Text

Response to Supplemental Information Request Regarding Technical Specifications Condensate Storage Tank Minimum Level License Amendment Request
	ML12300A279
Person / Time
Site:	Farley
Issue date:	10/25/2012
From:	Ajluni M; Southern Nuclear Operating Co, Southern Co
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	NL-12-2080
	Download: ML12300A279 (60)
	v • d • e

Mark J. Ajluni. P.E.

Southern Nuclear Nuclear Licensing Director Operating Company. Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 2059927673 Fax 205.992.7885 October 25,2012 SOUTHERN'\\'

COMPANY Docket Nos.: 50-348 NL-12-2080 50-364 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Units 1 and 2 Response to Supplemental Information Request Regarding Technical Specifications Condensate Storage Tank Minimum Level License Amendment Request Ladies and Gentlemen:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated August 20, 2012 (Agencywide Documents Access and Management System (ADAMS),

Accession No. ML12234A743), Southern Nuclear Operating Company, Inc.,

(SNC) submitted a license amendment request for TS 3.7.6, "Condensate Storage Tank." The change revises the minimum condensate storage tank level from 150,000 gallons to 164,000 gallons. On September 25, 2012, the NRC provided SNC with a Request for Supplemental Information letter (ML12257A098), containing 4 questions regarding the license amendment request. contains the responses to the NRC's request for supplemental information. Enclosure 2 contains a calculation supporting SNC's response. As discussed with the NRC on October 25, 2012, this letter will be supplemented with Enclosure 3, which will contain Westinghouse Electric Company, LLC proprietary information that also supports SNC's response, in a separate letter.

U.

Nuclear Regulatory Commission NL-12-2080 Page 2 This letter contains no NRC commitments. If you have any please contact Ken McElroy at (205) 992-7369.

Mr. Mark Ajluni states he is Nuclear Licensing Director of Nuclear Operating Company, is authorized to this oath on Southern Nuclear Operating Company and, to the best of his knowledge belief, the forth in this letter are true.

~..L-day

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My commission expires: _1--___

Sincerely,

~2Df---

M. J. Ajluni Nuclear Licensing Director MJAlCLNllac

Enclosures:

1. Responses to Request for Supplemental Information

2. SNC Calculation BM-95-0961-001, Basis", Version 6 cc:

Southern Nuclear Operating Company Mr. S.

Kuczynski, Chairman, President &

Mr. D. G. Bast, Executive Vice President & Chief Nuclear Mr. T. A. Lynch, Vice President -- Farley Mr.

L. Ivey, Vice President -- Regulatory Affairs Mr.

J. Adams, Vice President -- Fleet RTYPE: CFA04.054 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R.

Martin, NRR Project Manager -- Fleet Mr.

L. Crowe, Senior Resident Inspector -- Farley

Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Supplemental Information Request Regarding Technical Specifications Condensate Storage Tank Minimum level ResP4:>m~es to Request for Supplemental Information to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 3.7.6 Question 1:

Regarding Standard Review Plan (SRP) Branch Technical Position (BTP)

Reactor Systems Branch (RSB) 5.1, LAR provides neither the assumption changes, nor the new BTP RSB 5.1 analysis reflecting the change to assumptions for determination of the revised water volume.

Clarify whether the current analysis satisfying BTP RSB 5.1 is changed in support of LAR. If the current analYSis is changed, provide the new analysis for NRC staff review.

Please also clarify whether the Technical Specifications (TSs) for CST water is based on the RSB 5.1 (natural circulation cooldown analysis) or not. If not, specify the basis (Le., the plant-specific analysis) supporting the and provide information to justify the associated basis.

a) Standard Review Plan (SRP) Branch Technical Position (BTP) Reactor Systems Branch (RSB) 5.1 was in the license amendment request (LAR) specifically for section G, "Auxiliary Feedwater Supply". This C!or-flnn of the RSB 5.1 states that the auxiliary feedwater system shall have a sufficient inventory to allow operation at hot shutdown for at 4

hours, followed by cooldown to the conditions permitting operation of the residual heat removal system (RHR). This inventory for cooldown is to be based on the longest cooldown time needed with either only onsite or only offsite power available with an assumed single failure. shows that the condensate tank (CST) has sufficient inventory in the maximum protected water area to hold reactor at hot standby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cooldown in 4 at 350 at a cooldown of 50 °F/hr, including:

the total water volume lost from ruptured of AFW pump reCirculation lines and unisolated flow instrumentation lines; volume for one reactor coolant pump (RCP) in operation for the duration of the event (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) plus 10 megawatt thermal (MWt)

RCP heat added and decayed over one hour; minimum tank level to prevent vortexing.

Relative to the requirements of RSB 5.1, Section G, the ro",C!on calculation does not represent a change in satisfying the requirements of this section. The only change to assumptions made for determination of the revised CST water volume is the addition of an assumption that considers the potential for vortex formation. Thus, a minimum submergence is added to the CST required volume to prevent formation of a vortex.

1 to NL*12*2080 to Request for Supplemental Information Regarding LAR for 3.7.6 The event described above is the most limiting, requiring 154,054 gallons.

Other including those with either only onsite or only offsite power available with an assumed

failure, less inventory and are discussed in response to question 2.

b) The

- Operability (B.3.7.6) (Mode 3 for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months ) assumes natural circulation, this event is concurrent with a LOSP where have lost power; thus, natural circulation is in Furthermore, per the documentation of an engineering analysis of all events that assume a loss of off-site power (LOSP) as defined by FSAR Chapter 15 and the TS Dd~:it::l::; requirements, natural circulation is considered, since power is lost RCP during a LOSP In these no addition to the is included the pumps are not operating; however, 10MWt residual RCP heat is added due to the power operation prior to the event with LOSP.

The licensee stated in the LAR that the revised calculation for CST minimum volume is based upon additional assumptions regarding loads as referenced from the Component Design Basis Inspection also stated that plant events involving the usage of were reanalyzed with the revised calculation to identify the most limiting event to at the new minimum volume amount.

Provide additional information on how the new heat load assumptions were factored into the revised calculation. Also provide additional information on all of the events analyzed with revised calculation for the CST to verify how the licensee identified the most limiting event involving the a) (1) Heat Load Assumptions:

Decay heat load was based on assuming 102% power; Le., 102% of 2775 MWt (100% power). Thus, the volume to remove decay heat was based on 2831 MWt. Prior to the CDBI, the previous version of design basis calculation for the CST volume verification considered load on 100% power.

Sensible heat load assumption was based on the Tavg (hot) of OF plus 6 OF (583 for measurement uncertainty plant events where the unit is being shutdown. Prior to the CDBI, the previous of design basis calculation the CST volume verification determined sensible heat at Tavg (no load) of 547 conditions.

plant events where the unit is being held at hot standby, no heat load is added to the CST volume since the unit is not in transition to a shutdown mode but is held in hot standby with the intention to return unit to power.

-2 to NL~12~2080 Response to Request for Supplemental Information Regarding LAR for 3.7.6 Reactor Coolant Pump (RCP) heat load assumptions were based on several factors. First, if a loss of offsite power (LOSP) was event or concurrent with another event, no RCP heat was added during the hot standby or cooldown the unit. In these instances, only 10 MWt net heat input added the RCS was included due to power operation prior to the event. Secondly, if an LOSP was not the event or not concurrent with the event and the unit is being shutdown, RCP heat for operation of pump(s) during the cooldown and the heat added during power operation prior to the event were considered in determining the volume.

following are specific assumptions relative to RCP heat load included for the C\\I",.nT'" analyzed:

Due power operation prior to an 1 0 MWt net heat input is added to Reactor Coolant System (RCS) for all events analyzed with exception to of Normal Feedwater (LONF) event, which conservatively adds 15 MWt input to RCS. This net heat is added to the volume requirements due to operation of the RCPs at power prior to the event.

Technical Specification Bases Operability (9 hrs. at hot standby), Main Feedwater Line Break (MFWLB), Main Steam Line Break (MSLB) with LOSP, Small Break Loss of Coolant Accident (SBLOCA), and LOSP events were analyzed with no heat added during hot or cooldown.

each of these LOSP is as the event or concurrent with the event.

TS Design (Normal Cooldown 2 hrs. hot standby with 4 hrs. cooldown) event assumed 1 RCP pump will operating during the 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months duration of the

Depressurization of Main Steam assumes three operate for 10 minutes to reach RCS equilibrium, and then, one operates for the remainder of 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with the reactor in hot standby. This assumption is supported by Chapter 15 of the FSAR and WCAP 15097, "FNP Units 1 and 2 Replacements Generator Program NSSS Engineering Report Book 1, March 2001".

Main Steam Break without LOSP event assumes three RCPs operate for the duration of the event which is determined by a conservative cooldown of 50°F/hr from Tavg (no~

load) to

Loss of Normal Feedwater (LNFW) event assumes RCPs operate for 10 minutes to reach RCS equilibrium then

-3 to NL-12-2080 to Request for Supplemental Information LAR for operates for remainder of 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with the r£",-","Tnr in hot standby. These assumptions are supported by Chapter 15 of the Vortex During the Component Design Inspection 111.21), the of a vortex prevention calculation for the CST was identified as an unresolved issue. Subsequently, a Green non-cited violation was issued in NRC Quarterly Report "Joseph M.

Nuclear Plant NRC Integrated Inspection 05000348/201 and 05000364/2012003",

July 20, 201 violation, a minimum submergence to prevent formation added (Enclosure Vortexing was considered for where a breach to the tank's unprotected walls or connecting lines could occur and allow to enter the tank beneath the tank's diaphragm. It has assumed that this breach is due to a tornado missile or seismic event. The that make this assumption are the Normal Cool down event and the cuc.,ue with a or event concurrent. Assuming a failure of the CST that would allow into below diaphragm during a Normal Cooldown event is a conservative assumption that adds to the minimum required volume of the CST.

unusable volume below the AFW pump's suction unusable volume is considered in minimum to prevent vortex formation for events Il"Iontl"lol"I (3) Inventory Assumptions:

The CST inventory loss due to the rupture of AFW pump's minimum flow recirculation lines and the tank's instrumentation line has been assumed for events that postulate a tornado concurrent. As described for the minimum submergence assumption, and Normal Cooldown (TS Bases).

The CST inventory loss due to main steam (MSLB) and feedwater line break events (MFWLB) is accounted for in the determination of the CST volume. That the volume of auxiliary feedwater lost through line breaks is not available to provide shutdown cooling of the RCS.

Assumptions are made and documented for time required for isolation of AFW through breaks in to determine volume of the inventory IV';'""",,,,.

b) Determination of the most limiting event The Technical Specification Bases, B in the Applicable Safety

Analysis, that the provides cooling to remove decay heat and to down the unit following all in the analysis as discussed in the FSAR, 6 and 15. Upon review

-4 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 3.7.6 FSAR chapters, as well as the TS Bases, the events that require cooling the RCS by the AFW were identified and the operability and design requirements of the CST per the LCO section of the CST TS Bases were defined. These events and requirements include:

LOSP wi Seismic Event LOSP MSLB wlo LOSP LNFW wlo LSOP

Depressurization Main Steam LOSP wi Tornado Event SBLOCA

MSLBw/LOSP MFWLB w/LOSP TS Bases - Design (Normal Cooldown)

TS Bases - Operability The TS Bases - Operability requirement of the CST is defined as having sufficient water available to maintain the RCS in MODE 3 for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharge to the atmosphere concurrent with a loss of offsite power. In addition, the TS Bases - Design, labeled "Normal Cooldown",

defines the design bases requirement of the CST as holding the unit in Mode 3 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , followed by a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months cooldown to RHR entry conditions of 350°F at a rate of 50°F/hr.

The previous version of the design basis calculation identified the CST sizing components that made up the required volume. These sizing components consisted of decay heat, sensible heat, and RCP heat removal, as well as inventory loss due to AFW recirculation and instrumentation line ruptures. Pressurizer heater heat input to the RCS as required by the FSAR accident analysis for Loss of Normal Feedwater has been included in this version of the calculation. As discussed in the CDBI and documented in the CDBI report, a volume for vortex protection has been added to the CST minimum required volume for events that consider a seismic event or tornado event concurrent as well as CST inventory volume losses due to main steam and feedwater line break events.

For each event identified including the TS Bases - Operability and TS Bases - Design requirements, the CST minimum required volume to remove the specific heat load from the RCS was determined upon application of the assumptions as described above in response to question number 2(a). The required volumes of CST water to remove the different RCS heat components (decay, sensible, and RCP) were determined using a calometeric method whereby the enthalpy differences between the maximum allowable water temperature in the CST and the saturated steam pressure of the steam generator secondary side were used.

E1 - 5 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 3.7.6 Portions of the AFW pump's minimum flow recirculation line and the four instrumentation lines attached to the AFW pump suction pipes are located outdoors and exposed to a potential tornado missile. Thus, the inventory losses due to the rupture of these lines have been considered in determining the CST required minimum flow for events whereby a tornado is assumed. These events include !\\Iormal Cooldown, LOSP with Tornado, and LOSP with Seismic event.

It is assumed that the recirculation lines from all three pumps would be isolated within 30 minutes. The recirculation flow from each pump is conservatively considered greater than the calculated value to accommodate for the slight decrease in frictional loss due to a line break.

The maximum volume of water lost during the 30 minutes span before isolation is the summation of all three purnps' minimum flow assumed. No inventory loss is considered from the CST through the AFW pump's recirculation connection to the tank since this connection is above the 164,000 gallon protected volume of the tank.

The break point of the four instrumentation lines is assumed to occur at the lowest location above the ground level where the instrumentation lines are exposed to missile impact. The inventory loss through the breaks is based on the flow through a discharge nozzle of a size equivalent to the ID of tubing at a pressure equivalent to the middle point height between the protected volume (164,000 gallons) level to the assumed break point of the tubing ignoring line losses. It is considered that these four instrumentation lines will not be isolated during the 6-hour unit cooldown or the 9-hour unit hot standby period.

Thus, the total inventory losses due to the ruptured instrumentation lines and the AFW pump's minimum flow recirculation lines were accounted for in determining the CST required minimum volume for events that occur concurrent with a potential tornado missile.

Additional CST inventory losses due to MSLB and MFWLB events were also considered in determining the minimum required volume of the CST.

The magnitude of these losses was determined from the design bases calculations of record, "Verification of AFW Flow Bases". The Units 1 and 2 calculations identify the required AFW flow rates for various normal and accident events which are supported by the AFW system. These flow models of the system for these accidents determined the flow rates through the main steam and main feedwater line breaks to the faulted steam generator. It has been assumed that the time required for isolation of the AFW flow through the MSLB break is 15 minutes and 30 minutes for the MFWLB. Given this information, time of isolation and magnitude of AFW flow through these breaks, the CST inventory losses were determined for each event and accounted for in the determination of the minimum required volume of the CST. No credit for AFW heat removal was applied for the MSLB event, even though some RCS heat removal does occur since the MSLB location is downstream of the faulted steam generator.

E1 - 6 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 3.7.6 With the volume of CST water determined to remove each heat load component of the RCS, the CST inventory losses, and the minimum submergence level required to prevent vortex formation, the most limiting event could be determined. Summing the water volumes required for each sizing component revealed that the TS Bases - Design (Normal Cooldown) was the most limiting event. It is noted that this event includes several conservatisms which account for its greater volume requirement, such as the inventory losses due to the rupture of the AFW pump's minimum flow recirculation lines and the four instrumentation lines, as well as the vortex formation prevention volume. These added volumes are considered conservative since the Normal Cooldown event does not require the assumption of a tornado event concurrent with this event. The minimum required volume of 154,054 gallons for this event was used as the bases in establishing the greater than or equal to 164,000 gallons TS minimum level for the CST.

Question 3:

The LAR states that additional consideration regarding vortexing was applied during the revised calculation of the CST minimum volume. However, the LAR did not describe specific considerations that factored into changes made to the referenced revised calculations.

Provide additional information to describe how the licensee factored in the vortexing effects as part of the revised calculation for the CST volume.

SNC Response:

During the CDBI inspection, the NRC team identified an unresolved item (URI 05000348, 364/2011010-04) regarding the evaluation of the CST minimum required submergence for the AFW pumps, given the potential for vortex formation in the CST. During the inspection, it was observed that the design calculation for the CST sizing did not evaluate the effects of tornado missile damage to the un-protected portion of the CST which could create an air introduction path under the CST bladder which would allow a vortex formation. Subsequently, a Green non-cited violation was issued in the NRC Quarterly Report "Joseph M. Farley Nuclear Plant NRC Integrated Inspection Report 05000348/2012003; and 05000364/2012003", dated July 20, 2012.

