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Category:REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)
MONTHYEARML20247G3801989-08-31031 August 1989 RESAR-SP/90 Pda Response to Draft SER Open Issues 82-107 ML20248H8501989-08-31031 August 1989 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20235N4791989-01-31031 January 1989 Amend 1a to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20235N4951989-01-31031 January 1989 Amend 2 to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20206F8861988-11-30030 November 1988 Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys ML20195C7931988-10-31031 October 1988 Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs ML20153F7341988-08-31031 August 1988 Amend 3 to Module 3, Introduction & Site ML20207J9601988-08-31031 August 1988 Nonproprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20151R6361988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt ML20151N4321988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 11, Radiation Protection ML20154F0641988-05-31031 May 1988 Amend 1a to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20154H5011988-05-31031 May 1988 Non-proprietary Amend 1 to RESAR-SP/90 Pda Module 4, Rcs ML20154F0811988-05-31031 May 1988 Amend 3 to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20151Y0501988-04-30030 April 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20154E9521988-04-30030 April 1988 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20154H6701988-03-31031 March 1988 Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site ML20234C5271987-11-30030 November 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 9, Instrumentation & Controls & Electric Power ML20236V0721987-10-31031 October 1987 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 1,Primary Side Safeguards Sys ML20236V0741987-10-31031 October 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20236E9251987-09-30030 September 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 16, Probabilistic Safety Study ML20236F6991987-09-30030 September 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20207S3811986-11-30030 November 1986 Chapter 18, Human Factors Engineering, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3781986-11-30030 November 1986 Chapter 17, QA, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3751986-11-30030 November 1986 Chapter 16, Tech Specs, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3671986-11-30030 November 1986 Chapter 14, Initial Test Program, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3691986-11-30030 November 1986 Chapter 15, Accident Analyses, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3631986-11-30030 November 1986 Chapter 13, Conduct of Operations, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3541986-11-30030 November 1986 Chapter 12, Radiation Protection, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3381986-11-30030 November 1986 Chapter 11, Radwaste Mgt, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20214L5501986-11-30030 November 1986 Nonproprietary Amend 1 to RESAR-SP/90 Preliminary Design Approval Module 6/8, Secondary Side Safeguards Sys/Steam & Power Conversion ML20207R9661986-11-30030 November 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2581986-11-30030 November 1986 Chapter 1, Introduction & General Description of Plant, to Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR, Module 10, Containment Sys ML20207S2621986-11-30030 November 1986 Chapter 2, Site Characteristics, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2681986-11-30030 November 1986 Chapter 3, Design of Structures,Components,Equipment & Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2731986-11-30030 November 1986 Chapter 4, Reactor, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2781986-11-30030 November 1986 Chapter 5, RCS & Connected Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2941986-11-30030 November 1986 Chapter 6, ESF, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3001986-11-30030 November 1986 Chapter 7, Instrumentation & Controls, to RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3051986-11-30030 November 1986 Chapter 8, Electric Power, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3221986-11-30030 November 1986 Chapter 9, Auxiliary Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3321986-11-30030 November 1986 Chapter 10, Steam & Power Conversion Sys, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20213F7121986-10-31031 October 1986 Nonproprietary Chapter 3, Design of Structures,Components, Equipment & Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20215M8681986-10-31031 October 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR Std Plant Design Module 15, Control/Human Factors Engineering ML20213F3931986-10-31031 October 1986 Nonproprietary Version of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7021986-10-31031 October 1986 Nonproprietary Chapter 1, Introduction & General Description of Plant, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7981986-10-31031 October 1986 Nonproprietary Chapter 18, Human Factors Engineering, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7101986-10-31031 October 1986 Nonproprietary Chapter 2, Site Characteristics, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7151986-10-31031 October 1986 Nonproprietary Chapter 4, Reactor, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7171986-10-31031 October 1986 Nonproprietary Chapter 5, RCS & Connected Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7241986-10-31031 October 1986 Nonproprietary Chapter 6.4, Control Room Habitability Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys 1989-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20024H1211991-04-30030 April 1991 Safety Evaluation Report Related to the Preliminary Design of the Standard Nuclear Steam Supply Reference System,Resar SP/90.Docket No. 50-601.