.8 196.0 196.2 195.2 195.3 195.4 195.4 195.5 195.4 195.3 195.2 195.l 194.9 194.7 194.5 194.1 194.8 194.3 194.8 194.2 194.5 193.7 193.8 193:7 193.5. 194.1 193.5 193.7 193:6 193.2 85.5 (SG Side) TI1ousand (Btu/sec) 248.5 249.4 248.5 249.3 248.4 249.1 248.2 248.9 248.0 248.7 247.6 248.3 247.2 247.8 246.8 247.3 247.8 246.6 247.1 247.5 246.3 246.6 246.9 247.1 245.8 245.9 246.1 246.1 246.1 246.1 246.0 245.8 245,7 245.5 245.2 244.9 244.5 245.3 244.7 245:3 244.5 244.9 243.9 244.0 243.9 243.7 244.4 243.7 243.9 243.7 243.3 107.6 I Enthalpy (Btu/lbm}
1,259.3 1,259.3 1,259.3 1,259.3 1,2593 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 l,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 l,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 l,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 1,259.3 l,259.3 1,259.3 l,259.3 1,259.3 (Maximum SI) Break Path No. 2 Flow *(Pump Side) (lbm/sec)
I Thousand I Enthalpy (Btu/sec) (Btu/lbm) 1,399.5 280.4 200.3 1,398.8 279.9 200.1 1,399.6 279.9 200.0 1,398.9 279.4 199.8 1,399.6 279.4 199.6 1,399.0 279.0 199.4 1,399.8 278.9 199.3 1,399;2 278.5 199.I 1,399.9 278.5 198.9 1,399.4 285.5 204.0 1,400.2 285.4 203,8 1,399.7 285.0 203.6 1,400.5 285.0 1,400.I 284.5 203.2 1,400.9 284.5 203.l 1,400.5 284.1 202.9 1,400.1 283.7 202.6 1,401.0 283.7 202.5 1,400:? "283.3 202.3 1,400.4 283.0 202.1 1,401.3 282,9 201.9 1,401.0 282.6 201.7 1,400.8 282.2 201.5 1,400.6 281.9 201.3 1,401.7 281.9 201.1 1,401.5 281.6 200.9 l,401.5 281.3 200.7 1,401.4 281.0 200.5 1,401.4 280.7 200.3 1,401.4 280.4 200.1 1,401.5 280.l 199.9 1,401.6 279.9 199.7 1,401.7 279.6 199.5 1,401.9 279.4 199.3 1,402.1 279.2 199.1 1,402.4 279.0 198.9 1,402.7 278.8 198.7 1,402.l 278.3 198.5 1,402.5 278.1 198.3 1,402.0 277.7 198.I 1,402.7 277.6 197.9 1,402.4 277.2 197.7 1,403.2 277.1 197.5 1,403.1 276.8 197.3 1,403.2 276.6 197.1 1,403.3 276.3 196,9 1,402.8 27{9 196.7 1,403.3 275.7 196.S. 1,403.2 275.4 196.3 1,403.3 275.1 196.I 1,403.7 274.9 195.9 1,511.4 296.7 196.3 6.2-140 Total Mass From Both Sides (lbm/sec) 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596:9 1,596.9 1,596.9 1,596.9 l,596.9 1,596.9 1,596;9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 1,596.9 Total Energy From Both Sides Thousand (Btu/sec) 528.8 529.3 528.3 528.7 527.8 528.1 527.l 527.4 526.4 534.I 533,J 533.3 532.2 532.4 531.3 531.4 531.5 530.3 530.4 530.4 529.2 529.2 529.1 .529.0 527.7 527.5 527.3 527.l 526.8 526.5 526.1 525.7 525.3 524,9 524.4 523.8 523.2 523.6 522.9 523.0 522.1 522.1 521.l 520.8 520.5 520.0 520.2 519.4 519.3 518.9 518.2 404.3 Revision 18 STPEGS UFSAR TABLE 6.2.l.3-5B (continued)