In response to this URI and Green non-cited violation, compensatory measures have been taken to evaluate the minimum required submergence for the AFW pumps assuming the potential for vortex formation in the CST. This evaluation has been performed and issued as a separate and unique design calculation that determines the minimum submergence level required for the specific physical configuration of the AFW pump's suction piping (see Enclosure 3 which will be submitted in a separate letter as a supplement to this letter). The results of this E1 - 7 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for 3.7.6 calculation have been used as design input into determining the minimum required volume of the The CST has two 8" AFW suction pipes one for the TDAFW pump and one for both MDAFW pumps. Both suction pipes open 4" from the tank's bottom, facing down at a angle.

suction piping centers are approximately 1'-3" apart. The CST has an internal bladder that prevents introduction of air under normal operating conditions.

The primary technical reference utilized in determination of the minimum submergence level is Calculation-Note Number FAI/09-19, Rev. 0, titled "Vortex Evaluation for Vogtle and Farley RWSTs and Hatch CSTs", dated January 2009, by Fauske Associates, Inc. (Attachment 3 to Enclosure 3). Note Enclosure 3 contains Westinghouse Electric Company LLC proprietary information and is not included with this will be submitted in a separate letter as a supplement this letter.

This calculation-note was issued to Southern Nuclear by Westinghouse Nuclear Services letter 8458 dated 1/1612009 as supporting documentation to the GL 2008-01 This calculation-note was reviewed and evaluated for applicability to the Farley CST in determining the minimum submergence level required to prevent vortex formation.

This document states in the summary that data taken for tank configurations D.C.Cook, McGuire, Catawba, Oconee and Cooper nuclear plants all relate to the specific configurations used in the Southern Nuclear plants. In addition, it that specific measurements all provide justification for the manner in which air intrusion should for the Vogtle, Farley, and Hatch CSTs. The obtained from data taken produced results that are consistent with radial inflow conditions being the mechanism whereby significant gas intrusion would be drawn into the specific suction configurations. The downward facing suction configuration that is installed in CSTs acts to considerably suppress the potential for air intrusion. Evaluations of this radial inflow to a downward facing elbow resulted in a bounding correlation for misbehavior that is given by SID = 0.5(NFR}2 where the submergence S is the same as that defined in 7, Catawba Fueling Water Storage Vortex Study Tank and Suction Nozzle downward facing configuration. Since the Farley AFW pump's configuration is a 45 degree downward facing configuration, this correlation can be used to determine the submergence required to suppress air intrusion and vortex formation.

However, upon development of calculation for determining the minimum submergence (Enclosure 3) for the AFW pump's suction nm:zles. the equation also presented in the calculation-note FA1/09-19 based on the Harleman correlation was utilized (note Enclosure 3 contains Westinghouse Electric Company LLC proprietary information and is not included with this letter. Enclosure 3 will be submitted in a separate letter as a supplement to this letter).

correlation defines the crncnr'c level required above the horizontal entrance to a vertically E1 - 8 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 3.7.6 downward suction as shown in Figure 5(a) of the FA1/09-19 Calculation Note FAI/09-19. This correlation is given as Sw'D = 0.75[NFr]o.4 on page 13 of 25. Even though the Farley suction nozzle is a 45 degree downward facing nozzle configuration, this Harleman correlation was used to provide a conservative submergence level. Using this vertically downward suction correlation increased the submergence level by a factor of two over the submergence for a 45 degree angle pipe or elbow nozzle facing downward. Thus, this greater submergence level was used in determining the volume component required in the CST sizing calculation for vortex prevention.

Question 4:

The LAR is incomplete and the staff cannot initiate a technical review until, at a minimum, the following is provided:

Calculation of post-trip water requirements.

Information that supports an independent evaluation of the level necessary to prevent vortexing.

Provide the licensee's determination of the level that prevents vortexing.

Applicable updated Final Safety Analysis Report sections.

SNC Response:

a) Calculation of post-trip water requirements.

The calculation SM-95-0961-001, Version 6, "Verification of CST Sizing Basis" (Enclosure 2 to this submittal), consists of the detail calculations, assumptions, and design inputs that form the bases for the determination of the post-trip water requirements of the CST. A detailed results and conclusions presented on sheets 21 and 22 of this calculation summarizes the minimum CST volume requirements for the TS Bases - Operability and TS Bases - Design (Normal Cooldown) requirements, including the volume requirement for the LONF without LOSP event which results in the worst case CST volume requirement of the FSAR Chapter 15 accidents.

b) Information that supports an independent evaluation of the level necessary to prevent vortexing.

The information necessary to support this request can be found in calculation SM-SNC335993-001 Version 2.0, titled "CST AFW Pump Suction - Submergence Analysis". This calculation will be included in, which will be submitted in a separate letter as a supplement to this letter. The purpose of this calcuation states "for the withdrawal of water from the CST, determine the minimum submergence water level in the tank to prevent vortexing at the AFW suction inlet when the flow rate is E1 - 9 to NL-12-2080 Response to Request for Supplemental Information Regarding LAR for TS 700 gpm. This level (water volume) has been incorporated as input into the "Verification of Sizing Basis" calculation, BM-95-0961-001 Version 6. Attached SM-SNC335993-001 Version 2.0 (Enclosure 3, which will be submitted in a separate letter as a supplement this is Fauske &Associates, Inc. Calculation-Note FAI/09-19 referenced in the response to question 3 above. As stated, calculation-note provides the bases for the method used in determination of submergence level required to prevent vortex formation and air intrusion into AFW pump's suction piping.

The summary of conclusions states the minimum submergence level required in the based on the operation of two (2) MDAFW pumps or the TDAFW pumps shall 9.78 inches from the bottom of the tank which includes 4 inches of unusable volume below the suction nozzles. Also, the minimum submergence level required in the based on the operation of one (1) MDAFW pump shall 8.36 inches from the bottom of the tank.

c) Provide the licensee's determination of the level prevents vortexing.

The equation based on the Harleman correlation presented on page 13 25 of FAI/09-19, Calculation-Note the submergence as water height above horizontal entrance to the vertically downward suction location as shown in Figure 5(a) of this calculation-note.

correlation is given as Sw'D ::: O.75[NFr]0.4. Even though the Farley suction nozzle is a 45 degree downward facing nozzle configuration that results in a lesser submergence level, as shown in Figure 7, the Harleman correlation was used provide a conservative level. Using this vertically downward suction correlation increased the submergence level a factor of two over the submergence for a 45 degree angle pipe or elbow nozzle facing downward. Thus, this greater submergence level was used in determining the volume component required in the sizing calculation for vortex prevention. The submergence level, based on the vertically downward suction configuration, the piping and the AFW pumps flow rates, was determined to be 5.78 inches. Since AFW pump's suction pipes open at 4 inches from the tank's bottom, the submergence level to determine the volume component to intrusion and vortex formation is 9.78 inches Enclosure which will be submitted in a letter as a supplement to this letter).

d)

Applicable updated Final Safety Analysis Report sections.

The following sections of the FSAR will be updated, as appropriate, following approval of this license amendment request (next page).

E1 - 10

1 to NL-12-20S0 to Request for Supplemental Information Regarding LAR for TS FSAR 6.5.1, Rev.

June 2 - AFVIJ Design Section Rev. 24, June 2012, -

Storage Facilities FSAR Section 15.2.S, Rev.

June 2012 Loss of Normal Feedwater FSAR Section 1 24, June 2012 -

of All AC Power to the Station Auxiliaries FSAR Section 15.2.13, Rev. 24, June 2012 - Accidental Depressurization of Main Steam System Section 1 24 June 201 of Reactor Coolant From Small Ruptured or From in Large Pipes Which Actuate Emergency Cooling System Section 1

, Rev.

June 2012 - Rupture of Main Line FSAR Section 1 Rev. 24, June 201

- Main Rupture of a Main ~O<'f'I\\A/<>

Line Pipe E1 - 11

Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Supplemental Information Request Regarding Technical Specifications Condensate Storage Tank Minimum Level License Amendment Request SNC Calculation BM-95-0961-001, "Verification of CST Sizing Basis", Version 6

Southern Nuclear Design Calculation SOUTHERN A..

COMPANY EIl~rgy to S~r&J~ Your World*

Calculation Number:

BM-95-0961-001 Plant: Farley Units 1 and 2 lUnit:

IDiscipline:

01 02 [8]1&2 Mechanical

Title:

Verification of CST Sizing Basis I

Subject:

CST/AFW Purpose / Objective: Verification of CST Sizing Basis System or Equipment Tag Numbers: 01 P11 T001, 02P11 TOO1 Contents Topic Page Attachments

of (Computer Printouts, Technical Papers, Pages Sketches, Correspondence)

Purpose of Calculation 3-4 Appendix "A" 18 Summary of Conclusions 21-22 Attachment "A" 1

Methodology 4

Attachment "B" 2

Assumptions 4-5 Design Inputs 4-5 Design Inputs/References 23 Body of Calculation 5-21 Total # of Pages including 45 cover sheet &Attachments:

Nuclear Qualit Level I:&l Safet -Related o

o Version Record Originator Reviewer Approval 1 Approval 2 Version Printed Name Printed Name Printed Name Printed Name No.

Description Initial I Date In~lall Date InKlal1 Date Initlall Date W.J.Jennings; Andy Patko; C.M. Sellers; C.M. Sellers; 5

Status: AP CMS/7-5-2012 WJJ/7-5-2012 AJP/7-5-2012 CMS/7-5-2012 Revised to modify design basis for the CST per TEs. (see Sht. 1 for TEs).

W.J.Jennings C.M.Sellers C.M.Seliers 6

Status: AP C!-V 5 0~5 Revised to add LONF event and If!!:!z

~o It::) /iO/;L modify MFWLB event.

lo/(oh "Z-leJ}O/I~

Notes:

NMP-ES-039-F01 Version 2.0 NMP-ES-039-001

Southern Nuclear Design Calculations Calculation Number:

Sheet:

BM-95-0961-001 1

CALCULATION COVER ROCRAMrfYPE Calculation prepared in support of REA 95-0961 This REA was prepared to resolve condensate storage tank issues identified by Assessment Observation AFW-tv{ECH-02. Since power up-rate is currently being evaluated for FNP, power up-rate is considered in this evaluation.

- NOTE:**

Revision 2 ofthis calculation does not affect the referenced material in the Feedwater Functional System Description (A-I&lOlO). A-I & 1010 has been reviewed for this determination.

Revision 3 fixes a typographical error on Sheet No.7.

Revision 4 ofthis calculation was performed and affects FSAR Sections 6.5 and 9.2 and the Auxiliary Feedwater Functional Description 81010).

to these documents have been initiated.

Revision 5 of this calculation was performed to modify the design basis for the CST in resolution of TE TE 286016, TE TE 289230 and TE289260.

Revision 6 of this calculation was performed to modify the loss of CST inventory and results for the MFWLB event add the calculations and results for the LONF event and provide reference to RER SNC41 9117 2 response.

4 Revised per REA 99*1965 33 13 UYPN Iv iDWVl 5IZ~/')GJ 3

Revised text on Sheet 7 31 II MGG OWM PES 1123/98

~. Change 10 SG level selpoints ChlUlgeto CST Design Basi.

T.mp....ture (SCS C.laSM*9S.0nl.

31 31 III II MGG BKS MEA DWM PES RCG 6/12/98 6/6/96 ODS)

I 0

Initial Issue 31 II DWM SSR RCG 3/12/96 NO.

REASON FOR REVISION TOTALNQ.

LAST BY CHECKED APPROVEDI DATE OFSHEETS SHEET NO.

ACCEPTED RECORD OF REVISIONS BM*95*0961*Q01 Calculations.docx

Southern Nuclear Design Calculations Calculation Number:

Sheet:

BM-95-0961-001 2 of 23 CALCULATION SHEET PROJECT: Farley DATE 03/06/96 TABLE OF CONTENTS

1.

II.

III.

IV.

CALCULATIONS V.

RESULTS / CONCLUSIO II VI.

REFERENCES 12 APPENDIX A (19 sheets) 13 See Calculation Cover Sheet for Table of Contents BM-95-0961-001 Caicuiations.docx

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BM-95-0961-001 3 of 23 I.

INTRODUCTION I PURPOSE The purpose of this calculation is to verify the sizing basis of the Condensate Storage Tank (CST). This calculation is therefore composed of the following determinations:

A. Determine the maximum protected volume of the CST.

B. Verify adequate volume is available in the missile protected portion of the CST for "Normal Cool down";

that is, to hold the reactor at hot standyby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cooldown in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 350 OF at 50 OF/hr.

where RHR may be utilized for cooling. Up-rate power conditions of 2785 MWth (2775 MWth core power plus 10 MWth from the RCPs) will be considered in this evaluation. Also, verify adequate reserve margin is available considering a missile rupture of the recirculation line from the AFW pumps back to the CST and the four instrumentation lines for the two suction lines of the Auxiliary Feedwater Pumps. Since the portions of these lines are located outdoor and are exposed to a potential tornado missile, the impact to the CST and AFW systems due to a potential rupture of these lines will be evaluated. Also, verify adequate reserve margin is available to provide a minimum submergence water height above AFW pump nozzles to prevent vortex formation.

C. Verify adequate volume is available in the missile protected portion of the CST for a" Main Feedwater Line Break with Loss of Off-Site Power" event; that is, to hold the reactor at hot standyby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cool down in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 350 OF at 50 OF/hr. where RHR may be utilized for cooling. Up-rate power conditions of 2785 MWth (2775 MWth core power plus 10 MWth from the RCPs) will be considered in this evaluation. Also, verify adequate reserve margin is available considering the loss of CST inventory due to I the main feedwater line break. No other line failures, such as, AFW pumps recirculation or CST instrument lines, are considered to fail due to a seismic event or tornado generated missile. Also, no reserve margin is required to provide a minimum submergence water height above AFW pump nozzles to prevent vortex formation since no lines attached to the tank are assumed to fail allowing air to enter the tank.

D. Verify CST capacity based on the Technical Specification Bases (OPERABILITY) that sufficient water is available to maintain the RCS at hot standby conditions for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharge to the atmosphere concurrent with a total loss of off-site power. Up-rate power conditions will be also considered for this case (Reference 4).

E. Verify adequate volume is available in the missile protected portion of the CST for a "Loss of Normal Feedwater" (LONF) event w/o Loss of Off-Site Power; that is, verify sufficient water is available to maintain the RCS at hot standby conditions for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharge to the atmosphere. Up-rate power conditions of 2775 MWth core power will be considered in this evaluation. The WCAP 15097 (Ref.

22) assumes a conservatively large RCP net heat input of 15MWt. This initial net heat input of 15MWt is assumed to decay over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Per this WCAP, all three(3) RCPs operate at the initiation of the event for 10 mins and one(1) RCP operates for the duration of the event; i.e. 9 hrs. in hot standby. No line failures, such as, AFW pumps recirculation or CST instrument lines, are considered to fail due to a seismic event BM-95-0961-001 Calculations.docx

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BM-95-0961-001 4 of 23 or tornado generated Also, no reserve margin is required to provide a minimum submergence water height above AFW pump nozzles to prevent vortex formation since no lines attached to the tank are assumed to fail allowing air to enter the tank.

WCAP 15097, during a of Normal Feedwater (LONF) event, the pressurizer proportional and backup heaters are operable. The total capacity the is 1.4 MWt.

heaters output an addition to the RCS energy which must be removed by AFW system.

II.

METHODOLOGY calculation code MAP*i21, Version V01 was used to the decay heat of the core. This model calculates decay heat based on NRC Branch Technical Position 9-2. FSAR section 9A.1 and figure 9A-2 discusses the conservatism of basing the decay heat on Branch Technical Position ASB 9-2 as opposed to the original provided by Westinghouse specification Revision 1 and as presented in FSAR figure 9A-i.

The results of heat as shown in Appendix "AI! is based on of 2785 MWt (2775 MWt core power plus 10 MWt from The model decays the total in Btu/hr equivalent to 2785 MWt, including the heat. This version of the calculation separates the decay heat due to fission products from RCP and applies both to the CST volume sizing individually. That MWt due to fission product heat is decayed according to the model; however, the 10 MWt to heat is decayed over a one(1) hour period and both applied to the required CST volume separately.

This calculation CST volume required for four(4) different plant events: Normal Cooldown hrs at hot standby and 4 to 350°F at 50"F/hr where RHR is utilized for cooling), Main Break w LOSP hrs at hot standby and 4 hrs to at 50°F/hr where RHR is utilized for cooling), Hot Standby for 9 hrs. wI LOSP per T.S.

B.3.7.6 and Loss of Normal Feedwater wlo LOSP. Several different heat loads, volume due to tornado missiles, events and breaks, and a minimum submergence level to prevent vortex formation have been determined for each of the plant events, as to determine the CST volume required to cooldown the for each plant event.

III.

INPUT I ASSUMPTIONS

1. Up-rate power conditions of 2785 MWt MWt core power plus 10 MWt from RCPs).

2.