(Westinghouse Electric Corporation, Inc.) ML20012E9321990-03-31031 March 1990 SP/90 Position on Severe Accident Policy Issues ML20247G3801989-08-31031 August 1989 RESAR-SP/90 Pda Response to Draft SER Open Issues 82-107 ML20248H8501989-08-31031 August 1989 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20235N4791989-01-31031 January 1989 Amend 1a to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20235N4951989-01-31031 January 1989 Amend 2 to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20206F8861988-11-30030 November 1988 Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys ML20195C7931988-10-31031 October 1988 Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs ML20153F7341988-08-31031 August 1988 Amend 3 to Module 3, Introduction & Site ML20151T8661988-08-31031 August 1988 Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20207J9601988-08-31031 August 1988 Nonproprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20151R6361988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt ML20151N4321988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 11, Radiation Protection ML20154H5011988-05-31031 May 1988 Non-proprietary Amend 1 to RESAR-SP/90 Pda Module 4, Rcs ML20154F0811988-05-31031 May 1988 Amend 3 to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20154F0641988-05-31031 May 1988 Amend 1a to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20154E9521988-04-30030 April 1988 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20151Y0501988-04-30030 April 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20154H6701988-03-31031 March 1988 Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site ML20234C5271987-11-30030 November 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 9, Instrumentation & Controls & Electric Power ML20236V0721987-10-31031 October 1987 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 1,Primary Side Safeguards Sys ML20236V0741987-10-31031 October 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20236D9111987-10-26026 October 1987 Safety Evaluation Re Reactor Coolant Pump Flywheel Integrity.Matl,Fabrication,Design & Insp Aspects of Flywheels Acceptable ML20236E9251987-09-30030 September 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 16, Probabilistic Safety Study ML20236F6991987-09-30030 September 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20207S2621986-11-30030 November 1986 Chapter 2, Site Characteristics, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3811986-11-30030 November 1986 Chapter 18, Human Factors Engineering, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3781986-11-30030 November 1986 Chapter 17, QA, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3751986-11-30030 November 1986 Chapter 16, Tech Specs, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3671986-11-30030 November 1986 Chapter 14, Initial Test Program, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3691986-11-30030 November 1986 Chapter 15, Accident Analyses, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3631986-11-30030 November 1986 Chapter 13, Conduct of Operations, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3541986-11-30030 November 1986 Chapter 12, Radiation Protection, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3381986-11-30030 November 1986 Chapter 11, Radwaste Mgt, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3321986-11-30030 November 1986 Chapter 10, Steam & Power Conversion Sys, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3221986-11-30030 November 1986 Chapter 9, Auxiliary Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3051986-11-30030 November 1986 Chapter 8, Electric Power, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3001986-11-30030 November 1986 Chapter 7, Instrumentation & Controls, to RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2941986-11-30030 November 1986 Chapter 6, ESF, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2781986-11-30030 November 1986 Chapter 5, RCS & Connected Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2681986-11-30030 November 1986 Chapter 3, Design of Structures,Components,Equipment & Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2581986-11-30030 November 1986 Chapter 1, Introduction & General Description of Plant, to Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR, Module 10, Containment Sys ML20207R9661986-11-30030 November 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20214L5501986-11-30030 November 1986 Nonproprietary Amend 1 to RESAR-SP/90 Preliminary Design Approval Module 6/8, Secondary Side Safeguards Sys/Steam & Power Conversion ML20207S2731986-11-30030 November 1986 Chapter 4, Reactor, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20213F7021986-10-31031 October 1986 Nonproprietary Chapter 1, Introduction & General Description of Plant, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7121986-10-31031 October 1986 Nonproprietary Chapter 3, Design of Structures,Components, Equipment & Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7551986-10-31031 October 1986 Nonproprietary Chapter 9, Auxiliary Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7291986-10-31031 October 1986 Nonproprietary Chapter 8, Electric Power, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20215M8681986-10-31031 October 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR Std Plant Design Module 15, Control/Human Factors Engineering 1991-04-30
[Table view] |
Text
_ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _
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WESTINGHOUSE CLASS.3 AMENDMENT 3 TO RESAR-SP/90 PDA MODULE 16 O
PROBABILISTIC SAFETY STUDY l
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O WAPWR-PSS AMENDMENT 3 5960e:1d SEPTEMBER, 1987
AMENDHENT 3 TO RESAR-SP/90 PDA MODULE 16 Instruction Sheet o
Insert pages 720-27 through 720-30 after 720-26 of Amendment 2.