NOC-AE-1600334 7 Enclosure Attachment Page 57 of?? DOUBLE-ENDED PUMP SUCTION BREAK MASS AND ENERGY RELEASES (Maximum SI) Break Path No. I Flow Break Path No. 2 Flow Total Mass Total Energy From Time From Both (SG Side) (Pump Side) Sides Both Sides (seconds) (lbm/sec)
I Thousand' I Enthalpy (lbm/sec)
I Thousand I Enthalpy (lbm/s'ec)
Thousand (Btu/sec) (Btu/sec) (Btu/lbm) (Btu/sec) (Btu/lbm)
Start of sump recirculation 1,000.00 85.4 107.5 1,259.3 1,564.4 534.2 341.4 1,649.8 641.7 1;045.56 85.4 107.5 1,259 .3 1,564.4 534.2 341.4 1,649.8 641.7 1,045.66 95.l 118.6 1,247.3 1,554:7 534.6 343.9 1,649.8 653.2 1,050.00 95.0 118.5 l,247J 1,554.8 534.3 343.6 1,649.8 652.7 1,754.45 95.0 118.5 1,247.3 1,554.8 534.J 343.6 1,649.8 652.7 1,754.55 82.8 95.3 1,150.6 1,567.0 407.7 260.2 1,649.8 503.0 3,600.00 69.1 79.5 1,150.6 1,580.7 410.2 259,5 1,649.8 489.7 Start of revised post-recirculation methodology
[4 J NOTES: 1. Pump Suction Break Area= 5 .24 ft 2* Pipe inside diameter=
2.5 8 ft. 2. The blowdown phase mass and energy releases are the same for Minimum and Maximum SI cases. 3. Blowdown ends at 25.2 seconds. Reflood ends at 220.0 seconds. Sump recirculation begins at 1000 seconds. All SGs depressurized to atmospheric pressure at 3600 seconds. 4. After 3600 seconds, the revised post recirculation methodology is used, as discussed in Section 6.2.1.3.4.5.
6.2-141 Revision 18 STPEGS UFSAR NOC-AE-16003347 Enclosure Attachment Page 58 of77 TABLE 6.2.1.3-6 DECAYHEATDATABASED ON ANS-5.1-1979, PLUS 2 SIGMA UNCERTAINTY
* Time (sec) 1.00E+Ol 1.50E+Ol 2.00E+Ol 4.00E+Ol 6.00E+Ol 8.00E+Ol 1.00E+02 1.50E+02 2.00E+02 4.00E+02 6.00E+02 8.00E+02 1.00E+03 1.50E+03 2.00E+03 4.00E+03 6.00E+03 8.00E+03 1.00E+04 l.50E+04 2.00E+04 4.00E+04 6.00E+04 8.00E+04 1.00E+05 1.50E+05 4.00E+OS 6.00E+OS 8.00E+05 1.00E+06 \ 6.2-142 Decay Heat Generation Rate (Btu/Btu)
ICFtaction of Full Power)!
* 0.053876 0.050401 0.048018 0.042401 0,039244 0.037065 0.035466 0.032724 0.030936 0.027078 0.024931 0.023389 0.022156 0.019921 0.018315 0.014781 0.013040 0.012000 0.011262 0.010097 0.009350 0.007778 0.006958 0.006424 0.006021 0.005323 0.003770 *0.003201 0.002834 0.002580 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-6A DECAY HEAT DATA BASED ON STANDARD REVIEW PLAN ASB 9-2 CORRELATIONS Time {seconds) 9.0E+OO 1.1E+02 5.0E+02 1.0E+03 2.0E+03 3.0E+03 3.6E+03 4.0B+03 5.0E+03 6,0E+03 7.0E+03 8.0B+03 9.0E+03 1.0E+04 2.0E+04 3.0E+04 4.0E+04 5.0E+04 6.0E+04 7.0E+04 8.0E+04 9.0E+04 l.OE+05 2.0E+05 3.0E+05 4.0B+05 5.0E+05 6.0E+05 7;0E+OS .8.0E+OS 9.0E+OS l.OE+06 l.IE+D6 1.2E+06 1.3E+06