3.

temperature 110°F (Reference 1

4.

trip occurs from 102 percent power. An initinite reactor operating time is

5. The RCS is maintained at hot standby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cooldown to accomplished in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Hot standby is defined as reactivity than 0.99 temperature greater or equal 350 OF.

6.

of decay heat is based on NRC Branch Technical Position ASB BM*95*0961*001 Calculations.docx

Southern Nuclear Design Calculations

7. Specific volume of water (VI) at 11 is 0.0161 ft3/1b. (Reference 6)

8. To envelop all possible scenarios of decay heat removal, the worst case steam generator back (highest) from 1 will used to the enthalpy steam from steam generators.

9. During cooldown the steam from hot standby condition,1155 psi a to 1

psia (saturation pressure at 350 OF).

enthalpy 1204 Btu/lb to an enthalpy of 1187 Btu/lb.

The lower enthalpy, 1187 Btu/lb is conservatively used to determine the water volume required Attachment uA"}

10. "Deleted"

11.

on the as-built condition of the CST, missile protected portion of the tank is approximately 16' overall height 12, 23). This protected portion a volume of 204,706, (Volume =(1 2") x rr(46'}2/4 x 7.48 204,076 This volume of 204,076 gallons does not however the condensate makeup and return line, 24" UL.r-'-: d,e. connection to the This line connects to CST in the portion the tank, and is Seismic Category II, not protected from a tornado missile.

establishes the maximum protected volume of the since a failure of this is assumed based on design.

Sheets 5 for determination of the maximum protected volume of the CST.

12.

rupture of the pump recirculation line is assumed to occur at the location near CST connection where the portion of the line is unprotected by missile barrier (References 11 and 18).

13.

four instrumentation lines for Auxiliary Pump suction to rupture at the same elevation as of suction at the

{el. 1 conservative purpose. This elevation is the point the ground level for the portion the instrumentation lines that are unprotected from the missile impact.

14. RCP heat added is equivalent to 5 MWt per pump; however, the pump net heat added to is 10 MWt when the unit is at 100% power (Reference 22). No RCPs are in operation during a event.

15. Isolation of the faulted will be rnnl."h,>rI by FNP within minutes to a main feedwater line break.

Attachment "B"}

IV.

CALCULATIONS 8M*95-0961*001 Calculations.docx

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BM-95-0961-001 6 of 23 Determine the maximum protected volume of the CST. This volume is based on the elevation of the condensate makeup and return line, 24" HBD-252. Since this line connects to the CST in the missile protected portion of the tank, is seismic category II, not protected from a tornado missile and the only non missile protected Seismic Category II line in the missile protected portion of the tank this line establishes maximum protected volume of the tank. Thus, the maximum protected volume of the CST is determined by the elevation of the invert of the condensate makeup and return line since failure of this line is assumed based on it's design.

From vendor documents U-161693 and U-213481 (Reference 11), the 24 inch dia, condensate and makeup return nozzle is 14'-2 SA" from the bottom of tank. The piping 24" HBD piping and tank nozzle is Sch. 40 with a wall thickness of 0.375 inches. Therefore, the invert of the pipe is:

Condo Makeup Invert = 14.229 - (10/2), where the 10 of the piping is 23.250 in.

= 14.229 ft - ((23.250 in/2) x 1 ftl12 in)

= 13.260 ft Now, Tank bottom area: rrr2 =rr (23 ft.)2 = 1662 ft2 (Reference 11)

Based on 24" HBD-252 piping invert of 13.260 ft, the maximum protected volume of the CST is:

W (maximum protected volume of the CST) = Tank Area x height

= 1662 ft2x 13.260 ft 0.1337 ft3/gal.

W (maximum protected volume of the csn = 164,832 gallons B. Normal Cool down Determine required CST volume based on holding the reactor at hot standby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cooldown in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 350°F at 50°F/hr where RHR may be utilized for cooling.

Decay Heat Adjust decay load from Appendix "A" which represents 2775 MWt (100% power) plus 10 MWt pump heat to values that represents only decay heat due to fisson products decay heat.

The portion of decay heat results that is due to pump heat is: 10 MWt 12785 MWt =0.00359 The decay heat from App. CIA" at 2 hrs after shutdown is 0.35713 x 109 Btu.

BM*95*0961*001 Calculatlons.docx

Southern Nuclear De:siClln Therefore, the decay heat at 2 hrs.

shutdown from products alone 0.35713 x 1

- 0.00359(0.35713 x 109)==

x 1 iUs the reactor at 102% of rated reactor thermal power for this event, the fission product decay shutdown...."'~"...."""

v.v'""-,..,. x 1 Btu x 1

=:::;..:.;:.....:..:::.-

The decay heat from "A" at 6 hrs after shutdown is 0.7878 x 109 Btu.

Therefore, the decay heat at 6 hrs. from fisson product heat alone is:

x 109 - 0.00359(0.7878 x 109) 0.7849 x 109 Btu it is conservatively assumed that the reactor trips at 102%

reactor thermal power for event, the fission product decay heat at 6 hrs after shutdown becomes:

0.7849 X 109 Volume of water required for heat removal is determined by:

Where, Llh== hg(1155 psia) - hI (11

!-lot"OI'''' 1)

== 11

1109 Btu/lb (Reference Calculating the required volume of condensate water for the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months holding period results in:

W(2

= (0.3630 x 109 Btu 11109 Btu/lb] (0.016165 fe/lb) (1gaI/O.1 W(2 hrs) ::: 39515 gallons Calculating required volume of condensate for the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months holding period results in:

hrs) =[(0.8006 x 109 Btu -

x 109 Btu) 111 Btu/lb] (0.016165 fts/lb) (1 gall 0.1337 fts)

W(4 hrs} ::: 41,108 gallons BM-95-0961-001 Calculations.docx

Southern Nuclear Design Calculations Calculation Number:

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~~~~-1~~~~

80123

Determine required volume for removal of Heat in ReS at (hot) of An uncertainty of 6°F on the initial reactor coolant temperature is conservatively

Thus, sensible heat calculation is based on a temperature of 577.2 of + 6°F== 583.2 of for the thermal capacity of the system metal and the reactor coolant fluid enthalpy change from 583.2 of to equation used to calculate the heat is based upon of mass and energy:

dU::;; m xCp x

+ llh x M where; dU ::;; sensible load from ReS temperature of m::;; mass of metal, Ibm

<= 5.0 x 1061bs (from Reference 2)

Cp ::;; "'.....'"1 heat of metal, 0.11 Btu/OF-Ibm (from Reference 4) llh== enthalpy change of reactor coolant, Btu/lb of; hf1== 593.02 BtU/lb; Vii 0.022918 fe/lb 350°F; hf2== 321.80 Btu/lb; Vl2== 0.01799 ft3/1b M :::: total reactor coolant mass, Ib

== V lVI, V== total reactor coolant volume, fe

== 9,723 ft3 VI== specific volume of reactor coolant, where Vii = Vf2 for ('r\\r'<::"'r\\l~

== 0.018 fe/lb; M :::: 9,723 ft3IO.018 fe/lb 540,167

Thus, dU :::: m x cp x

+ Ah x M

5.0 X 106 x 0.11 Btu/OF-Ibm x

- 350°F) + (593.02 Btu/lb -

.80 Btu/lb) x 540,1 Ibs.

dU:::: 2.7476 X 108 Btus W (sensible ht.)== g;zmUL~JllidlS..Q&1.§j~lf!l!m1m 1109 Btu/Ibm x 0.1 BM-95-0961*001 Calculations.docx

Southern Nuclear Design Calculations Plant:

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BM-95-0961-001 Rep Heat Determine required volume for removal of the heat added to the by coolant pumps.

For this event, normal cooldown, the heat added to the ReS is based on 1 Rep in operation for the duration of the event, 6 hrs. plus 10MWt net Rep heat added and assumed to decay over

) hr. after shutdown.

Per Reference 22, the heat added to ReS per pump is assumed at 5 MWt and the net heat input added for all three(3) is 10 MWt 5 MWt (1 Rep), the eST volume required per hour 5 MWt::: 5 X 106 watts and 1 Btulhr:::: 0.293 watts, therefore, 5 MWt ::: 5 x 10 6 watts x (1 Btu/hr / 0.293 watts) ::: 1.7065 x 107 Btu/hr.

W/hr ( 1 Rep):::

1.7065 x 107 Btu/hr x 0.016165 ft3/1b ;

1109 Btullb x 0.1337 ft3/gal where 1109 Btu/lb is enthalpy sink of the AFW, from 110°F to 11 maximum of the S/G secondary For 10 MWt the volume required hour is:

10 MWt::::3.41 x107 Btu/hr WIhr (10 MWt net heat added):::: 3.4129 x 107 Btulhr x 0.016165 te/lb ;

1109 Btu/lb x 0.1337 ft3/gal.

W/hr (10 MWt net heat added) :::: 3721 gal/hr.

Therefore, for this normal cooldown the volume required for removal of RCP heat is; W(RCP

(6 hr. x 1860 gal/hr) + ( 1 hr x gallhr)

W (Rep heat)== 14881 gallons Thus far, the volume required by the normal cooldown is 132,119 gallons, now consider vortex prevention, AFW pumping capacity and CST potential inventory losses for conservatism.

the CST volume required based on the minimum submergence water level required in to prevent vortexing at the AFW pump's suction inlet.

Reference the minimum submergence BM*95-QS61*001 Calculations.docx

Southern Nuclear Design Calculations Sheet:

10 of level required in the based on the operation of two(2) MDAFW pumps or the TDAFW pumps shall or equal 9.78 inches from the bottom of the From the internal dimensions of tank per Reference 23, the volume required Volume Req'd (gallons)==

Area (1t2) x Min.

(ft.) x ~==--:?-"==

Tank Area (ft.2)== TT radius2, where the radius is equal to 23 ft.

Tank Area (ft.2)== TT (23)2== 1661.9 ft.2, use 1662 ft2 Min. Submergence(ft.) ::::: 9.78 inches x (1 ft.l12inches) :::. 0.815 ft.

Thus, Volume Req'd (gallons) for Vortex PfIR<\\I43tlflt"l 1662 fe x 0.815 ft. x 1 0,132 gallons

"'-'-'~"""""'=.:..;'""'-

Pumping Capacity and Inventory Loss During normal plant cooldown, operating of one MDAFW pump will permit a maximum initial cooldown rate of 100°F/Hr. Each of the MDAFW pump is to supply the steam generators with 100 percent of the required feedwater flow for a normal cool down of the reactor coolant system (References 1 and Therefore, one MDAFW pump is sufficient for a normal cooling operation with a cooldown rate of 50 assumed calculation.

approach for calculation, however, it is modeled for all three AFW pumps (the TDAFW and two MDAFW pumps, each at the design flow rate of 700 and 350 gpm, respectively) to operate for the first 30 minutes before the TDAFW and one MDAFW pumps are For normal plant cooldown, the AFWS is placed under manual control to supply feedwater to steam generators for removal of decay and sensible heat from the reactor system. The TDAFW pump is designed to manually or automatically initiated to rated capacity and within 1 minute from starting at rest at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months independent any ac power (Reference 1). Operator action to secure the TDAFW and one MDAFW pump within 30 minutes will be adequate for this calculation purpose.

It is to check that this operational mode will deliver sufficient water during the period (6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ) to meet the volume of 1 19 gallons above. The amount of water pumps can deliver during the 6-hour period will (700 gpm + 2 x 350 gpm) x 0.5 + 350 gpm x 5.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s:::::: 157,500 gallons.

Therefore, the pumps will cover required water volume during the 6-hour period.

The volume of water out from a break in the pump recirculation line will calculated with an assumption that the ruptured minimum flow recirculation will be isolated within minutes. Three recirculation lines of the pumps form one 6-inch line to the It is even though single 6-inch return line would rupture at a location near the all the three pump recirculation lines would be isolated. The MDAFW pumps will operated with the minimum flow lines isolated during the remaining time 5.5-hour period and will not the pump performance for this operation mode.

BM*95*0961-Q01 Calculations.docx

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BM-95-0961-001 Since valves for the recirculation lines can be closed manually inside the plant, 30-minute span for the action is considered sufficient (Reference Section B.3.7.6).

9 and 10, the maximum recirculation flow for the TOAFW pumps is 100 gpm, and 50 gpm for MOAFW pump.

recirculation flow are slightly higher than calculated to conservatively accommodate the slight in frictional loss due to a line break.

Thus, the maximum volume of water will lost during the 30-minute span from recirculation line failure while all three AFW pumps are in operation is:

(100 + 50 + 50)gpm x hour =

Since the nozzle of AFW pump recirculation is located at 19 above the which is well above the height (1 feet, see below calculation) of the protected 164,832 gallon volume, or even above protected height of the tank (16') (Reference 11), a possibility of water coming out from the through the ruptured recirculation line is not considered.

From 14, 15, 16, 17 and 18, the four flow instrumentation lines branch out from two AFW pump suction lines at EI. 150 ft. location. Since the locations of the branch-out are in the pipe trench, for a conservative calculation purpose, the break point of the instrumentation is assumed to happen at location above the ground level 1

where the instrumentation are to missile impact. This is the same elevation as the pump suction nozzle at the instrument tubing is 3/8" with 17). In order to calculate the flow rate at the rupture assume the in the 8" pump suction and the instrument tubing are Ignored. This will give a conservative result for the flow rate. Since the lower 164,832 gallon volume of the tank shall be reserved for handling decay heat and cooldown, the height of this water volume in tank Tank bottom area: TI r2 TI (23ft)2 = 1662 (Reference 11)

Height of volume (164,832

= (164832 17.48gals/ft~ /1 ft2 =13.25 (equivalent to a pressure of psi). From 6,

2-9, the water flow from the break point is calculated by extrapolation. The break size of the tubing (0.245" 10) is approximately equivalent to 1/4". The discharges of 1/4" nozzle at 10 and 15 psi are 5.91 and 7.24 gpm, respectively (Reference 6).

Taking a middle pOint of the fluid at the instrument break point, or 2.9 psi, and ignoring all the and effect of the AFW pump suction conservatism, then the flow at the break points is calculated as:

5.91 gpm - {[(7.24 - 5.91 )/(15-1 0)] x (10-2.9)}

5.91 - 1.88 4.03 gpm per line Total outflow for four instrumentation lines: 4.03 x 4 lines 16.1 gpm If we consider that instrumentation tubing will not isolated during 6-hour cooldown period, than the total volume lost from the ruptured instrument for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is 16.1 x 6 x 60 = 5803 gallons.

total volume inventory lost from all the ruptured lines assuming the line ruptures were occurred at time::: 0 sec. of the cooldown mode: 6,000 + 5,803 :::: 11,803 gallons BM-95*0961-001 Calculations.docx

Southern Nuclear Design Calculations In addition to the conservative scenario assumed in calculation, result is even more conservative for the following aspects.

First, operating aU pumps at the beginning of the normal plant cooldown is a highly conservative scenario. Only one or two pumps would be used for this purpose, which would make the water lost from the ruptured line much less than the calculated The water volume lost from the one 6-inch recirculation line was calculated by combining all the recirculation flows (200 gpm) from each AFW pumps.

Secondly, the volume of water required for decay and sensible heat removal calculated based on the enthalpy water at 1155 psia. The rate of decay and heat removal at lower pressures will be significantly higher (enthalpy increase from 1187 Btu/lb at 1155 psia to 1204 Btu/lb at 135 psia) and the calculation does not take any credit for the increase in enthalpy lower pressures and, thus, higher heat removal capacity Attachment A and Assumption Total CST Volume Required for Normal Cooldown is:

39575(decay ht. 2 hrs) + 47,708(decay ht. 4 hrs) + 29,955(sensible ht.) + 14881(RCP heat) +

10, 132(vortex prevention} + 11,803(inventory loss)== ~~~~~!2 This amount which consrvatively assumes a minimum submergence volume to prevent a vortex and the volume lost due to the failure of the AFW reciculation line and the instrumentation lines is still within the 164,832 gallons of the CST protected water volume.

c.

Determine required CST volume based on holding reactor hot standby for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and cooldown in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 350°F at 50°F/hr where RHR may be utilized for cooling.

With power unavailable, the RCPS will not in operation through the duration of this removal of RCS will from circulation where the cooldown rate will at 50 °Flhr. Thus, the duration of the event is set at 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at hot standby and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to cooldown to Also, it is asssumed that FNP Operations will AFW to the faulted steam generator within 30 minutes.

Decay Heat Adjust decay load from Appendix "A" which represents MWt (100% power) plus 10 MWt pump to values that only decay heat due to fisson products decay heat.