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Insert Attachments E through I after Attachment D of Amendment 2.
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Insert Figures 720.46 (A-C) after series of foldouts from Amendment 1.
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O WAPWR-PSS AMENDHENT 3 E960e:Id SEPTEMBER, 1987
a REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROBABILISTIC SAFETY STUDY RESAR SP/90 i
l' (p. 4, STCP User's Guide (MOD 1)) NUREG/CR-4587, July 1986)g [per Table 1 720.39 Provide an inventory of elements for 40 species in k
RESPONSE
See Attachment E for fission product inventories.
O 720.40 Provide engineering drawings of:
i) Reactor cavity and junction flow areas;
}-
ii) Reactor building. cross-sections (concrete only) showing wall penetrations; iii) Elevation floor plans; iv) Overall' ventilation system for the reactor building; and v) The 4-V MAAP nodalization illustrating junction flow area, structure heat sink composition, areas and thicknesses, and junctionelevations.
RESPONSE
Later - Reactor Containment design parameters.
~
720.41 Provide the containment failure pressure distribution or mean and standard deviction as used in the PSS.
RESPONSE
A failure pressure of containment design,+(a,c) was used for the APWR containment.
In view of the recent Sandia containment ultimate pressure capacity tests, this is a
very conservative assumption.
There was no distribution of failure pressures vs. probability of failure used in the probabilistic safety study, and therefore no mean or assceiated standard deviation.
This was necessary due to the preliminary state of developunt of the containment design at the time of the performance of the core and containment analysis.
O WAPWR-PSS 720-27 AMENDMENT 3 5794e:1d SEPTEMBER, 1987
1; j
1 720.42 What;is the PORV capacity per valve at design pressure (Table 5.4-13)?
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RESPONSE
The'. relief capacity ofthepressurizerPORV' sat 2385psigis[
]+(a,c) lb/hr. per valve. This value could change during the FDA design stage.
tq V
720.43 What is the probability of restoration of AC power as a function of time from accident initiation?
i l
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RESPONSE
I G
The value for " probability of restoration of AC power as a function of time from accident initiation" used for,the SP/90 PDA PRA was 50%
recovery within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
This was conservatively based on Table 3.2 of EPRI report NP-2301, " Loss of Offsite Power at Nuclear Power Plants,
)
Data and Anal,ysis," 1982, which is included here as Attachment F.
720.44 If the containment fails by overpressure, what is the likely failure mode, failure location (s), and area of the breach?
O>
l
RESPONSE
An overpressure failure of the APWR containment was assumed to consist of a failure of the containment in the upper compartment.
The area associated with such a failure was assumed to be
+(a c) 720.45 Do sprays survive a hydrogen burn? What is the probability of their successful operation?
RESPONSE _:
Sprays will survive a hydrogen burn.
The successful operation of the containment sprays is unaffected by a hydrogen burn because the spray water is capable of absorbing a large amount of the heat generated during a hydrogen burn.
o Y
WAPWR-PSS 720-28 AMENDMENT 3 5794e:1d SEPTEMBER, 1987
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y 720.46 Provide the following detailed output from the MAAP calculations:
l i)'The transient output in table form and plots for TE, SE, and
)
SEFC; j
ii) The molar gas concentrations in the four compartments;
)
iii) The temperature of the gas and of the surrounding structure in l
q the tour compartments; Qi-v) The gas release rate from corium/ concrete interactions and the j
iv) The containment leak rate; total. release; 4
vi) The aerosol generation rate in corium/ concrete interactions-1 vii) The fraction of I, Cs, and Te released in-vessel prior to vessel e
- failure, retained.
in-vessel after vessel
- failure, and the
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ex-vessel release to containment after vessel failure; also revaporization from vessel after vessel failure as a function of time; and viii) The temperature of corium as a function of time.
l
RESPONSE
Detailed output from the MAAP Code is not available in al1 of the specific forms and/or for the specific quantities requested. Output is available and is provided for : molar gas concentrations (item ii)
- Attachments G,
H & I; temperature of gas (item iii) - Figures Oy 720.46 iii A, B & C; temperature of corium (item viii)
Figures 720.46 viii A, B & C.