* 1.4E+06 l.5E+06 1.6E+06 l.7E+06 1.8E+06 l.9E+06 2'.0E+.06 2.5E+06 3.0E+06 3.5E+06 4.0E+06 4.5E+06 5.0E+06 u.OE+06 7:0E+06 8.0E+06 9.0E+06 6.2-143 Decay Heat (Btu/hr) 1.03E+D9 5.80E+08 3.84E+08 3.06E+o8 2.56E+08 2.24E+08 2.llE+08 2.03E+08 1.88E+08 l.78E+08 1.70E+08 1.64E+08 1.59E+08 1.55E+08 l.29E+08 l.13E+08 l.02E+08 9.49E+07 8.96E+07 8.57E+07 8.25E+.07 8.00E+07 7.78E+07 6.33E+07 5.42E+07 4.81E+07 4.38E+07 4.06E+07 3.82E+07 3.63E+07 3.48E+07 3.34E+07 3.23E+07 3.13E+07 3.04E+07 2.95E+07 2.87E+07 2.80E+07 2.73E+07 2.67E+07 2.61E+07 2.55E+07 2.30E+07 2.l0E+07 l.94E+07 l.81E+07 1.70E+07 l.60E+07 l.46E+07 l.34E+07 l.25E+07 1.17E+07 NOC-AE-1600334 7 Enclosure Attachment Page 59 of77 Revision 18 STPEGS UFSAR TABLE 6.2.l.3-6A (Continued)
DECAY HEAT DATA BASED ON STANDARD REVIEW PLAN ASB 9-2 CORRELATIONS Time (seconds) l.OE+07 2.0E+07 3.0E+07 4.0E+07 5.0E+07 6.0E+o7 7.0E+07 8.0E+o7 9.0E+OT 1.0E+08 6.2-144 Decay Heat (Btu/hr) 1.IOE+07 6.90E+D6 4.99E+D6 3.96E+06 3.32E+06 2.90E+06 2.60E+06 2.37E+06 2.2!E+06 2.08E+06 NOC-AE-1600334 7 Enclosure Attachment Page 60 of77 Revision 18 NOC-AE-1600334 7 Enclosure Attachment Page 61 of 77 STPEGS UFSAR TABLE 6.2.1.3-9 DOUBLE-ENDED PUMP SUCTION BREAK PRINCIPAL PARAMETERS DURING REFLOOD (Minimum SI) Flooding Core Downcomer Time Temp Rate Carryover Height Height Flow Injection
{lbm/sec)
Enthalpy (seconds)
('F) (in/sec) Fraction fill fill Fraction Total Accumulator Spill CBtu/lbm) 25.2 196.5 0.000 0.000 0.00 0.00 0.250 0.0 0.0 0.0 0.0 25.9 192.4 26.017 0.000 0.60 2.29 o.ooo 11135.7 11135.7 0.0 89.5 26.1 189.7 31.875 0.000 1.08 2.37 0.000 11067.7 11067.7 0.0 *89.5 26.9 187.8 3.653 0.307 1.50 5.59 0.324 10760.5 10760.5 0.0 89.5 27.8 187.5 3.423 0.456 1.67 9.88 0.360 10483.6 10483.6 0.0 89.5 30.0 186.9 7.415 0.630 2.00. 18.29 0.654 8989.9 8989.9 0.0 89.5 30.3 186.7 7.529 0.649 2.07 18.31 0:646 8792.9 8792.9 0.0 89.5 31.3 186.1 7.102 0.686 2.27 lB.31 0.644 8545.2 8545.2 0.0 89.5 32.7 185.7 6.719 0.712 2.51 18.31 0.645 8282.l 8282.l 0.0 89.5 w 33.3 185.6 6.980 0.719 2.60 18.31 ...... 0.653 8833.6 8017.3 0.0 90.28 w 0\ 35.9 185.7 6.603 0.735 3.00 18.31 0.651 8418.4 7592.6 0.0 90.33 39.5 186.8 *6.233 0.744 3.50 18.3! 0.648 7967.0 7125.2 o.o 90.40 43.4 . 188.9 5.927 0.749 4.00 18.31 0.642 7551.3 {5695.0 0.0 90.46 47.3 191.5 3.964 0;747 4.46 18.31 0.543 922.4 0.0 0.0 97.98 48,3 192.3 3.957 0.747 4.54 18.31 0.542 922.0 0.0 0.0 97.98 53.9 198.3 3.915 0.750 5.01 18.31 0.545 922.D 0.0 0.0 97.98 60.3 207.7 3.867 0.753 5.52 18.31 0.548 921.9 0.0 0.0 97.98 66.4 218.3 . 