The portion of decay heat results that is due to pump heat is: 10 MWt /2785 MWt 0.00359 BM-95-0961-001 CalculaUons.docx

Southern Nuclear Calculations The decay heat from App. "A" at 2 hrs after shutdown is 0.35713 x 109 Therefore, decay heat at 2 hrs. after shutdown from fisson products alone is:

0.35713 x 1 09

~ 0.00359(0.35713 x 109) :::: 0.35584 x 1 Btu it is conservatively assumed that the reactor trips at 102% of rated reactor thermal power for event, the fission product decay at 2 hrs.

shutdown becomes:

0.35584 x 109 Btu x 1.02 ::: =:::~~~-=:.::::

The from App. "A" at 6 hrs shutdown is 0.7878 x 1 Btu.

Therefore, the decay heat at 6 hrs. from fisson product heat alone x 109 - 0.00359(0.7878 x 109 ) ::::: 0.7849 x 109 Since it is conservatively assumed that reactor trips at 102% of reactor thermal power for this the fission product decay heat at 6 hrs after shutdown becomes:

0.7849 xi 09 Btu x 1.02 Volume of water required for removal is determined by:

Where, (Reference 1)

~h ::: 1187 -78== 11 09 Btu/lb (Reference 5)

Calculating required volume of

..... nru:mCQT*O water for the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months holding in:

W(2 hrs)== [0.3630 x 109 Btu 111 Btu/lb] (0.016165 ft3/1b) (1gal 10.1337ft3)

Calculating the required volume of condensate water the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months holding period ( 6 hrs.

2 hrs.)

results in:

BM*95-0961-001 Calculalions.docx

Southern Nuclear Design Calculations Calculation Number:

14 of 23 W(4 hrs) =[(0.8006 x 1 Btu* 0.3630 x 109 Btu) /1109 Btu/lb] (0.0161 ft3l1b) (1 gal/ 0.1337 fe)

Determine required eST volume for removal of Sensible Heat in the ReS at Tavg (hot) 577.2°F. An uncertainty of 6°F on the initial reactor average coolant temperature is conservatively assumed. Thus, sensible heat calculation is on a ReS temperature of

+

=

OF the thermal capacity of the metal and the reactor coolant fluid enthalpy change from 583.2 to The equation used to calculate the sensible heat load is based upon the conservation of mass and energy:

dU = m x cp x

+ Llh x M where; dU sensible heat load from ReS temperature of 583.2 OF to 350°F, Btu m

mass of ReS metal, Ibm x 1061bs (from Reference 2) cp = specific heat of metal, 0.11 Btu/OF-Ibm (from

4)

Llh ::::: enthalpy change of reactor coolant, Btullb hf1 =

Btu/lb; Vll = 0.022918 fe/lb

==

.80 Btu/lb; Vf2 ::::.: 0.01799 ft3/1b M== total reactor coolant mass, Ib

.: V I v,, where V::: total reactor coolant volume, fe

==

fe v, =: specific volume of reactor coolant, where VI1 ~ V'2 for conservatism.

=: 0.018 ff/lb; M::: 9,723 fe10.018 te/lb== 540,1671bs

Thus, dU =: m x x

+ Llh x M 5.0 x 1 Ibs. x 0.11 BturF*lbm x (583.2°F. 350"F) + (593.02 Btu/lb -

.80 Btullb) x 540,167 Ibs.

BM*95*0961*001 Calculations.docx

Southern Nuclear Design Calculations Plant:

Calculation Number:

Sheet:

Nuclear Plant Units 1 & 2 BM-95-0961-001 15 of 23 W (sensible ht.) =2.7476 x 108 Btu x 0.016165 fe/Ibm 1109 Btu/Ibm x 0.1337 ft3/gal.

W (sensible ht.) = 29,955 gallons required for sensible heat load RCP Heat with LOSP Determine CST volume required for removal of the RCP heat added to the RCS.

This RCP heat is based on net heat input of 10 MWt from the full power operation of the unit prior to the event per WCAP-15097. The FSAR Section 15.4.2.1 does not assume a conservatively large RC P heat of 15MWt. The initial net heat input of 10MWt is assumed to decay over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and no operation of the RCPs is condsidered since LOSP is assummed.

Determine number of gallons per hour required remove 10MWt pump heat is:

W (gal/hr.) =(3.41297 x 107 Btu/hr / 1109 Btu/lb) x 0.16165 fe/Ibm x gall.1337ft3 W =3721 gal/hr to remove 10MWt pump heat For the initial net RCP heat input of 1 OMWt that is assumed to decay over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from the start of the event the CST volume required is: 3721 gallons.

Therefore, the total CST volume required to remove the initial heat: 3721 gallons Unusable Volume Unusable Volume in CST is equivalent to the 4 inches (0.33 ft) of CST volume below the pumps' suction nozzles since no vortex prevention is required while bringing the unit to hot shutdown, RCS at 350°F. That is, no attached lines to the CST are assumed to fail allowing air to enter the tank below the diaphragm during this event due to the single failure criteria.

Unusable Volume (gallons) =Tank Area (ft2) x 0.33 ft. x 7.48 gallons/ft.3 Tank Area (ft.2) =TT radius2, where the radius is equal to 23 ft.

Tank Area (ft. 2) =TT (23)2 = 1661.9 ft.2, use 1662 tf Thus, Unusable Volume (gallons) = 1662 fe x 0.33 ft. x 7.48 gal/ftl = 4102 gal BM-95-0961-001 Calculallons.docx

Southern Nuclear Design Calculations inventory loss from a MFWLB based on new Proto-Flo runs with as-built AFW orifice Calculation 40.02, inventory loss of CST volume due a MFWLB assuming break is isolated in 30 mins is...:.....:..l......,.,;;:;.....;:J=.;::;.;..;..;;:;..

However, a 10% margin is added to this value for uncertainity until this value is documented and verified in a new version of the calculation 40.02. Thus, the new version of calc. 40.02 will an input this this calculation.

Including the 10"10 margin: 14,898 + 1490 :::: 16,388 gallons Results The total volume of the required to bring the to for a MFWLB w/LOSP This amount is within the 164,832 gallons of the CST protected water volume.

Verify the CST protected water volume capacity based on the Technical Specification Basis B.3.7.6 that "The OPERABILITY the CST is on having sufficient water to maintain the RCS in MODE 3 for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharge to the atmosphere concurrent with a total loss of offsite power.

Adjust decay load from Appendix "A" which represents MWt (100% power) plus 10 MWt pump heat to values that represents only decay heat due to fisson products decay heat.

heat from App. "A" at 9 after shutdown is 0.1 x 1010 Btu which includes 10 MWt pump heat.

The portion of decay heat results that is due to pump heat is: 10 MWt I 2785 MWt ::::: 0.00359 Therefore, the decay at 9 shutdown from fisson products ( minus pump is:

0.1055 X 1010.0.00359(0.1 BM-95-0961-001 Calculations.docx

Southern Nuclear Design Calculations Since it is conservatively assumed that the reactor trips at 102% of rated reactor thermal power MWt) for this event, the fission product decay heat at 9 hrs after shutdown becomes:

0.10512 x 1OW Btus x 1.02 Therefore, the Volume Required for Decay W(9hrs.)= 0.10722 x 1010Btu (0.016165ft3/Ibm)(gaI/0.1337 fe) 1109 Btullbm RCP Net Heat

&I 9.2.6.3, event is concurent with no RCPs are in operation; however, the net heat input of 10 MWt due to RCPs at beginning of event exists in the RCS and it is assumed this heat decays over a one(1) hour period. No RCP heat is added during 9 hr event since a LOSP is assumed with this event.

10 MWt=

297 x 107 Btu/hr (based on 0.293 watts 1 Btu/hr)

Therefore, CST volume required due to 10 MWt RCP net heat input at beginning of the event and assumed to decay in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months W(10MWt decayed over 1 hr.)==.::::.:.....:...:.::::.;=....;:..:.....:..;;::;....:::.=.:.:.:-.\\_

6165ft3I1bm}(gaI/0.1 1109 Btu/Ibm Unusable Volume

&I Unsable Volume in CST is equivlent to the 4 inches (0.33 ft) of CST volume below the pumps' since no vortex prevention is required while maintaining the RCS in MODE 3 for 9 That no attached lines to the CST is assumed to fail allowing to enter below the diaphragm.

Unusable Volume (gallons)

Tank Area (fe) x 0.33 ft. x.!...:....:.=...::I=::.:;..;r Tank Area (ft,2) :::: IT radius2, where the radius is to 23 Tank Area (ft.2)::: IT (23)2 ::::: 1661.9 ft.2, use 1662 fe Thus, BM*95*0961*001 Calculations.docx

Southern Nuclear Design Calculations Unusable Volume (gallons):::: 1662 x 0.33 ft. x 7.48 gallons ::: 4102 gallons ft.3 116,893 gallons + 3721 gallons + 4102 gallons::::..:..=....:.:t.:...:...::.....;=:..=;::;.

This is volume water required for reactor shutdown does not include the water for sensible removal the temperature will be maintained at the hot standby condition throughout this duration. A line break that would result in CST inventory loss by a tornado or a seismic is not of the mode standby condition with a off-site power.

amount within the 164,832 gallons of the CST protected water volume.

E.

loss of Normal Feedwater w/o lOSP Adjust decay load from "A" which represents MWt (100% power) plus 10 MWt pump heat to values that represents only decay heat due to fisson products heat.

decay from App. "An at 9 hrs after shutdown is 0.1 x 101o Btu which includes 10 MWt pump heat.

The portion of heat results that is due to pump heat 10 MWt 12785 MWt Therefore, the decay at 9 after shutdown from fisson products (

pump heat) is:

0.1055 x 1010 - 0.00359(0.1 x 1010) ::: 0.10512 x 101o Btu Since it is conservatively assumed the reactor trips at 102% of rated reactor thermal power (2775 MWt) for this event, fission product decay heat at 9 hrs after shutdown becomes:

0.10512x10 10 x1.02= ""-'-!~=.::.:....:.:::.--=::.;:::.

Therefore, the Volume Required for Decay Heat is:

W(9hrs.) = ~.:....:..;=...::::::::...:..:--'-"'--=""'-\\

6165ft3I1bm)(gaI/0.1337 1109 Btu/Ibm BM*95-0961*Q01 Calculalions.docx

Southern Nuclear Design Calculations No sensible heat is included since unit at hot standby conditions through-out duration of event.

RCP Heat w/o LOSP Determine CST volume required for removal the heat added to the RCS.

This RCP heat is based on net input of 15 MWt perWCAP-1 and operation of all from Tavg(full power) to 350°F at a cooldown rate of 50°F/hr. The WCAP assumes a conservatively large RCP of 15MWt.

initial net heat input of 15 MWt is assumed to decay over 1 Per this WCAP, all three(3) RCPs at the initiation of event 10 mins and) for the duration of event; 9 hrs. in hot standby.

15 MWt pump input:::: 5.119 x 107 Btu/hr.

Determine number of gallons per hour required to remove 15MWt pump heat W (gal/hr.) :::

119 x 107 Btu/hr 11109 x 0.0161 fe/Ibm x gall 0.1 W ::.:: 5580 gal/hr to remove 15MWt pump heat. Thus, assumming 1 hr to decay 15 MWt, the net input yields:

5581 gallons Per FSAR 15.2.8.2.1.A, Reps nn,;>n:l'rc for 10 mins at start of event:

5581 gals/hr. x 1 hr./ 60mins x 10 min.

Thus, for the remaining duration of the event which 9 hrs 10 mins, the CST volume required to remove heat input of one (1) RCPs operating 1 Rep heat input:::::; 5 MWt =1.7065 x 107 Btu/hr.

W (gal/hr) = (1.7065 x 107 Btu/hr 11109 Btu/lb) x 0.016165 ft3/lbm x gal./ 0.1 fe W (gal/hr) 1860 gallhr Now, timing

= 9 hrs.

(10min x 1 hr/60 min) 8.83 hr.

BM-95-0961-001 Calculations. doc>:

Southern Nuclear Design Calculations t:

Ie Nuclear Plant Units 1 & 2

..""***nn Number:

BM-95-0961-001 Sheet:

20 of 23 Therefore, volume required for timing remaining during event is:

Volume:::: 1860 gal/hr x 8.83 hr. =: 16,430 gallons CST volume

+ 930 + 16,430 for RCP heat ad(:ted LNFWevent FSAR Section 1 during a Normal Feedwater the pressurizer proportional no~n""lrQ are assumed operable. The total capacity of the heaters is 1.4 MWt. The ron,rac,ontc! an addition to energy which must removed by the AFW Therefore, determine volume required removal of this <.>"""".\\1 during the event duration hours in Mode 3, steaming to atmosphere.

It Loss of Normal Feedwater Pressurizer in Btu/hr.

1.4 MWt =: 4.7781 xi (based on watts =: 1 W/hr (pzr Htrs.) =:

where 1109 Btu/lb is enthalpy heat sink the AFW, from 11 to 1155 psia, maximum backpressure secondary Therefore, for LONF event, the volume required for H.,nnn,,'-l of Pressurizer........,n.... '

input to the ReS:

W (pzr Htrs.)

(9 hr. x 521 gal/hr)

Unusable Volume BM-95-0961-001 Calculations.docx

Southern Nuclear Design Calculations Calculation Number:

Sheet:

BM~95-0961-001 21

Unusable Volume in CST is equivlent to the 4 inches ft) of CST volume below the pumps' suction nozzles since no vortex prevention is required while bring the unit to hot shutdown, RCS at 350°F. That is, no attached lines to the that are to allowing air to enter the tank below the diaphragm during this event due to the single failure criteria.

Unusable Volume (gallons)

Tank Area (ft2) x 0.33 ft. x 7.48 gallons/ft.3 Tank Area (ft.2) ::::: IT radius2, where the radius is equal to 23 ft.

Area (ft.2) ::::: IT

1

.9 ft.2, use 1662 Unusable Volume (gallons) :::::: 1662 ft2 X 0.33 ft. x 7.48 galm3

..

....

..

=-=.:.

No loss or inventory is for this event total volume of the CST required to bring the to 350°F for LNFW wlo LOSP is:

116,893 + 22941 + 4689 + 4102 ::::::

~=:.::::..:::~=

This amount within the ~...:.==~=;.::.:.;::::; of the CST protected water volume.

V.

RESULTS I CONCLUSIONS The quanitity of water required in the protected portion of the to cooldown the reactor within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to a point at which the plant can be transitioned to RHR system cooling is 132,119 gallons which of decay, and heat during a Normal Cooldown event.

However, in this analYSis for the Normal Cooldown event, several conservative assumptions were made in addition to the decay, and loads considered in determing the minimum volume required for the Normal Cooldown event These conservative assumptions included volume losses due to missile rupture unprotected portion of the pump's recirculation lines and the tank's instrumentation and a minimum submergence in the to prevent a vortex formation.

assumptions are conservative a tornado event, the failure mechanism, is not required to be assumed concurrent with a Normal Cooldown event. Thus, the conservative amount of water needed for this event is "!":;!::!"c:!~~~!.!2.'

This analysis also shows based on the CST volume for Main Feedwater Break with Loss-of-Offsite Power event, adequate margin is available to accommodate a loss of CST inventory due BM*95*0961 "001 Calcula\\ions.docx

Southern Nuclear Design Calculations Calculation Number:

Sheet:

BM-95-0961-001 22 of 23 to the MFWLB in addition to cooldown the RCS within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to a point at which the plant can be transitioned to RHR system cooling. The amount of water needed for this MFWLB event is 141,449 gallons.

The quantity of water to maintain the RCS at hot standby conditions for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharge to the atmosphere concurrent with a totalloss-of-offsite power, as required for the Technical Specification Bases for Operability, is calculated to be 124,716 gallons.

This analysis also shows that an adequate volume of water is available in the missile protected portion of the CST to maintain the RCS at hot standby conditions for 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months with steam discharging to the atmosphere for the Loss of Normal Feedwater without Loss-of-Offsite Power event. The amount of water needed for this LONF event is 148,625 gallons.

All of these required water volumes are within the maximum protected water amount of 164,832 gallons for the CST and the Normal Cooldown has been determined to be the most limiting event for the sizing of the CST volume.

Therefore, the CST capacity is adequate to remove the reactor decay heat from 102% RTP, RCS sensible heat, and RCP heat for various conditions described above which include the water loss from rupture of the unprotected lines due to potential missile impact or a seismic event, inventory loss due to a main steam line break and AFW pump suction vortex prevention.

BM*95-0961*001 Calculations.docx

Southern Nuclear Design Calculations Calculation Number:

Sheet:

BM-95-0961-001 23 of 23 VI.

REFERENCES

1.

Auxiliary Feedwater Functional System Description (FSD), A-181 01 0, Ver. 22

2.

Calculation 1.10, Rev. 0, Condensate Storgage, 3/10172 and Engineering Judgement M1.10 R/01

3.