720.47 What is the penetration size and failure mode due to over-temperature?
?
RESPONSE
No specific failure mode was identified for over-temperature failure of the APWR containment.
For over-temperature failure (temperature in upper compartment greater than 400'F) a failure
~
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+(a,c) 720.48 For severe accidents where the reactor vessel fails while the primary coolant system is still at high pressure, direct containment heating has been identified as a potential means for early containment failure.
There are large uncertainties in the methods used to make
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current predictions of the likelihood and consequences of direct heating.
- However, if the vessel can be depressurized before failure occurs, direct heating is precluded. Some recent studies by the NRC and its contractors and by the industry have indicated that there are a number of potential schemes for ensuring such depressurization.
O Have these " accident management" schemes been considered for the SP/90 WAPWR-PSS 720-29 AMENDMENT 3
'5794e:1d SEPTEMBER, 1987
-pp
- design, and if so, please describe them along with any conclusions
.ig that have been reached regarding their viability?
RESPONSE
Such " accident management" schemes have not been considered in the APWR Probabilistic Safety Study.
Potential strategies for ensuring primary system depressurization for APWR could be implemented through-the use'of specific' safety procedures during severe accidents.
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V WAPWR-PSS 720-30 AMENDMENT 3 5794e:1d SEPTEMBER, 1987
O ATTACHMENT E APWR Fission Product Inventory - for 40 species in CORSOR Code CORSOR Code APWR Inventory Group Species Kg
+(a,c)
- O s
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O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 l
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-ATTACHMENT F C
3.2 RECOVERY TIME FROM LOSS OF OFFSITE POWER q
The object of this section is to use the data to estimate the probability that j
(
recovery of offsite power after a LOSP exceeds a certain length of time.
The empirical distribution of recovery time is shown in Table 3-2.
Table 3-2 i
(
RECOVERY TIME DISTRIBUTION RECOVERY TIME NO. OF PCT. OF IN HOURS EVENTS EVENTS
+(a,c) l l
l' NOTE: Recovery time not obtainable for 3 events in data A rough estimate of the recovery time distribution would indicate that, as a i
/
whole, plants recover offsite power within one half hour about 48 percent of the time and within four he'urs about 77 percent of the time.
The four hour threshold is important in LOSP events at nuclear plants since plant battery systems can drain of all power in about four hours.
Recovery of offsite power, then, is crucial if the LOSP event is coupled with unavailabilities of the plant diesel generators or other backup power sources (assuming these sources cannot be made available within four hours).
0' ISource: EPRI Report NP-2301, " Loss of Offsite Power at Nuclear Power Plants Data and Analysis, 1982]
WAPWR-PSS AMENDMENT 3 E794e:1d SEPTEMBER, 1987
ATTACHMENT G (Sheet 1of4)
MOLAR GAS CONCENTRATIONS-SE BASE Time Mole Frac.
Upper Comp Lower Ccmp Reactor Cavity Annular
+(a,s, O
O O
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WAPWR-PSS AMENDMENT 3 E794e:1d SEPTEMBER, 1987
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ATTACHMENT G (Sheet 2of4)
MOLAR GAS CONCENTRATIONS SE BASE Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular
+( a, c ) -
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O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
1
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MOLAR GAS CONCENTRATIONS j
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Upper Comp Lower Comp Reactor Cavity Annular
+(a,c) i i
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I WAPWR-PSS AMENDMENT 3 l
E794e:1d SEPTEMBER, 1987 I
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MOLAR GAS CONCENTRATIONS SE BASE Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular
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+(a,c)
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O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
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I ATTACHMENT H (Sheet 1 of 3)
MOLAR GAS CONCENTRATIONS SEFC BASE (24 hr run) l Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular O-
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O WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
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ATTACHMENT H (Sheet 2 of 3)
MOLAR GAS CONCENTRATIONS SEFCBASE(24hrrun)
Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular f
g
+(a,c) 1 O
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O WAPWR-?SS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
.1 ATTACHMENT H (Sheet 3of3)
MOLAR GAS CONCENTRATIONS SEFC BASE (24 hr run)
Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular O,
+(a,c) i
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MOLAR GAS CONCENTRATIONS TE BASE Time' Mole Frac.