3.818 0.756 6.00 18.31 0.552 921.8 0.0 o.o 97.98 73.3 231.1 3.757 0.760 6.53 18.31 0.556 921.8 0.0 0.0 97.98 79.7 243.0 3.693 0.765 7.00 0.559 921.8 0.0 0.0 97.98 88.3: 256.6 3.599 0.771 7.61 1831 0.564 92L9 o.o 0.0 97.98 94.2* 264.2 3.530 0.775 8.01 1831 0.567 922.1 0.0 0.0 97.98 102.3. 273.0 3.431 0.780 8.53 18.31 0.570 922.5 0.0 0.0 97.98 110.0 279.8 3.332 0.784 9.00 18.31 0.573 923.l 0.0 0.0 97.98 120.3 287.l 3.195 0.790 9.60 18.31 0.576 924.1 0.0 o.o 97.98 127.7 291.4 3.094 0.795 10.00 18.31 0.578 924.9 0.0 0;0 97.98 138.3 296.3 2.945 0.801 10.54 18.31 0.579 926.3 0.0 0.0 97.98 148.2 300.0 2.800 0.808 11.00 18.31 o.578 927.9 0.0 o.o 97.98 160.3 303.5 2.613 0.817 11.51 18.31 0.575 930.1 0.0 0.0 97.98 173.l 303.3 2.427 0.818 12.00 18.31 0.566 932.9 0.0 0.0 97;98 6.2-145 Revision 18 NOC-AE-1600334 7 Enclosure Attachment Page 62 of77 STPEGS UFSAR TABLE 6.2.1.3-10 DOUBLE-ENDED PUMP SUCTION BREAK PRINCIPAL PARAMETERS DURING REFLOOD (Maximum SI) Flooding Core Down comer Time Temp Rate Carryover Height Height Flow Injection (lbm/sec)
Enthalpy (seconds)
('F) Cinlsec) Fraction  {.fil Fraction Total Accumulator Spill <Btu/lbmr 25.2 196.5 0.000 0.000 0.00 0.00 0.250 0.0 0.0 0.0 0.0 25.9 192.4 26.017 0.000 0.60 2.29 0.000 11135.7 11135.7 0.0 89.5 26.1 189.7 31.875 0.000 1.08 2.37 0.000 11067.7 11067.7 0.0 89.5 26.9 187.'8 3;653 0.307 1.50 5.59 0.324 10760.5 10760.5 o:o 89.5 27.8 187.5 3.423 0.456 1.67 9.88 0.360 10483.6 10483.6 0.0 89.5 30.0 186.9 7.415 0.630 2.00 18.29 0.654 8989.9 8989.9 0.0 89.5 30.3 186.7 7.529 0.649 2.07 18.31 0.646 8792.9 8792.9 0.0 89.5 31.3 186.1 7.102 0.686 2.27 18.31 0.644 8545.2 8545.2 0.0 89.5 w 32.7 185.7 6.719 0.712 2.51 18.31 0.645 8282.1 8282.1 0.0 89.5 ....... l;.J 33.3 18&deg;5.6 7.250 0.720 2.60 18.31 0.658 9299.3 7905.3 0.0 90.77 0\ 35.8 185.6 6.880 0.734 3.01 18.31 0.656 8869.0 7468.3 0.0 90.84 39.3 186.6 6.534 0.744 3.51 18.3 I 0.654 8436.8 7016.4 0.0 90.93 43.0 188.5 6.257 0.749 4.01 18.31 0.651 8046.5 6608.5 0.0 91.02 I 47.3 191.3 3.990 0.752 4.56 18.31 0.489 2673.6 1218.7 0.0 94.11 . 48.3 192.0 3.558 0.745 4.64 18.31 0.509 1570.7 0.0 0.0 97.98 .53.4 196.7 3.198 0.743 5.00 18.31 0.473 1582.2 0.0 0.0 97.98 61.3 205.9 2.814 0.741 5.50 18.31 0.424 1592.1 0.0 0.0 97.98 69.6 216.9 2.752 0.744 6.00 18.31 0.425 1592.0 0.0 0.0 97.98 78.3 229.2 2.687 0.748 6.50 18.31 0.427 1592.0 0.0 0.0 87.4 242.0 2.617/ 0.753 . 7.00 18.31 0.428 1591.9 0.0 0.0 97.98 98.3 255.3 2.535 0.759 7.58 18.31 0.430 1591.8 0.0 0.0 97.98 106.9 263.9 2.472 0.764 8.00 18.31 0.432 1591.7 0.0 0.0 97.98 118.3 273.4 2.391 0.771 8.54 18.31 0.435 1591.6 0.0 0.0 97.98 128.7 280.4 . 