"Deleted"

4.

Technical Specification, Unit 1 - Amendment 188, Unit 2 -Amendment 183

5.

Mechanical Engineering Review Manual, 8th Edition.

6.

Cameron Hydraulic Data, 16th Edition

7.

"Deleted"

8.

"Deleted"

9.

Calculation 38.04, Revision 3, Verification of AFW flow Bases - Unit 2

10.

Calculation 40.02, Revsion 3, Verification of AFW flow Bases - Unit 1

11.

U-161693, Version 2.0, and U-213481, Version 3.0 - CST General Plan

12.

"Deleted"

13.

SCS Calculation SM-95-0721-005, Revision 1 - Design Basis Temperature Site/Condensate Storage Tank/Refueling Water Storage Tank.

14.

Pump Suction Piping Isometric Drawings D-514547, Rev.O and D-514548, Rev. O.

15.

MDAFW Pump Suction Piping, D-518847, Sheets 2, Rev.O

16.

TDAFW Pump Suction Piping, D-518847, Sheet 1, Rev. 0

17.

AFW Suction Line Flow Instrument Drawings, A-175856, Rev. 2 and A-205856, Rev. 3

18.

AFW System P&ID, D-175007, Rev. 31; 0-205007, Rev. 25

19.

"Deleted"

20.

"Deleted"

21.

"Deleted"

22.

WCAP-15097, Revision 1: FNP Units 1 and 2 Replacements Steam Generator Program NSSS Engineering Report Book 1, March 2001.

23.

U-161703B, Ver. 0.3; U-161694C, Ver. 0.4; U-213481 Ver.1.0 - CST Internal Dimensions

24.

SM-SNC335993-001, Version 2.0 - CST AFW Pump Suction - Submergence Analysis

25.

RER SNC419117, Seq. 2 - "CST AI for Enhanced ACD for NRC CDBI NCVs 2011010-01 & 02."

APPENDIX A Decay heat model was based on an operating power of 2785 MWth and computer code MAP-121, Version V01.

BM*95-0961 -001 Calculations.docx

Appel"!dix "':-" Sheet 1 of 18 APr80Dix, A) CAcc. il-,

FNP Units 1 & 2

".~ev*fS9' Calculation No. BM-9S-0961-001, Rev. 6

'1 'PAc" E>~"b-tM

'D.W. N'\\L:f..P*~\\'{

i2../12./C.Y)

~ dI/'#Pf!

TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(BTU/HR)

(BTU)

MAP-121 DECAY HEAT CALCULATION CODE, VERSION VOl:

NRC VERSION CALCULATES RESIDUAL DECAY HEAT BY EQUATIONS PRESENTED IN NRC BRANCH TECHNICAL POSITION ASB 9-2. REV.2 JULY 1981. CODE CALCULATES DECAY HEAT RESULTING FROM FISSION PRODUCT DECAY, FP,AND THE DECAY OF U-239 AND NP-239. THE TOTAL DECAY RATE, INCLUDING THE APPROPRIATE UNCERTAINTY FACTORS IS LABELED TOTAL. THE TOTAL HEAT RELEASED IS L~ELED INTEGRAL. RESULTS ARE ACCURATE ONLY UP TO 1.0E07 SEC.

fARLey utVIT5

~

~ 'Z OPERATING POWER

.95070E+10 BTU/HR

('2. 7'D5 MW+")

OUTPUT FILENAME C:DCPDK.PRN REACTOR OPERATING TIME = INFINITY MAXIMUM TIME

.10000E+08 SEC.

PRINTOUT OPTION 1

"A" Sheet 2 of 18 FNP Units 1 & 2 No. BM~95-09 TIME (SEC)

.OOOOOE+OO

.10000E+00

.20000E+00

.30000E+00

.40000E+00

.50000E+00

.60000E+00

.70000E+00

.80000E+00

.90000E+00

.10000E+01

.20000E+01

.30000E+01

.40000E+01

.50000E+01

.60000E+01

.70000E+01

.80000E+01

.90000E+01

.10000E+02

. 11000E+02

.12000E+02

.13000E+02

. 14000E+02

.15000E+02

.16000E+02

.170

.18000E+02

.19000E+02

.20000E+02

.21000E+02 Rev. 6 FP

.79850E+09

.78635E+09

.77540E+09

.76550E+09

.75649E+09

.748 09

.74074E+09

.73381E+09 OE+09

.72147E+09

.71594E+09

. 67575E+09

. 65043E+09 09

.61783E+09 60590E+09

. 59553E+09

.58624E+09

.57774E+09

.56987E+09

. 56251E+09

.55560E+09

.54909E+09

. 54295E+09

.53713E+09

.53161E+09

.52639E+09

.52142E+09

.51671E+09

.51222E+09

.50795E+09 U-239

(

.15173E+08

.15172E+08

. 15172E+08

.15171E+08

.15170E+08

.15169E+08

.15168E+08

.15167E+08

.15166E+08

.1 66E+08

.15158E+08

.15151E+08

.15143E+08

.15136E+08

.15129E+08

.1 21E+08

. 15114E+08

.15106E+08

.15099E+08

.15091E+08

.15084E+08

.15077E+08

.15069E+08

.150

.15054E+08

.15047E+08

.15040E+08

.15032E+08

.15025E+08

.15018E+08 NP-239

(

.14441E+08

.14441£+08

. 14441E+08

.14441E+08

.1444 8

.14441E+08

.14441E+08 14441E+08

.14441E+08

.1444 8

U239+NP239 (BTU/HR)

.29614E+08

.29613E+08

.2961

.29611E+08

.29610E+08

.29609E+08

.29608E+08

.29607E+08

.29599E+08

.29592E+08

.29585E+08

.29577E+08

.29570E+08

.29562E+08

.2 08

.29547E+08

.29540E+08

.29533E+08

.29525E+08

.29518E+08

.29510E+08

.2 08

.29496E+08

.29488E+08

.29481E+08

.29473E+08

.29466E+08

.29459E+08 TOTAL

(

10 81596E+09

.80502E+09

.7

.78610E+09

.77788E+09

.77035E+09

.76342E+09

.75701E+09

.75107E+09

.74555E+09

.70535E+09

.68002E+09

.66174E+09

.64741E+09

.6354

. 62509E+09

.61

.60729E+09

.59941E+09

.59204E+09

.58513E+09

.57861E+09

.57246E+09 63E+09

.56111E+09

.55587E+09

.55090E+09

.54618E+09

.54169E+09

.53741E+09 INTEGRAL

.OOOOOE+OO

.14337E+06

.16589E+06

.18811E+06

.21007E+06

.23180E+06

.25330E+06

.27460E+06

.29572E+06

.31666E+06

.33745E+06

.53896E+06

.73138E+06

.91773E+06

.10996E+07

.12777E+07

.14528E+07

.16252E+07

.17950E+07

.19626E+07

.21281E+07

.22916E+07

.24532E+07

.26131E+07

.27713E+07

.29279E+07

.30831E+07

.32368E+07

.33892E+07

.35403E+07

.36901E+07

Sheet 3 of 18 FNP Units 1 &2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(BTU/HR)

(BTU)

.22000E+02

.50389E+09

.15010E+08

.14441E+08

.29451E+08

.53334E+09

.38389E+07

.23000E+02

.50002E+09

.15003E+08

.14441E+08

.29444E+08

.52946E+09

.39865E+07

.240

.4 09

.14 08

.14441E+08

.29437E+08

.52576E+09

.41330E+07

.25000E+02

.49279E+09

.14988E+08

.14441E+08

.29429E+08

.52222E+09

.42786E+07

.2

.48942E+09

.14981E+08

.14441E+08

.29422E+08

.51884E+09

.44232E+07

.27000E+02

.48619E+09

.14973E+08

.14441E+08

.29414E+08

.51560E+09

.45668E+07

.28000E+02

.48310E+09

.14966E+08

.14441E+08

.294 08

.51251E+09

.47096E+07

.29000E+02

.48014E+09

. 14959E+08

.14441E+08

.29400E+08

.50954E+09

.48516E+07

.30000E+02

.47730E+09

.14951E+08

.14441E+08

.50669E+09

.4 7E+07

.31 02

.47457E+09

.1494 8

.14441E+08

.29385E+08

.50396E+09

.51331E+07

.32000E+02

.47195E+09

.14937E+08

.14441E+08

.29378E+08

.50133E+09

.52727E+07

.33000E+02

.46944E+09

.14929E+08

.14441E+08

.29370E+08

.49881E+09

.54116E+07

.34000E+02

.46701E+09

.14922E+08

.14441E+08

.29363E+08

.49637E+09

.55498E+07

. 35000E+02

.464

.14915E+08

.14441E+08

.29356E+08

.49403E+09

.56874E+07

.36000E+02

.46242E+09

.14907E+08

.14441E+08

.29348E+08

.49177E+09

.58243E+07

. 37000E+02

.46024E+09

.14900E+08

.14441E+08

. 29341EoI-08

.48958E+09

.59606E+07

. 38000E+02

.4581

.14893E+08

.14441E+08

.2 08

.48747E+09

.60963E+07

. 39000E+02

.45610E+09

.14885E+08

.14441E+08

.29327E+08

.48543E+09

.62314E+07

.40000E+02

.45413E+09

.14878E+08

.14441E+08

.29319E+08

.48345E+09

. 63660E+07 41000E+02

.45222E+09

.14871E+08

.14441E+08

.29312E+08

.48154E+09

. 65000E+07

. 42000E+02

.45037E+09

.14863E+08

.14441E+08

.29305E+08

.47968E+09

. 66335E+07

.4

.44857E+09

.14856E+08

.14441E+08

.29297E+08

.47787E+09

.67665E+07 44000E+02

.44683E+09

.14849E+08

.14441E+08

.29290E+08

.47612E+09

. 68990E+07

. 45000E+02

.44513E+09

.14842E+08

.14441E+08

.29283E+08

.47441E+09

.70310E+07

.46000E+02

.44347E+09

.14834E+08

.14441E+08

.29275E+08

.47275E+09

.71626E+07 47000E+02

.44186E+09

.1482 08

.14441E+08

.29268E+08

.47113E+09

.72937E+07

.48000E+02

.44029E+09

.14820E+08

.14441E+08

.29261E+08

.4

.74243E+07

. 49000E+02

.43876E+09

.14812E+08

.14441E+08

.29254E+08

.46801E+09

.75546E+07

.50000E+02

.43726E+09

.14805E+08

.14441E+08

.29246E+08

.466 9

.76844E+07

. 51000E+02

.43580E+09

.14798E+08

.14441E+08

.29239E+08

.46504E+09

.78137E+07

.434 09

.14791E+08

.14441E+08

.29232E+08

.46360E+09

.79427E+07

.53000E+02

. 43297E+09

.14783E+08

.14441E+08

.29225E+08

.46219E+09

.80713E+07

. 54000E+02

.43159E+09

.14776E+08

.14441E+08

.29217E+08

.46081E+09

.81995E+07

.4 09

.14769E+08

.14441E+08

.29210E+08

.45946E+09

.83273E+07

"A" Sh eet 4 of 18 FNP Units 1 & 2 Calculation No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(BTU/HR)

(

(BTU/HR)

(

. 56000E+02

.42893E+09

.14762E+08

.14441E+08

.29203E+08

.45813E+09

.84547E+07

. 57000E+02

.42763E+09

.14754E+08

.14441E+08

.29196E+08

.45683E+09

.85818E+07

.58000E+02

.42636E+09

.14747E+08

.14441E+08

.29188E+08

.4 09

.87085E+07

. 59000E+02

.42511E+09

.14740E+08

.14441E+08

.29181E+08

",45429E+09

.88349E+07

,60000E+02

.42388E+09

.14733E+08

.14441E+08

.29174E+08

.45306E+09

.89609E+07

. 61000E+02

.42268E+09

.14725E+08

.14441E+08

.29167E+08

.45184E+09

.90866E+07

.62000E+02

.42149E+09

.1471

.1444 08

.291

.45065E+09

.92120E+07

. 63000E+02

.42032E+09

.14711E+08

.14441

.29152E+08

.44947E+09

.93370E+07

. 64000E+02

.41916E+09

. 14704E+08

.14441E+08

.29145E+08

.44831E+09

.94617E+07

. 65000E+02

.418 09

.14

.14441E+08

.29138E+08

.44716E+09

.95860E+07

. 66000E+02

.41690E+09

.14 689E+08

.14441E+08

.29130E+08

.44603E+09

.97101E+07

.67000E+02

.41580E+09

.14682E+08

.14441E+08

.29123E+08

.44492E+09

.98338E+07

.68

.41470E+09

.14675E+08

.14441E+08

.29116E+08

.44382E+09

.99573E+07

.413 09

.146

.14441E+08 09E+08

.44273E+09

.10080E+08

.70000E+02

.41256E+09

.14661E+08

.14441E+08

.29102E+08

.44166E+09

.10203E+08

.71000E+02

.41151E+09

.14653E+08

.14441E+08

.29094E+08

.44060E+09

.10326E+08

.72000E+02

.4104 9

.14646E+08

.14441E+08

.29087E+08

.43955E+09

.10448E+08

.73

.40944E+09

.14639E+08

.14441E+08

.29080E+08

.43852E+09

.10570E+08

.74000E+02

.40842E+09

.14 632E+08

.14441E+08

.29073E+08

.43749E+09

.10692E+08

. 75000E+02

.40741E+09

. 14625E+08

.14441E+08

.29066E+08

.43648E+09

.10813E+08

.76000E+02

.40642E+09

.14617E+08

.14441E+

.2

.4 8E+09

.10934E+08

.77000E+02

.40543E+09

.14 610E+08

.14441E+08

.29051E+08

.43448E+09

.11055E+08

.78000E+02

.40446E+09

.14603E+08

.14441E+08

.29044E+08

.43350E+09

.11176E+08

.79000E+02

.40349E+09

.1459 08

.14 1E+08

.2 7E+08

.43253E+09

.11296E+08

.80000E+02

.40253E+09

.14589E+08

.14441E+08

.29030E+08

.43156E+09

. 11416E+08

.81000E+02

.40158E+09

. 14582E+08

.14441E+08

.29023E+08

.43061E+09

.11536E+08

. 82000E+02

.40064E+09

.14574E+08

.14441E+08

.29015E+08

.42966E+09

. 11655E+08

.83000E+02

.39971E+09

. 14567E+08

.14441E+08

.29008E+08

.42872E+09

.11774E+08

. 84000E+02

.39879E+09

.14560E+08

.14441E+08

.29001E+08

.42779E+09

.11893E+

.85000E+02

.39787E+09

.14

.14441E+08

.28994E+08

.42687E+09

.12012E+08

.8600

. 39697E+09

.14546E+08

.14441E+08

.28987E+08

.42595E+09

. 12130E+08

. 87000E+02

.39607E+09

.14539E+08

.14441E+08

.28980E+08

.42504E+09

.12249E+08

.88000E+02

.39517E+09

. 14532E+08

.14441E+08

.28973E+08

.42414E+09

.12366E+08

.89000E+02

.39429E+09

.14524E+08

.14441E+08

.28965E+08

.42325E+09

.12484E+08

(lA" Sheet 5 18 FNP Units 1 & 2 Calculation No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(BTU/HR)

{

(BTU/HR)