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O WAPWR-PSS.
AMENDMENT 3 E794e:1d SEPTEMBER, 1987 L1 ___ _-- -_. - - _ - _
ATTACHMENT I (Sheet 2 of 5)
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MOLAR GAS CONCENTRATIONS TE BASE Time Mole Frac.
-Upper Comp Lower Comp Reactor Cavity Annular
+(a.c)
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rO WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 1
C________________._...__
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ATTACHMENT I (Sheet 3of5)
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+(a,c)
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l WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 l
ATTACHMENT I (Sheet 4 of 5)
I MOLAR GAS CONCENTRATIONS
'TE BASE
' Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular O-
'+(a,c)
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WAPWR-PSS AMENDHENT 3 5794e:1d SEPTEMBER, 1987
ATTACHMENT I (Sheet.5 of 5)
MOLAR GAS CONCENTRATIONS TE BASE Time Mole Frac.
Upper Comp Lower Comp Reactor Cavity Annular
+(a,c)
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FIGURE 720.46 iii) A l-SE BASE (Sheet 1 of 4)
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WAPWR-PSS AMENDMENT 3 5794e:Id SEPTEMBER, 1987
O
+(a,c)
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FIGURE 720.46 iii) A i
O SE BASE (Sheet 2 of 4) t WAPWR-PSS AMERCHENT 3 5794e:Id SEPTEMBER, 1987
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SE BASE (Sheet 3 of 4) 1 WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
.v 7891,REBMETPES d1:e4975 3 TNEMDNEMA SSP-RWPAW
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WAPWR-PSS AMENDMEN1 3 5794e:1d SEPTEMBER, 1987
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I I
I t
i I
1 o
l I
l FIGURE 720.46iii) B SEFC BASE (Sheet 2 of 4)
WAPWR-PSS AMENDHENT 3 5794e:1d SEPTEMBER, 1987
j ~, [i(k O
i
+(ac){
q o
O I
O O
l I
I O
l i
FIGURE 720.46iii) B SEFC BASE (Sheet 3 of 4)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
., h :',
j
+(a,c) e i
O l
f
^
a OV,-
FIGURE 720.46 iii) B SEFCBASE(Sheet 4of4)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
O
+(a,c)
- D
- -v O
I I
l l
FIGURE 720.46 iii) C
(
TE BASE (Sheet 1 of 4)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
0 _,
+(a,c) e l
l I
I I
I L
l FIGURE 720.46 iii) C TE BASE (Sheet 2 of 4)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
+(a,c) 0-O l
I l
i 9
O O
i FIGURE 720.46 iii) C TE BASE (Sheet 3 of 4)
WAPWR-PSS AMENDMENT 3 i
5794e:1d SEPTEMBER, 1987 o _ ---
i
W i y.
+(a c)
G l
1 I
l l
I
(,
4' (r
1 FIGURE 720.46iii) C TE BASE (Sheet 4 of 4)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987 t
4 $
+(a,c)
G G
G I
.)
\\
}
l
~
j FIGURE 720.46viii) A SE BASE (Sheet 1 of 1) l WAPWR-PSS AMENDHENT 3 f
1 E794e:1d SEPTEMBER, 1987
, *' s p
+(a,c)
L-O 9
9 e
~
O~
FIGURE 720.46 viii) B SEFC BASE (Sheet 1 of 1)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
.,: A f.
+(a,c).
v 1
O l
e I
8 l
)
9-FIGURE 720.46viii) C O-TE BASE (Sheet 1 of 1)
WAPWR-PSS AMENDMENT 3 5794e:1d SEPTEMBER, 1987
- - _ - - _ - _ _ _ _ _