2.320 0.777 9.00 18.31 0.437 1591.5 0.0 0.0 97.98 142.3 287.8 2.231 0.786 9.57 18.31 0.441 1591.3 0.0 0.0 97.98 153.6 292.8 2.160 o.7'94 10.00 18.31 OA44 1591.2 0.0 0.0 97.98 168.3 298.0 2.069 0;807 10.52 18.31 0.449 1591.1 .0.0 0.0 97;98 183.8 302.4 1.973 0.824 11.00 18,31 0.454 1590;9 0.0 0.0 97.98 202.3 303.3 1.902 0.829 11.50 18.31 0.459 1590.9 0.0 0.0 97.98 220.0 301.7 1.865 0.818 12.00 18.31 0.463 1590.9 0.0 0.0 97.98 6.2-146 Revision 18 NOC-AE-16003347 Enclosure Attachment Page 63 of77 STPEGS UFSAR TABLE 6.2.1.3-13 DOUBLE-ENDED PUMP SUCTION BREAK MASS BALANCE (Minimum SI} Thne (seconds) 0.00 25.20 25.20 173.10 639.95 1613.06 3600.0 Mass (Thousand lbm) Initial Mass In RCS and 933.50 933,50 933.50 933.50 933.50 933.50 933.50 Accumulator Added Mass Pumped Injection 0.00 .00 .00 128.39 570.47 1442.38 2753.95 ..... Total Added 0.00 .00 .00 128.39 570.47 1442.38 2753;95 (JJ 0\ *** Total Available
*** 933.50 933.50 933.50 1061.89* 1503.98 2375.89 3687.45 Distribution Reactor Coolant 625.85 54.54 59.94 129.38 129.38 129.38 129.38 Accumulator 307.65 256.21 250.81 0.00 0.00 0.00 0.00 Total Contents 933.50 310.75 310.75 129.38 129.38 129.38 129.38 Effluent Break Flow o.oo 622.73 622.73 . 841.65 1283.74 2162.39 3467:20 ECCS Spill 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total Effluent 0.00 622.73 . 622.73 841.65 1283.74 2162.39 3467.20 *>I<* Total Available
*** 933.50 933.48 933.48 971.04 1413.12 2291.78 3596.58 6.2-147 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-14 NOC-AE-16003347 Enclosure Attachment Page 64 of77 DOUBLE-ENDED PUMP SUCTION BREAK MASS BALANCE (Maximum SI) Time (seconds) 0.00 25.20 25.20 220.0 1045.66 1754.45 3600.0 Mass (Thousand lbm) Initial Mass InRCS and 933.50 933.50 933.50 933.50 933.50 933.50 933.50 Accumulator Added Mass Pumped Injection 0.00 0.00 0.00 295.06 1615.78 2785.14 5829.93 Total Added 0;00 0.00 0.00 295.06 1615.78 2785.14 5829.93 *** Total Available
*** 933.50 933.50 933.50 1228.57 2549.28 3718.64 6763.43 Distribution Reactor Coolant 625.85 54.54 59.94 131.30 131.30 131.309 131.30 Accumulator 307.65 256.21 250.81 0.00 0.00 0.00 0.00 Total Contents 933.50 310.75 310.75 131.30 131.30 131.30 131.30 2 .. Effluent Break Flow 0.00 622.73 622.73 1006.42 2327.13 3496.62 *6541.41 I w ECCS Spill 0.00 0.00 0.00 0.00 0.00 0.00 0.00 .._. w &deg;' Total Effluent 0.00 622.73 622.73 1006.42 2327.13 3496.62 6541.41 *** Total Available
*** 933,50 933.48 933.48 1137.71 2458.43 3627.92 6672.71 6.2-148 Revision 18 STPEGS UFSAR TABLE 6.2.1.3-15 DOUBLE-ENDED HOT LEG BREAK MASS BALANCE Time (seconds) 0.00 24.8 24.8 Mass (Thousand Ihm) Initial Mass InRCS and 933.50 933.50 933.50 Accumulator Added Mass Pumped Injection 0.00 0.00 0.00 Total Added 0.00 0.00 0.00 *** Total Available
*** 933.50 933.50 933.50 Distribution Reactor Coolant 625.85 90.85 96.82 Accumulator 307.65 232.24 226.28 Total Contents 933.50 323.lO 323.10 Effluent Break Flow 0.00 610.39 610.39 ECCS.Spill 0.00 0.00 0.00 Total Effluent 0.00 610.39 610.39 *** Total Available
*** 933.50 933.490 933.49 6.2-149 NOC-AE-16003347 Enclosure Attachment Page 65 of77 Revision 18 0 l,;J -l,;J &deg;'
STPEGS UFSAR TABLE 6.2.1.3-16 NOC-AE-16003347 Enclosure Attachment Page 66 of77 DOUBLE-ENDED PUMP SUCTION BREAK ENERGY BALANCE (Minimum SI) Time (seconds}
0.00 25.20 25.20 173.10 639.95 1613.06 3600.0 Energy (Million Btu) Initial Energy In RCS, Accumulator, 1219.l5 1219.15 12.19.15 1219.15 1219.15 1219.15 1219.15 SG Added Energy Pumped Injection 0;00 0.00 0.00 12.58 55.90 157.19 467.55 Decay Heat 0.00 8.68 8.68 28.58 75.85 153.68 279.01 Heat From Secondary 0.00 8.76 8.76 8.76 20.06 26.30 26.30 Total Added 0.00 17.44 17.44. 49.92 151.80 337.18 772.86 *** Total Available
*** 1219.15 1236.58 1236.58 1269.06 1370.95 1556.32 1992.01 Distribution Reactor Coolant 375.72 12.28 12.76 36.52 36.52 36.52 36.52 Accumulator 27.53 22.93 22A5 0.00 0.00 0.00 0.00 Core Stored 31.45 15.37 15.37 5.87 5.36 4.87 3.88 Primary Metal 204.93 194.62 194.62 173.42 125.06 93.04 72.25 Secondary Metal 161.72 158.13 158.13 143.93 116.37 81.03 62.30 Steam Generator 417.80 431.42 43L42 386.36 315.58 222.96 174.42. Total Contents 1219.15 834.75 834.75 746,09 598.90 438.43 349.38 Effiuent Break Flow 0.00 401.15 401.15 512.53 761.61 1128.39 1657.23 ECCSSpill 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total Effluent 0.00 401.15 401.15 512.53 761.61 1128.39 1657.23 *** Total Available
*** 1219.15 1235.90 1235.90 1258.63 1360.51 1566.82 2006.61 6.2-150 Revision 18 w ..... w 0\
STPEGS UFSAR TABLE 6.2.1.3-17 NOC-AE-1600334 7 Enclosure Attachment Page 67 of77 DOUBLE-ENDED PUMP SUCTION BREAK ENERGY BALANCE (Maximum SI) Time (seconds) 0.00 25.20 25.20 .220.0 1045.66 1754.45 3600.0 Energy (Million Btu) Initial Energy In RCS, Accumulator, 1219.15 1219.15 1219.15 1219.15 1219.15 1219.15 1219.15 SG Added Energy Pumped Injection 0.00 0.00 0.00 28.91 168.94 448.41 1176.12 Decay Heat o.oo 8.68 8.*68 33.95 110.45 163.70 278.94 Heat From Secondary 0.00 8.76 8.76 8.76 26.30 . 26.30 26.30 Total Added Q;OO 17.44 17.44 71.62 305.70 638.42 1481.37 *** Total Available