(

.90000E+02

.39341E+09

.14517E+08

.14441E+08

.28958E+08

.42236E+09

.12 08

. 91000E+02

.3

.14510E+08

.14441E+08

.28951E+08

.42149E+09

.12719E+08

.92000E+02

.39167E+09

. 14503E+08

.14441E+08

.28944E+08

.42061E+09

.12836E+08

.93000E+02

.39081E+09

. 14496E+08

.1444 8

,28937E+08

',41975E+09

.12953E+08 000E+02

.38996E+09

.14489E+08

.14441E+08

.28930E+08

.4188

.13069E+08

. 95000E+02

.38911E+09

. 14482E+08

.14441E+08

.28923E+08

.41803E+09

.13185E+08

.96000E+02

.38

.14475E+08

.14441E+08 916E+08

.41718E+09

.13301E+08

. 97000E+02

.38743E+09

.14467E+08

. 14441E+08

.28908E+08

.41634E+09

.1341 8

.98000E+02

.38660E+09

.14460E+08

.14441E+08

.28901E+08

.41551E+09

. 13533E+08

. 99000E+02

.38578E+09

. 14453E+08

.14441E+08

.28894E+08

.41468E+09

.13648E+08

.10000E+03

.38496E+09

.14446E+08

.14441E+08

.28887E+08

.41385E+09

. 13763E+08

. 11000E+03

.37708E+09

.14375E+08

.14441E+08

.28816E+08

.40590E+09

.14901E+08

. 12000E+03

.36968E+09

.14305E+08

.14441E+08

.28746E+08

.39843E+09

.16019E+08

. 1 03

.36272E+09

.14235E+08

.14441E+08

.28676E+08

. 39139E+09

. 17116E+08

. 14000E+03

.35614E+09

.14165E+08

.14441E+08

.28606E+08

.38475E+09

.18194E+08

.15000E+03

.34994E+09

.14096E+08

.14441E+08

.28537E+08

.37848E+09

.19254E+08

.16000E+03

.34408E+09

.14 E+08

.14441E+08

.28468E+08

.37255E+09

.20297E+08

.17000E+03

.33854E+09

.13958E+08

.14441E+08

.28399E+08

.3

.21324E+08

.18000E+03

.33329E+09

. 13890E+08

.14441E+08

.28330E+08

.36163E+09

.22336E+08

.19000E+03

.32833E+09

. 13822E+08

.14441E+08

.28262E+08 35660E+09

.23333E+08

.20000E+03

.323 09

.13754E+08

.14441E+08

.28195E+08

.35183E+09

.24317E+08

.21000E+03

.31919E+09

.13687E+08

.14441E+08

.28127E+08

.34732E+09

.25288E+08

.22000E+03

.31498E+09

.13620E+08

.14441E+08

.28060E+08

.34304E+09

.26247E+08

.23000E+03

.31099E+09

.1 08

.14441E+08

.27993E+08

.33898E+09 194E+08

.24000E+03

.30720E+09

.13486E+08

.14440E+08

.27927E+08

.33513E+09

.28130E+08

.25000E+03

.30361E+09

. 13420E+08

.14440E+08

.27861E+08

.33147E+09

.29056E+08

.26000E+03

.30021E+09

. 13355E+08

.14440E+08

.27795E+08

.32800E+09 08

.27000E+03

.29697E+09

. 13289E+08

.14440E+08

.27730E+08

.32470E+09

.30879E+08

.28000E+03

.29390E+09

. 13224E+08

.14440E+08

.27664E+08

.32156E+09

.31776E+08

.29000E+03

.29097£+09

.13159E+08

.14440E+08

.27600E+08

.318 09

.32665E+08

.30000E+03

.28820E+09

.13095E+08

.14440E+08

.27535E+08

.31573E+09

.33546E+08

.31000E+03

.28555E+09

. 13031E+08

.14440E+08

.27471E+08

.31302E+09

.34420E+08

.32000E+03

.2830

. 12967E+06

.14440E+08

.27407E+08

.31044E+09

.35286E+08

. 33000E+03

.28064E+09

.12904E+08

.14440E+08

.27343E+08

.30798E+09

.36145E+08

"A" Sheet 6 of 18 FNP Units 1 & 2 Calculation No. BM-95-0961-001. Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(BTU/HR)

(BTU/HRl

(

.34000E+03

.27835£+09

.12840E+08

.14440E+08

.27280E+08

.30564E+09

.36997E+08

. 35000E+03

.27618E+09

.12777E+08

.14440E+08

.27217E+08

.30339E+09

.37843E+08

. 36000E+03

.27410E+09

.12715E+08

.14440E+08

.27154E+08

.30125E+09

.38682E+08

. 37000E+03

.27211E+09

.12653£+08

.14440E+08 92E+08

.29920E+09

.39516E+08

.38000E+03

.27021E+09

.12591E+08

.14440E+08

.27030E+08

.29724E+09

.40345E+08 03

.26840E+09

.12529E+08

.14439E+08

.26968E+08

.29536E+09

.41168£+08

.40000E+03

.266 09

.12468E+08

.14439E+08

.26907E+08

.29357E+09

.41986E+08

.41000£+03

.26500E+09

.12406E+08

.14439E+08

.26846E+08

.29184E+09

.42799E+08

.42000E+03

.26340E+09

.12346E+08

.14439£+08

.26785E+08

.29019E+09

.43607E+08

.43000E+03

.261 9

.12285E+08

.14439E+08

.26724E+08

.28860E+09

.44411E+08

.44000E+03

.26040E+09

.12225E+08

.14439E+08

.26664E+08

.28707E+09

.45211E+08

.45000E+03

.2 99E+09

.12165E+08

.14439E+08

.26604E+08

.28560E+09

.46006E+08

.46000E+03

.25764E+09

.12106E+08

.14439E+08

.26544E+08

.28418E+09

.46797E+08

.47000E+03

.25633E+09

.1204 8

.14439E+08

.2648 08

.28282E+09

.47585E+08

.48000E+03

.25508E+09

. 11987E+08

.14439E+08

.26426E+08

.28150E+09

.48369E+08

.49000E+03

.25387E+09

. 11929E+08

.14438E+08

.26367E+08

.28023E+09

.49149E+08

.50000E+03 70E+09

. 11870E+08

. 14438E+08

.26309E+08

.27901E+09

.49926E+08

.51000E+03

.25157E+09

.11812E+08

.14438E+08

.26250£+08

. 27782E+09

.50699E+08

. 52000E+03

.2 8E+09

.11754E+08 14438E+08

.26192E+08

.27668E+09

.51469E+08

.53000E+03

.24943E+09

.11697E+08

.14438E+08

.261 08 09

.52236E+08

.54000E+03

.24841E+09

.11639E+08

.14438E+08

.26077E+08

.27449E+09

.53000E+08

. 55000E+03

.24743E+09

.11582E+08

.14438E+08

.26020E+08

.27345E+09

.53761E+08

. 56000E+03

.24647E+09

. 11526E+08

.14438E+08

.25963E+08

.27243E+09

.54519E+08 OE+03 554E+09

. 11469E+08

.14438E+OB

.25907E+

.27145E+09 75E+08

.58000E+03

.24464E+09

.11413E+08

.14437E+08

.25850E+08

.27049E+09

.56027E+08

. 59000E+03

.24377E+09

.11357E+08

.144

.25794E+08

.26956E+09

.56777E+08

.60000E+03

.24292E+09

. 11301E+08

.14437E+08

.257 08

.26865E+09

.57525E+08

. 61000E+03

.24209E+09

. 11246E+08

.14437E+08

.25683E+08

.26777E+09

.58270E+08

. 62000E+03

.24128E+09

.11191E+08

.14437E+08

.25628E+08

.26691E+09

.59013E+08

. 63000E+03

.24049E+09

.11136E+08

.14437E+08

.25573E+08

.26607E+09

.59753E+08

.64000E+03

.2397

.11 082E+

.14437E+08

.25518E+08

.2 9

.60491E+08

. 65000E+03

.23898E+09

. 11027E+08

.14437E+08

.25464E+08

.26444E+09

.61226E+08

. 66000E+03

.23825E+09

.10973E+08

.14436E+08

.25410E+08

.26366E+09

.61960E+08

.23753E+09

.1 08

.14436E+08

.25356E+08

.26289E+09

.62691E+08

"A" Sheet 7 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL

(

)

(

(BTU)

.68000E+03

.23683E+09

.10B66E+08

.14436E+08

.253

.26213E+09

.63420E+08 3

.23615E+09

.10813E+08

.14436E+08

.25249E+08

.26139E+09

.64148E+08

.70000E+03

.23547E+09

.10760E+08

. 14436E+08

.25196E+08

.26067E+09

.64873E+08 71000E+03

.23482E+09

.10707E+08

.14436E+08

.25143E+08

.25996E+09

. 65596E+08

.72000E+03

.23417E+09

.10655E+08

.14436E+08

.25090E+08

.25926E+09

. 66317E+08

.73000E+03

.23354E+09

.10603E+08

.14435E+08

.25038E+08

.25857E+09

.67036E+08

.74000£+03

.23291E+

.10551E+08

.14435E+08

.24 6E+08 90E+09

.67753E+08

.75000E+03

.23230E+09

.10499E+08

.14435E+08

.24934E+08

.25723E+09

.684

.76000E+03

.23170E+09

.10448E+08

.14435E+08

.24883E+08

.25658E+09

.69182E+08

.77000E+03

.23111E+09

.10396E+08

.14435E+08

.24831E+08

.25594E+09

.69894E+08

.78000E+03

.23052E+09

.10345E+08

. 14435E+08

.24780E+08

.25530E+09

.70604E+08

. 79000E+03

.22995E+09

.10295E+08

.14435E+08

.24729E+08

.25468E+09

.71313E+08

.80000E+03

.22938E+09

.10244E+08

.14434E+08

.24679E+08

.25406E+09

.72019E+08

.81000E+03

.22 3E+09

.1 94E+

.144

.24628E+08

.2534 09

.72724E+08

. 82000E+03

.22828E+09

.10144E+08

.14434E+08

.24578E+08

.25285E+09

.73427E+08

.83000E+03

.22773E+09

.10095E+08

.14434E+08

.24528E+08

.2522

.7412

.84000E+03

.22720E+09

.10045E+08

.14434E+08

.24479E+08

.25167E+09

.74829E+08

.85000E+03

.22667E+09

.99959E+07

.14434E+08

.24429E+08

.25110E+09

.75527E+08

.86000E+03

.22614E+09

.99470E+07

. 14433E+08

.24380E+08

.25052E+09

.76224E+08

. 87000E+03

.22563E+09

.98983E+07

.14433E+08

.24331E+08

.24996E+09

.76919E+08

.88000E+03 512E+09

.98498E+

.14433E+08

.24283E+08

.24 OE+09

.77612E+08

.89000E+03

.22461E+09

. 98015E+07

.14433E+08

.24234E+08

.24884E+09

.78304E+08

.90000E+03

.22411E+09

.97535E+07

.14433E+08

.24186E+08

.24830E+09

.78995E+08

.91000E+03

.22361E+09

.97058E+07

.14433E+08

.24138E+08

.24775E+09

.79684E+08

.92000E+03

.22312E+09

.96582E+07

.14432E+08

.24091E+08

.24721E+09

.80371E+08

. 93000E+03

.22264E+09

.96109E+07

.144

.24043E+08

.24668E+09

.81057E+08

.94000E+03 16E+09

.95638E+07

.14432E+08

.23996E+08

.24615E+09

.817 42E+08 00E+03

.22168E+09

.144 8

.2394

.24

.82425E+08

.96000E+03

.22121E+09

.. 94704E+07

.14432E+08

.23902E+08

.24511E+09

.83106E+08

.97000E+03

.22074E+09

.94240E+07

.14431E+08

.23855E+08

.24460E+09

.83787E+08

.9800

.2202

.93778E+07

.14 431E+08

.23809E+

.244

.84465E+08

.99000E+03

.21982E+09

.93319E+07

.14431E+08

.23763E+08

.24358E+09 85143E+08

.10000E+04

.21936E+09

.92862E+07

.14431E+08

.23717E+08

.24308E+09

.85819E+08

. 11000E+04

.19706E+09

.88413E+07

.14429E+08 OE+08

.22033E+09

.92255E+08

"A" Sheet 8 18 FNP Units 1 & 2 Calculation No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(

(BTU)

.12000E+04

.19329E+09

.84176E+07

.14427E+08

.22844E+08

.21613E+09

.98317E+08 4

.18 2E+09

.80143E+07

.14425E+08

.22439E+08

.21216E+09

.10427E+09

.14000E+04

.18633E+09

.7630

.14422E+08

.22052E+08

.20838E+09

. 11011E+09

. 15000E+04

.18309E+09

.72647E+07

.14420E+08

.21684E+08

.20478E+09

.11584E+09

.16000E+04

.18000E+09

.69166E+07

.14417E+08

.21334E+08

.20133E+09

.12148E+09

.17000E+04

.17704E+09

.658

.14414E+08

.21000E+08

.19804E+09

.12703E+09

.18000E+04 21E+09

.62

. 14411E+08 89£+09

.13249£+09

.19000E+04

. 17149E+

. 59693E+07

.14409E+08

.20378E+08

. 19187E+09

. 13786E+09

.20000E+04

.16889E+09

.56833E+07

.14406E+08

.20089E+08

.18898E+09

.14315E+09

.21000E+04

.16640E+09

.541 07

.14402E+08

.19813E+08

.18621E+09

.14836E+09

.22000E+04

.1 01E+09

.51517E+07

.14399E+08

.19551E+08

.18356E+09

.15350E+09

.23000E+04

.16171E+09

.49049E+07

.14396E+08

.19301E+08

.18101E+09

.15856E+09

.24000E+04

.15951E+09

.46699E+07

. 14393E+08

.19062E+08

.17857E+09

.16355E+09

.25000E+04

.1 OE+09

.44461E+

.1438

.188

.17624E+09

.16848E+09

.26000E+04

.15538E+09

.42331E+07

.14386E+08

.18619E+08

.17400E+09

.17335E+09

.27000E+04

. 15343E+09

.40303E+07

. 14382E+08

.18412E+08

.17184E+09

.17815E+09

.28000E+04

.151

.38371E+07

.14378E+08

.18216E+08

.16978E+09

.18290E+09

.29000E+04

.14977E+09

.3653

. 14375E+08

.18028E+08

.16780E+09

.18758E+09

.30000E+04

. 14805E+09

.347

.14371E+08

.17849E+08

.16590E+09

.19222E+09

.31000E+04

.14640E+09

.33116E+07

. 14367E+08

.17679E+08

.16408E+09

. 19680E+09

.32000E+04

.14481E+09

.31529E+07

. 14363E+08

.17516E+08

.16232E+09

.20

.33000E+04

.14328E+09

.30019E+07

. 14359E+08

.17361E+08

.1

.20582E+09

.34000E+04

.14181E+09

.28 OE+07

.14356E+08

. 17214E+08

.15902E+09

.21026E+09

.35000E+04

.14039E+09

.2 11E+07

.1 8

.17073E+08

.15747E+09

.21466E+

. 36000E+04

. 13903E+09

.25907E+07

.14348E+08

.16938E+08

.15597E+09

.21

.37000E+04

.137

.24666E+07

.14343E+08

.16810E+08

.15453E+09

.22332E+09

.38000E+04

.13646E+09

.23484E+07

.14339E+08

.16688E+08

.15315E+09

.22759E+09

.39000E+04

.13525E+09

.22359E+07

. 14335E+08

.16571E+08

.15182E+09

.23183E+09

.40000E+04

.13408E+09

.21287E+07

.14331E+08

.16460E+08

.15054E+09

.23603E+09

.41000E+04

. 13295E+09

.20267E+07

. 14327E+08

.1 8

.14930E+09

.24019E+09

.42000E+04

.1318

.19296E+07

.14323E+08

.16252E+08

.14811£+09

.24432E+09

. 43000E+04

. 13081E+09

.18372E+07

.14318E+08

.16155E+08

.14697E+09

.24842E+09

.44000E+04

.12980E+09

.17491E+07

.14314E+08

.16063E+08

.14586E+09

.25249E+09

.45000E+04

.12882E+09

.16653E+07

.14310E+08

.15975E+08

.14480E+09

.25653E+09

"A" Sheet 9 of 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INT£GRAL (S£C)

(

)

.4 OE+04

.12788E+09

. 15855E+07

.14305E+08

.15891£+08

.14377E+09

.26054£+09

.47000£+04

.12697E+09

.15096E+07

.14301E+08

. 15811E+08

.14278E+09

.26452£+09

.48000E+04

.12609E+09

. 14372E+07

.14297£+08

.15734£+08

.141 9

.26847E+09

.49000E+04

.12524E+09

.13684E+07

.14292E+08

.1 61E+08

.14090E+09

.2723 9

.12442E+09

.13028E+07

.14288£+08

.15591E+08

.14001E+09

.27630E+09

.51000E+04

.12362E+09

.12404E+07

. 14283E+08

.15524£+08

.13915E+09

.28017£+09

.52000E+04 5E+09

. 11810E+07

.14279E+08

.15460E+08

.1 09

.284 9

. 53000E+04 1

9

.11244E+07

.14274E+08

.15399£+08

.137 09

.28786E+09

.54000E+04

.12138E+09

.10705E+07

.14270E+08

.15340E+08

.13673£+09

.29167£+09

, 55000E+04

. 12069E+09

.10192E+07

.14265E+08

.15284E+08

.13597£+09

.29545E+09

. 56000E+04

.12001E+09

. 97038E+06

.142 08

.15231E+08

. 13524E+09

.29922£+09

.57000E+04

. 11935E+09

.92388E+06

.14256E+08

.15180E+08

.13453E+09

.30297E+09

. 58000E+04

. 11871E+09

.87961E+06

.14252E+08

.15131E+08

. 13384E+09

.30669E+09

. 59000E+04

. 11809E+09

.83747E+06

.14247E+08

.1

.13318E+09

.31040E+09

.60000E+04

. 11749E+09

.79734E+06

.14242E+08

. 15040E+08

.13253E+09

.31409£+09

. 61000E+04

,11691E+09

.75914E+06

.14238E+08

.149

.13190E+09

.31777E+09

.62000E+04

. 11634E+09

.72276E+06

.14233E+08

. 14956E+08

.13129E+09

.32142E+09

. 63000E+04

. 11579E+09

.68813E+06

.14229E+08

.14917£+08

.13070E+09

.32506E+09

.64000£+04

.1152 9

.65516E+06

.14224E+08

.14879£+08

.13013E+09

.32868E+09

,65000£+04

. 11472E+09

. 62377E+06

.14219E+08

.14

.12957E+09

.33229E+09

. 66000E+04

.114

.5938 6

.14215E+08

.14809E+08

.12 9

9

. 67000E+04

. 11372E+09

.56543E+06

. 14210E+08

.14775E+08

.12949E+09 6E+09

.68

.11324£+09 34E+06

. 14205E+08

.14744E+08 98E+09

.34 9

. 69000E+04

.11 6E+09

.51254E+06

.14201E+08

.14713E+08

.12748E+09

.34657E+09

.70000E+04

. 11230E+09

.48798E+06

.14196E+08

.14684£+08

.12699E+09

.35010£+09

.71000E+04

. 11185E+09

.46460E+06

.14191E+08

.14 656£+08

.12651E+09

.35362E+09

.72000£+04

. 11142E+09

.44234E+06

.14187E+08

.14629E+08

.12604E+09

.3 13£+09

.73000E+04

. 11099E+09

.42115E+06

.14182E+08

.14603E+08

.12559E+09

.36063E+09

.74000E+04

. 11057E+09

.40097E+06

. 14177E+08

.14578£+08

.12515E+09

.36411E+09

.75000E+04

. 11016E+09

.38176E+06

. 14172E+08

.14554£+08

.12471E+09

.36758E+09

.76000E+04

.10976E+09

.36347E+06

.14168E+08

.14531E+08

.12429E+09

.37104E+09

.77000E+04

.10937E+09

.34605E+06

.14163E+08

.14509E+08

. 12388E+09

.37448E+09

.78000E+04

.10898E+09

.32947E+06

.14158E+08

.14488E+08

.12347£+09

.37792£+09

.7

.10861E+09

.31368E+06

.14154E+08

.14467E+08

.123 9

.38134£+09

"A" Sheet 10 of 18 FNP Units 1 & 2 Calculation No.