*** 1219.15 1236.58 1236.58 1524.84 1857.56 2700.51 Distribution Reactor Coolant 375.72 12.76 12.76 36.86 36.86 36.86 36.86 Accumulator 27.53 22.45 22.45 0.00 0.00 0.00 0.00 Core Stored 31.45 15.37 15.37 5.87 5.06 4.73 3.88 J Primary Metal 204.93 194.62 194.62 170.66 112.47 89.68 72.84 Secondary Metal 16L72 158,13 158.13 145.46 103.22 77.94 63.04 Steam Generator 417.80 431.42 431.42 390.48 283.11 214.76 176.32 Total Contents 1219.15 834.75 834.75 749.32 540.71 423.98 352.95 Effluent Break Flow 0.00 401.15 401.15 530.99 973.67 1416.40 2332.44 ECCS Spill 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Total Effluent 0.00 401.15 401.15 530.99 973.67 1416.4 2332.44 *** Total Available
*** 1219.15 1235.90 1235.90 1280.31 1514.39 1840.38 2685.39 6.2-151 Revision 18 2 I v.i ,_. v.i &deg;' 1 I :i ' I I ' I :i, STPEGS UFSAR TABLE 6.2.1.3-18 DOUBLE-ENDED HOT LEG BREAK ENERGY BALANCE Time (seconds) 0.00 24.84 24.84 Energy (Million Btu) Initial Energy In RCS, Accumulator, 1219.15 1219.15 1219.15 SG Added Energy Pumped Injection 0.00 0.00 0.00 Decay Heat 0.00 9.19 9.19 Heat From Secondary 0.00 -13.31 -13.31 Total Added *o.oo -4.12 -4.12 *** Total Available
*** 1219.15 1215.03 1215.03 Distribution Reactor Coolant 375.72 19.01 19.54 Accumulator 27.53 20.79 20.25 Core Stored 31.45 13.70 13.70 Primary Metal 204.93 192.02 ' 192.02 Secondary Metal 161.72 156.81 156.81 Steam Generator 417.80 401.73 401.73 Total Contents 1219.15 804.06 804.06 Effluent Break Flow 0.00 410.27 410.27 ECCS Spill 0.00 0.00 0.00 Total Effluent 0.00 410.27 410.27 NOC-AE-16003347 Enclosure Attachment Page 68 of77 *** Total Available
*** 1219.15 1214.33 1214.33 6.2-152 Revision 18 l.>J ...... '-w ,, &deg;' i L Figure 6.2.1.1-30 DEHL -Minimum SI, Minimum CHRS Containment Pressure NOC-AE-16003347 Enclosure Attachment Paae 69 of77
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] SOUTH TEXAS PROJECT UN I TS 1 & 2 CONTAINMENT PRESSURE LOCA -DEHL MINIMUM SI, MINIMUM CHRS FIGURE 6. 2.1.1-30 REVISION 18 UFSARFIG6.2.
: 1. 1-30.D(;N UFSARF!G6.2.
: 1. 1-30. CIT L LL Q.) ..... ::J ...., 0 ..... Q.) a. E Q.) I-Figure 6.2 .1.1-31 NOC-AE-16003347 Enclosure Attachment Page 70 of 77 DEHL -Minim um SI, Minim um CHRS Containment Temperature . 1V1 C*ontelnment Vapor*remi:>erature.
IL 1 Containment Liquid TemperatL1te SOUTH TEXAS PROJECT UNITS 1 & 2 CONTAINMENT TEMPERATURES LOCA -DEHL SI, MINIMUM CHRS FIGURE 6. 2. 1. 1 -31 REVISION 18 UFS/>RFJG6.2.1.
1-31.DGN UFS/>RFJG6.2.
1.1-31.CIT
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l ..............
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*1e+ooa HA2 Gontalnm.ent Wall HA1'6 Stainless Steel Componentst NOC-AE-16003347 Enclosure Attachment Page 71 of 77 SOUTH TEXAS PROJECT UNITS 1 & *2 HEAT TRANSFER COEFFICIENT LOCA -DEHL MINIMUM SI, MINIMUM CHRS FIGURE 6. 2.1.1-32 REVISION 18 UFS.ARFIG6.2.
: 1. 1-32.DGN UFSARFIG6.2.
: 1. 1-32.CIT _J L .... 0 "iii a. .., NOC-AE-16003347 Enclosure Attachment p 72 f77 f'igure 6.2 .1.1-33 OEPS .. Minimum SI, Minimum CHRS Containment Pressure f'igure 8 -Contoinmenl Pressure PR1cv5C a . ..._._ ... ---l PR1 Oontalnme.nt Preesuri&
dVoC . Contar.nmentsteam 0f e, or) Pressure SOUTH TEXAS PROJECT UNITS 18c 2 CONTAINMENT PRESSURE LOCA -DEPSG ( MINIMUM SI, MINIMUM CHRS FIGURE 6.2.1.1-33 REVISION 18 Lf'Slll" IG6. 2. 1. 1 *33. OOll Lf'Slll"IG6.2.t.1*33;CIT
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........ LL. Q) .... :J ...., 0 .... Q) . c.. E Q) I-Figure 6.2.1.1-34 NOC-AE-1600334 7 Enclosure Attachment Page 73 of77 DEPS -Minimum SI, Minimum CHRS Containment Temperature TV1 Conte.tnmentVa orTemperature
'Fl..1 containment Llq1..1ld (Sump Temperature
*SOUTH PROJECT UN I TS 1 & 2 CONTAINMENT TEMPERATURES LOCA -DEPSG MINIMUM SI, MINIMUM CHRS FIGURE 6. 2. 1. 1-34 REVISION 18 UFSARFIG6.2.
: 1. 1-34.DGN UFSARFJG6.2.
: 1. 1-34.CIT _J L ...... l.J.. 0 I N ...., ....... (. L.. L: ....... m ...., c: () :.;:::: ....... Q) 0 () L.. Q) ........ Ul c: c L.. . I-..... c Q) I Figure 6.2.1.1-35 NOC-AE-16003347 Enclosure Attachment Page 74 of77 DEPS -Minim um SI , Minim um CHRS Con tainm en t Heat Transfer Coefficient HA2 lnslde Col'l'ta1nmantWall HA1$ Stednles$
S'feel Compi:ments SOUTH TEXAS PROJECT UN I TS 1 & 2 HEAT TRANSFER COEFFICIENT LOCA -DEPSG MINIMUM SI, MINIMUM CHRS FIGURE 6. 2.1.1-35 REVISION 18 UFS.ARFIG6.2.
: 1. 1-35.DQ\l UFS.ARFIG6.2.
: 1. 1-35.CIT _J 0 "iii a. Q) .... :J Ul Ul Q) .... 0... Figure 6.2.1.1-36 NOC-AE-16003347 Enclosure Attachment Pa e75of77 DEPS -Maxim um SI, Minim um CHRS Containment Pressure Figure 8 -Con tainm en t Pressure PR1cv5C s-.-.-..... .P'R1 Containment Pressure *ov5C contalnrrrsnt Steam (Vapor) Pra*saura
* SOUTH TEXAS PROJECT UNITS 1 & 2 CONTAINMENT PRESSURE LOCA -DEPSG MAXIMUM SI, MINIMUM CHRS FIGURE 6. 2.1.1-36 REVISION 18 UFSl'RFIG6.2.
: 1. 1-36.DGN UFSl'RFIG6.2.
: 1. 1-36. CIT _J L (LI .... ::l ....... 0 .... (LI c.. E (LI I-Figure 6.2.1.1-37 NOC-AE-16003347 Enclosure Attachment Page 76 of77 DEPS -Maxim um SI, Minim um CHRS Containment Temperature IV1 Contalnm$nt Vapor iem:peratwrei TL 1
* aontalnment LlqL1ld (Sump) Tamperature SOUTH TEXAS PROJECT UNITS 1 & 2 CONTAINMENT TEMPERATURES LOCA -DEPSG MAXIMUM SI, MINIMUM CHRS FIGURE 6. 2. 1. 1 -37 REVISION 18 UFS.ARFIG6.2.
: 1. 1-37.DGN UFS.ARFIG6.2.
: 1. 1-37.CIT _J L Figure 6 .. 2 .. 1.1-38 DEPS -Maxim um SI, Minim um CHRS Containment Heat Transfer Coefficient NOC-AE-16003347 Enclosure Attachment Pa e 77 of77 !--------.
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Figure C -Heat Transfer Coefficient HA2HA16 l.J_ 0 I ..... ........ I ..... .c ' CD ...... c:: .. !!? u :;: ..... QJ 0 u ..... QJ ........ UJ c: 0 ..... I-..... 0 QJ L 1 1-i-t-1 1 l m. _., *"**h ....
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SOUTH TEXAS PROJECT UN I TS 1 & 2 HEAT TRANFER COEFFICIENT LOCA -DEPSG MAXIMUM SI, MINIMUM CHRS FIGURE 6. 2. 1 . 1 -38 REVISION 18 UFS/>RFIG6.
: 2. 1. 1-38.DGN UFS/>RF!G6.2.
: 1. 1-38.CIT _J}}

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