TIME (SEC)

.80000E+04

. 81000E+04

.8 4

.84000E+04

.86000E+04

.87000E+04

. 88000E+04

.90000E+04

.91000E+04

.92000E+04

.93000E+04

.94000E+04

. 95000E+04 04

. 97000E+04

.98000E+04

. 99000E+04

.10000E+05

.11000E+05

.12000E+05

.1 05

. 14000E+05

.15000E+05

.16000E+05

.17000E+05

.1800 05

.19 OE+05

.2

.21000E+05

.22000E+05

.23000E+05 Rev. 6 FP

.10824E+09

.10788E+09

.10752E+09

.10718E+09

.10684E+09

.10650E+09

.10617E+09

.10585E+09

.10553E+09

.1

.10491E+09

.10461E+09

.10431E+09

.10402E+09

.10373E+09 4E+09

.10316E+09

.10289E+09

.10261E+09

.10234E+09

.10208E+09

.99584E+08

.97336E+08 08

.93347E+08

.91541E+08

.89834E+08

.88214E+08

.86673E+08 08

.83

.824 08

.81179E+08

.79953E+08 U-239

.29865E+06

.28434E+06

.27072E+06

.25775E+06

.24540E+06

.23364E+06 45E+06

.21179E+06 64E+06

.1 9

6

.18278E+06

.17402E+06

.16568E+06

.1 75E+06

.15019E+

.14299E+06

.13614E+06

.12962E+06

.12341E+06

. 11749E+06

.11186E+06

. 68462E+05

. 41900E+05

.2 3E+05

.15694E+05

.96050E+04

.58784E+04 7E+04 8E+

. 13475E+04

.8247 3

.50474E+03

.30891E+03

.18906E+03 NP-239

)

.1414

.14144E+08

.14139E+08

.14135E+08

.14130E+08

.14125E+08

.141

.1411

.14111E+

.14106E+08

.14101E+08

.14097E+08

.14092E+08

.14087E+08

.14082E+08

.14078E+08

.1407 08

.14068E+08

.14063E+08

.14059E+08

.14054E+

.14006E+08

.13 08

.13

.13864E+08

.13817E+08

.13770E+08

.13723E+08

.13676E+08

. 13630E+08

.13583E+08

.13537E+08

.13491E+08

.13445E+08 U239+NP239

.14448E+08

.1 8E+08

.14410E+08

.14392E+08

. 14375E+08

.14359E+08

.14343E+08

. 14328E+08

.14 3E+08

.14298E+08

.14284E+08

. 14271E+08

.142

.1424

.1

.14221E+08 209E+08

.141 08

.14187E+08

.14176E+08

.14166E+08

.14075E+08

. 14001E+08

.13

.13880E+08

.13827E+08

. 13776E+08

.1

.1367

.1363

.13538E+08

.13491E+08

. 13445E+08 TOTAL

,12269E+09

.12231E+09

.12193E+09

',12157E+09

.12121E+09

.12086E+09

. 12052E+09

.12018E+09

. 11984E+09

.11

. 11920E+09

.11888E+09

. 11857E+09

.1182

.11796E+09

.11766E+09

.117

. 11708E+09

.11680E+09

.11

.11624E+09

. 11366E+09 11134E+09

.10921E+09

.1072

.1 09

.10361E+09

.101 9

.10035E+09

.98835E+08

. 97385E+08 08

.94670E+08

.93398E+08 INTEGRAL

.38476E+09

.38816E+09

.39155E+09

.39493E+09

,39831E+09

.40167E+09

.40502E+09

.40836E+09

.41170E+09

.41502E+09

.41834E+09

.42164E+09

.42494E+09

.42823E+09

.43151E+09

.43478E+09

.43805E+09

.44131E+09

.44455E+09

.44779E+09

.45103E+09

.48296E+09

.51421E+09

.54484E+09

.57490E+09 43E+09

.66200E+09

. 69009E+09

.7 6E+09

.74501E+09

.77187E+09

.79835E+09

.82447E+09

"A" Sheet 11 of 18 FNP Units 1 & 2 Calculation No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(

(BTU/HR)

(

.24000E+05

.78779E+08

. 11570E+03

.13399E+08

. 13400E+08

.92179E+08

. 25000E+05

.77656E+08

.70813E+02

. 13354E+08

.91010E+08

.26000E+05

.76581E+08

.43338E+02

.13308E+08

. 13308E+08

.89889E+08

.27000E+05

.75551E+08

.2

.13263E+08

.1326 8

',8881 8

.28000E+05

,74564E+08

,16233E+02

.13218E+08

,13218E+08

.87782E+08

,95016E+09

.29000E+05

.73619E+08

.99348E+01

.13173E+08

.1 3E+08

.86792E+08

,97441E+09 1

8 01

.13 8

.13

.85841E+08

.99839E+09

.31000E+05

,71844E+08

.37212E+01

. 13083E+08

.13083E+08

.84927E+08 21E+10

.32000E+05

.71011E+08

.22774E+01

.13039E+08

.84050E+08

.104 56E+ L

\\

)

.33000E+05

.70212E+08

. 13938E+01

. 12995E+08

.12995E+08

.83207E+08

.10688E+10

.34000E+05

.69446E+08

.85303E+00

.12950E+08

.82396E+08 8E+

. 35000E+05

.68711E+08

. 12906E+08

.1

.81617E+08

.11146E+10

.36000E+05

.68005E+08

.31951E+00

.12862E+08

.80867E+08

.11372E+10

.37000E+05

.67327E+08

. 19555E+00

.12818E+08

.80146E+08

.1 10

.38000E+05

. 66677E+08

. 11968E+00

.12775E+08

.79451E+08

.11817E+10

. 39000E+05

.6

.73244E-01

.12731E+08

. 12731E+08

.78783E+08

.12037E+10

.4 51E+08

.44826E-01

.12688E+08

.78139E+08

.12255E+10

.41000E+05

.64874E+08

.27434E-Ol

.12645E+08

. 12645E+08

.77519E+08

.12471E+10

.42000E+05

.64319E+08

.16790E-Ol

.12602E+08

.76921E+08

.12685E+10

.43000E+05

.63785E+08

.10276E-01

.12559E+08

.76344E+08

.12898E+I0

.44000E+05 2E+08

.62

.12516E+08

.75788E+08

.13109E+10

.45000E+05

.62778E+08

.38489E-02

.12473E+08

.75252E+08

.13319E+10

.46000E+05

.62303E+08

.2

.12431E+08

.74734E+08

.13527E+10

.4 845E+08

. 14417E-

.12389E+08

. 12389E+08 233E+08

.13734E+I0

.48000£+05

. 61404E+08

.88232E-03

.12347E+08

. 12347E+08

.73750E+08

.13940E+10

.49000E+05

.60979E+08

.53999E-03

.12305E+08

.73283E+08

.14144E+I0

.50000E+05

.60569E+08

.33048£-03

.12263E+08

.72832E+08

.14347E+10

. 51000E+05

.60174E+08

.12221E+08 1E+08

.72395E+08

.14549E+10

. 52000E+05

.59793E+08

.1 9E-03

. 12179E+08

.12179E+08

.71972E+08

.14749E+10

.59425E+08

.75758E-04

.12138E+08

.71563E+08

.14949E+10 000E+05

. 59070E+08

.463

. 12097E+08

.71166E+08

.15147£+10

. 55000E+05

.58727E+08

.28376E-04

.12055E+08

.70782E+08

.15344E+10 56000E+05

.58396E+08

.17367E-04

.12014£+08

. 12014E+08

.70410E+08

.15540E+10

.57000E+05

.58075E+08

.10629E-04

. 11973E+08

.70049E+08

.15735E+10

IfAn Sheet 12 of 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

(

. 58000E+05

.57766E+08

. 65049E-05

.1l933E+08

.11933E+08

. 69698E+08

. 15929E+10

. 59000E+05

.57466E+08

.39811E-05

.11892E+08

.1l892E+08

.16122E+10

.60000E+05

.57176E+08

.24365E-05

.1l852E+08

. 11852E+08

. 69028E+08

.16315E+10

. 61000E+05

.56B96E+08

.149

.1l811E+08

.1l81lE+08

.68 08

.16506E+lO

.62000E+05

. 56624E+08

.91261E-06

. 11771E+08

.11771E+08

. 68395E+08

.16696E+10

. 63000E+05

.56360E+08

.55853E-06

.11731E+08

. 68091E+08

.16886E+10

.64000E+05

.34183E-06

.11691E+08

.67796E+08

.17075E+I0

. 65000E+05

.55857E+08

.20920E-06

.1l651E+08

. 11651E+08

. 67508E+08

.17263E+I0

. 66000E+05

.55616E+08

.12803E-06

.11 8

.11612E+08

. 67228E+08

.17450E+10

. 67000E+05

.55383E+08

.78359E-07

. 11572E+08

. 66955E+08

.17636E+I0

. 68000E+05

.55156E+08

.47957E-07

.1l533E+08

.11533E+08

. 66689E+08

.17822E+I0

. 69000E+05

.54936E+OB

.29350E-07

.1l493E+08

.11493E+08

.66429E+08

.18007E+10

.70000E+05

.54722E+08

. 17963E-07

.11454E+08

. 66176E+08

.18191E+I0

.71000E+05

.54514E+08

.10994E-07

.1141

.1l415E+08

. 65929E+08

.18374E+I0 05

.5431lE+08

.67282E-08

.11376E+08

.1l376E+08

.65687E+08

.18557E+I0

.73000E+OS 114E+08

.41177E-08

.1l338E+08

.1l338E+08 51E+08

.18739E+I0

.74

.25201E-08

.11299E+08

.1l299E+08

. 65220E+08

.18921E+I0

.75000E+05

.S3734E+08

.lS423E-08

.1l261E+08

.11261E+08

.6499SE+08

.19101E+IO

.76000E+OS

.53552E+OB

.94 9

.1l222E+08

. 11222E+ 08

.64774E+08

.192B2E+IO

.77000E+05

.53373E+08

.57770E-09

.1l184E+OB

.11184E+08

. 64557E+08

.19461E+10

.7B

.53200E+08

.35356E-09

.1114 6E+08

.11146E+08

.64346E+08

.19640E+10

.79000E+OS

. 53030E+OB

.21638E-09

.11108E+08

.1110BE+08

.64138E+08

.19819E+10

.80000E+OS

.52864E+08

.13243E-09

.1l070E+08

.11070E+08

.63934E+08

.19997E+10

.81000E+OS

.52702E+08

.810S0E-I0

.11033E+OB

.II033E+08

.63735E+08

.20174E+10

.52544E+OB

.49603E-10

.10 8

.10995E+08

. 63539E+08

.20351E+10

.83000E+05

.52389E+08

.30358E-IO

.10958E+08

.63347E+08

.20527E+10

. 84000E+05 08

.18580E-10

.10920E+08

.63158E+08

.20703E+10

.85000E+05

.52089E+08

.1l371E-10

.10883E+08 83E+08

. 62973E+08

.20878E+IO 6000E+05

.51944E+08

.69592E-ll

.10846E+08

. 62790E+08

.21053E+10

(,

l 87000E+05

.51802E+08

.42591E-ll

.10809E+08

.62611E+OB

.21227E+10

. 88000E+05

.51662E+OB

.26066E-11

.1077

.10772E+OB

.62435E+08

.214 OOE+ 10

.89000E+OS

.51526E+OB

.lS953E-ll

.10736E+OB

.I0736E+08

.62261E+OB

.21574E+IO

.90000E+05

.51391E+OB

.97634E-12

.10699E+08

.62091E+08

.21746E+10

. 91000E+05

.51260E+OB

.59754E-12

.10663E+08

.61922E+08

.21919E+10

IIA" Sheet 13 of 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

)

. 92000E+05

.51130E+08

.36570E-12

.10626E+08

.61757E+08

.22090E+10

.93000E+05

.51003E+08

.22381E-12

.10590E+08

.61594E+08

.22262E+10

.94000E+05

.50879E+08

.13698E-12

.1

.10554E+08

.61433E+08

.22433E+10

.95000E+05

.50756E+08

.83832E-13

.10518E+08

.612 8

603E+10

.96000E+05

.50635E+08

.51306E-13

.10482E+08

.10482E+08 118E+08

.22773E+10

. 97000E+05

.50517E+08

.31400E-13

.10447E+08

.60963E+08

.22942E+10

. 98000E+05

.504 08

. 19217E-13

.10411E+08

.60811E+08

.23112E+10

.99000E+05

.50285E+08

.11761E-13

.10376E+08

.60660E+08

.23280E+10

.10000E+06

.50172E+08

.71981E-14

.1034

.60512E+08

.23449E+10

. 11000E+06

.491

.53068E-16

.9

.59116E+08

.25110E+10

. 12000E+06

.48192E+08

.39124E-18

.96587E+07

.9658

.57851E+08

.26735E+10

.13000E+06

.47348E+08

.28844E-20

. 93349E+07

.93349E+07

.56683E+08

.28325E+10

.14000E+06

.46570E+08

.21265E-22

.90219E+07

.90219E+07 08

.29885E+10

.1 6

.45843E+08

.15678E-24

.87194

.87194E+

.54 08

.31415E+10

. 16000E+06

.45160E+08

.11558E-26

. 84271E+07

.84271E+07

.53587E+08

.32917E+10

. 17000E+0 6

.44514E+08

.85215E-29

.8144

.81446E+07

.52 08

.34392E+10

.18000E+06

.4 08

.62824E-31

.78716E+07

.51773E+08

.35843E+10

. 19000E+06

.43318E+08

.46317E-33

.76077E+07

.50925E+08

.37269E+10

.20000E+06

.42761E+08

.34232E-35

.73526E+07

.50114E+08

.38673E+10

.21000E+06

.42230E+08

.21262E-37

.71061E+07

.49337E+08

.40054E+10

.22000E+06

.41723E+08

.OOOOOE+OO

.68 07

. 68679E+07

.48591E+08

.41414E+10

.23000E+06

.41238E+08

.OOOOOE+OO

. 66376E+07

.66376E+07

.47876E+08

.42754E+10

.24000E+06

.40774E+08

.OOOOOE+OO

.64151E+07

.47189E+08

.44074E+10 06

.40329E+08

.OOOOOE+OO

. 62000E+07

.46529E+08

.45376E+10

.26000E+06

.39904E+08

.OOOOOE+OO 2E+07

.59922E+07

.45896E+08

.46659E+10

.27000E+06

.39496E+08

.OOOOOE+OO

.57913E+07

. 45287E+08

.47926E+10

.28000E+06

.39104E+08

.OOOOOE+OO

.55971E+07

.44702E+08

.49176E+10

.29000E+06

.38729E+08

.OOOOOE+OO

.54

.54095E+07

.44139E+08

.50410E+10

.30000E+06

.38369E+08

.OOOOOE+OO

.52281E+07

.43597E+08

.51628E+10

.31000E+06

.38024E+08

.OOOOOE+OO

.50529E+07

.43076E+08

.52832E+10

.3 6

. 37692E+08

.OOOOOE+OO

.48835E+07

.42 08

.54021E+10

.33000E+06

.37373E+08

.OOOOOE+OO

.47198E+07

.42092E+08

.55197E+10

.34000E+06

.37066E+08

.OOOOOE+OO

.45615E+07

.41627E+08

.56360E+10

.35000E+06

.36771E+08

.OOOOOE+OO

.44086E+07

.41179E+08

.57510E+10

"AI} Sheet 14 of 18 FNP Units 1 & 2 No, Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL

)

(BTU/HR)

(

1

(

.36000E+06

.36487E+08

.OOOOOE+OO

.42608E+07

.40748E+08

.S8648E+10

.37000E+06

.36213E+08

.OOOOOE+OO

.41180E+07

.40331E+08

.S9774E+I0

.38000E+06

. 35950E+08

.OOOOOE+OO

. 39799E+07

.39799E+07

.39930E+08

.60889E+I0

.39000E+06

.35696E+08

.OOOOOE+OO

.38465E+07

.3846

',3954

.61993E+10

.40000E+06

,35451E+08

.OOOOOE+OO

.37175E+07

.39169E+08

.63086E+10

.41000E+06

. 35215E+08

.OOOOOE+OO

. 35929E+07

.38808E+08

.64169E+I0

.42000E+06

.34 OE+OO E+07

.34724E+07

.38460E+08

. 65242E+10

.43000E+06

.34767E+08

.OOOOOE+OO

. 33560E+07

.38123E+08

. 66306E+10

.44000E+06

.34554E+08

.OOOOOE+OO

. 32435E+

.324

.37797E+08

.67360E+I0

.45000E+06

. 34348E+08

.OOOOOE+OO

.31348E+07

.37483E+08

.68406E+lO

.46000E+06

.34149E+08

.OOOOOE+OO

.30297E+07

.37178E+08

.69443E+10

.47000E+06

. 33956E+08

.OOOOOE+OO

.29281E+07

.36884E+08

.70471E+I0

.48000E+06

. 33769E+08

.OOOOOE+OO

. 28299E+07

.28299E+07 08

.71492E+10

.4 6

. 33588E+08

.OOOOOE+OO 351E+07

.3 505E+10

.50000E+06

.33412E+08

.OOOOOE+OO

.26434E+07

.36056E+08

.73510E+I0

. 51000E+06 08

.OOOOOE+OO

.25548E+07

.35797E+08

.74508E+I0

.33076E+08

.OOOOOE+OO

.24691E+07

.35545E+08

.75499E+I0 6

. 32916E+08

.OOOOOE+OO

.23863E+07

.7 83E+10

.54000E+06

.32759E+08

.OOOOOE+OO

.230

.23063E+07

.3 08

.77460E+10

. 55000E+06

.32607E+08

.OOOOOE+OO

. 22290E+07

.22290E+07

.34836E+08

.78431E+10

. 56000E+06 08

.OOOOOE+OO

.21543E+07

.34614E+08

.79396E+10 57000E+06

. 32315E+08

.OOOOOE+OO

.20821E+07

.34

.80354E+10

. 58000E+06

.32175E+08

.OOOOOE+OO

.20123E+07

.34187E+08

.81307E+I0

.59000E+06

. 32038E+08

.OOOOOE+OO

. 19448E+07

.19448E+07

.33983E+08

.82254E+I0

.60000E+06

. 31905E+08

.OOOOOE+OO

. 18796E+07

.33784E+08

.83195E+10

. 61000E+06

.31774E+08

.OOOOOE+OO

. 18166E+07

.18166E+07

.33591E+08

.84130E+10

. 62000E+06

. 31647E+08

.OOOOOE+OO

. 17557E+07

.33403E+08

.85061E+I0

. 63000E+06

.31 0

.169

.16968E+07

.33219E+08

.85986E+10

. 64000E+06

.31401E+08

.OOOOOE+OO

.1

.16399E+07

.33041E+OB

.86907E+10

. 65000E+06

.31282E+08

.OOOOOE+OO

. 15850E+07

.1 07

.32867E+08

.87822E+I0

.6

.31

.0 0

.1

. 15318E+07

.32698E+OB

.88733E+I0

.67000E+06

.3

.OOOOOE+OO

.14805E+07

. 14805E+07

.32532E+08

.89639E+I0

. 68000E+06

.30940E+08

.OOOOOE+OO

. 14308E+07

.14308E+07

.32371E+08

.90540E+I0

.69000E+06

.30831E+08 OOE+OO

.13829E+07

. 13829E+07

.32214E+08

.914 37E+ 10

Sheet 15 of 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL (SEC)

)

(

(BTU/HR)

(

.70000E+06

.30724E+08

.OOOOOE+OO

.13365E+07

.32060E+08

.92330E+I0

.71000E+06

.3061SE+OS

.OOOOOE+OO

.12917E+07

.31910E+08

.93218E+I0

.72000E+06

.3

.OOOOOE+OO

.124B4E+07

. 124B4E+07

.31763E+OB

.94103E+I0

.73000E+06 14E+OS

.OOOOOE+OO

.12065E+07

.120

.31620E+OB

.94983E+I0

.74000E+06

.30314E+OS

.OOOOOE+OO

.1l661E+07

.314BOE+OB

.95859E+I0

.75000E+06

.30216E+08

.OOOOOE+OO

.1l270E+07

.31343E+OB

.96732E+10

.76000E+06 119E+08 00

.108 07

.10

.312 08

.97601E+I0

.77000E+06

.30025E+08

.OOOOOE+OO

.1 07

.1052

.3107

.9846 0

. 78000E+06 00

.10174E+07

.101

.30949E+08 10

.79000E+06

.29839E+08

.OOOOOE+OO

.98330E+06

.9S330E+06

.30B23E+08

.10019E+1l

.80000E+06

.29749E+OB

.OOOOOE+OO

.95033E+06

.30699E+OB

.10104E+ll

. 81000E+06

.29660E+08

.OOOOOE+OO

.91B47E+06

.91847E+06

.3057BE+08 11

.82000E+06

.2957 8

00

.88768E+06

.B8768E+06

.30459E+OS

.10274E+1l

.83000E+06 8

.0000

.8 06

.857 6

.30 3E+OB

.103 11

.S4000E+06

.29400E+08

.OOOOOE+OO 6E+06

.8291

.30229E+08

.10442E+1l

.85000E+06

.29315E+08

.OOOOOE+OO

.80136E+06

.301 8

.10526E+ll

.8600

.29232E+08

.OOOOOE+OO

. 77450E+06

.77450E+06

.30006E+08

.10610E+1l

.87000E+06

.29150E+OS

.OOOOOE+OO

.74853E+06

.29898E+OB

.10693E+1l

.88000E+06

.2906SE+OS

.OOOOOE+OO

.72344E+06

.29792E+OB

.10776E+1l

.89000E+06

.2898SE+Oa

.OOOOOE+OO 6

.69918E+06

.29687E+08

.1085SE+11

.90000E+06

.28909E+Oa

.OOOOOE+OO 574E+06

.6757 6

.2 8

.10941E+11

.91000E+06

.28830E+OS 0

.65309E+06

.294B3E+OB

. 11023E+ll

.92000E+06

.2S753E+OS

.OOOOOE+OO

.6311 06

.63119E+06

.29384E+08

.1l105E+ll

. 93000E+06

.28676E+OS

.00

.61003E+06

.292B6E+08

.11186E+11

.94000E+06

.28600E+08

.OOOOOE+OO

.5S958E+06

.58958E+06

.29190E+08

.11267E+11

.95000E+06

.2S525E+08

.OOOOOE+OO

.569BIE+06

.56981E+06

.29095E+08

.11348E+11

.96000E+06

.28451E+08

.OOOOOE+OO

.55071E+06

.29002E+08

.1l429E+11

.97000E+06

.28377E+08

.OOOOOE+OO

.53225E+06 6

.28 8

.11509E+11

.98000E+06 8

.OOOOOE+OO

.51441E+06

.5144 6

.28819E+08

.1l590E+ll

. 99000E+06

.28232E+08

.OOOOOE+OO

.49716E+06

.28729E+08

. 11 669E+1l

.1

.28161E+08 00

.48

.48049E+06

.28641E+08

.1l749E+11

.llOOOE+07

.27479E+OS

.OOOOOE+OO

.34166E+06

.27B21E+08

.12533E+11

. 12000E+07

.2684SE+08

.OOOOOE+OO

.24294E+06

.27091E+08

.13296E+1l

. 13000E+07

.26257E+OS

.OOOOOE+OO

.17274E+06

. 17274E+06

.26430E+08

. 14039E+1l

"An Sheet 16 of 18 FNP Units 1 & 2 No. BM-95-0961-001. Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL

(

(BTU/HR)

(

.14000E+07

.25701E+Oa

.OOOOOE+OO

.12283E+06

.25824E+08

. 14765E+11

.15000E+07

.25175E+08

.OOOOOE+OO

.8734

.87340E+05

.25262E+08

.15475E+11

.16000E+07

.24676E+08

.OOOOOE+OO

. 62104E+05

.62104E+05

.24738E+08

.16169E+11

. 17000E+07

.24201E+08

.OOOOOE+OO

.44160E+05

.24245E+08

.16849E+11

. 18000E+07

.23749E+08

.OOOOOE+OO

.31400E+05

.23781E+08

.17516E+11

. 19000E+07

.23319E+08

.OOOOOE+OO

.22327E+05

.23341E+08

.18171E+11

.22909E+08

.OOOOOE+OO

.1587

.1 6E+05

.22924E+08

.18813E+11

.21000E+07

.22517E+08

.OOOOOE+OO

. 11289E+05

.22528E+08

.19445E+11

.22143E+08

.OOOOOE+OO

.8 OE+04

.80270E+04

.22151E+08

.20065E+11

. 23000E+07

.21786E+08

.OOOOOE+OO 077E+04

.57077E+04

.21792E+08

.20676E+ll

.24000E+07

.21445E+08

.OOOOOE+OO

.40585E+04

.21449E+08

.21276E+11

.25000E+07

.21119E+08

.OOOOOE+OO

.28858E+04

.21122E+08

.21867E+11

.26000E+07

.20807E+08

.OOOOOE+OO

.20520E+04

.20809E+08

.224 50E+ 11

.20509E+08

.0

.14 04

. 14591E+04

.20510E+08

.23024E+11

.28000E+07

.20223E+08

.OOOOOE+OO

.10375E+04

.20224E+08

.23589E+11

.29000E+07

.19950E+08

.OOOOOE+OO

.73772E+03

.19951E+08

.24147E+11

.19688E+08

.OOOOOE+OO

.52456E+03

.19688E+08

.24698E+11

.31

.19436E+08

.OOOOOE+OO

.37300E+03

.19437E+08

.25241E+11

. 32000E+07

.19195E+08

.OOOOOE+OO

.26522E+03

.19195E+08

. 25778E+ 11

.33000E+07

.18964E+08

.OOOOOE+OO

.18859E+03

.188 3

.18964E+08

.26308E+11

. 34000E+07

.18742E+08

.OOOOOE+OO

.. 13410E+03

.13410E+03

.18742E+08

.26832E+11

.35000E+07

. 18528E+08

.OOOOOE+OO

.95351E+02

.18528E+08

.27349E+11

.1

.OOOOOE+OO

. 67800E+02

.67800E+02

.18323E+08

.27861E+11

.3

.1812

.48210E+02

.18126E+08

. 28367E+ 11

.38000E+07

.17936E+08

.OOOOOE+OO

.34280E+02

.17936E+08

.28868E+11

.39000E+07

.17753E+08

.OOOOOE+OO

.24375E+02

.17753E+08

.29364E+11

.40000E+07

.17577E+08

.OOOOOE+OO

.17332E+02

.17577E+08

.29855E+11

.41

. 17408E+08

.OOOOOE+OO

.12324E+02

.12324E+02 408E+08

.30340E+11

.42000E+07

.17244E+08

.OOOOOE+OO

.87632E+Ol

.87632E+01

.17244E+08

.30822E+11

.43000E+07

.17086E+08

.OOOOOE+OO

.62312E+01

.17086E+08

.31299E+11

.44000E+07

.16934E+08

.OOOOOE+OO

.44307E+01

.44307E+Ol

.16934E+08

. 31771E+11

.45000E+07

.16786E+OB

.OOOOOE+OO

.31505E+01

.16786E+OB

.32239E+11

.46000E+07

.16644E+08

.OOOOOE+OO

.22402E+01

.16644E+08

.32704E+11

.47000E+07

.16506E+08

.OOOOOE+OO

.15929E+01

.15929E+Ol

.16506E+08

.33164E+11

I(AJ}

17 of 18 FNP Units 1 & 2 No.

Rev. 6 TIME FP U-239 NP-239 U239+NP239 TOTAL INTEGRAL

(

{

(

. 48000E+07

.16373E+08

.OOOOOE+OO

. 11327E+01

.16373E+08

.33621E+11

.49000E+07

.16244E+08

.OOOOOE+OO

.80539E+00

.B0539E+00

.16244E+08 4E+1l

.50000E+07

. 16119E+08

.OOOOOE+OO

.57268E+00

.5726BE+00

.1611

.34523E+1l

.51000E+07

.1 08

.OOOOOE+OO

.40721E+00

.4 00

.1 OB

. 34969E+ 11

. 52000E+07

.15880E+08

.OOOOOE+OO

.28 00

.2B955E+00

.15880E+08

.35412E+1l 07

.15766E+08

.OOOOOE+OO

.20589E+00

.205B9E+00

.15766E+08

.35852E+ll 07

. 15655E+08

.OOOOOE+OO

.14 OE+OO 14

.15

.36288E+ll

. 55000E+07

.15547E+08

.10410E+00

.15547E+08

.36721E+11

.56000E+07

.15443E+08

.OOOOOE+OO

.74019E-Ol

.74019E-01

.1 43E+08

.37152E+11 000E+07

.15341E+08

.OOOOOE+OO

.52632E-Ol

.52632E-01

.15341E+08

.37579E+11

. 58000E+07

.15241E+08

.OOOOOE+OO

.37424E-Ol

.37*424E-Ol

.1524 8

.38004E+1l

.15145E+08

.OOOOOE+OO

.26611E-Ol

.26611E-01

. 15145E+08

.38426E+1l

.60000E+07

.15051E+08

.OOOOOE+OO

.18922E-01

.1

.15051E+08

.38845E+1l

.61000E+07

.1

.OOOOOE+OO

.134

.1

.14959E+08

.39262E+1l

. 62000E+07

.14870E+08

.OOOOOE+OO 95670E-02

.95670E-02

. 14870E+08

.39677E+11

. 63000E+07

.14782E+08

.OOOOOE+OO

.6B027E-02

. 14782E+08

.4008BE+11

.64

.14697E+08 OOOOOE+OO

.48371E-02

.14697E+08

.4049 11

.65000E+07

.14614E+08

.OOOOOE+OO

.34395E-02

.14614E+08

. 40905E+ 11

. 66000E+07

.14532E+08

.OOOOOE+OO

.24457E-02

. 14532E+08

. 41310E+ll

.67000E+

.14453E+08

.OOOOOE+OO

.173

.17

.14453E+08

.41712E+ll

.68000E+07

.14375E+08

.OOOOOE+OO

.123

. 12365E-02

.14375E+OB

. 42113E+11

. 69000E+07

.14299E+08

.OOOOOE+OO

.87926E-03

.14299E+08

.42511E+ll

.70000E+07

.14224E+08

.OOOOOE+OO

.62520E-03

.14224E+08

.42907E+11

.71000E+07

.14151E+08

.44456E-03

.14151E+08

.43301E+11

.72000E+07

.14079E+08

.OOOOOE+OO

.31611E-03

.14079E+OB

.43693E+1l

.73000E+07

.14009E+08

.OOOOOE+OO

.224 03

.224

. 14009E+08

.44083E+ll

.74000E+07

. 13940E+08

.OOOOOE+OO

. 15982E-03

.13940E+08

.44472E+11

.75000E+07

.13

.0 00

.11364E-03

. 11364E-03

.13873E+08

.44858E+1l

.76000E+07

. 13806E+08

.OOOOOE+OO

.80B08E-04

.80808E-04

.13806E+OB

.45242E+1l

.77000E+07

.13741E+08 OOE+OO

.57459E-04 57459E-04

.13741E+08

.45625E+11

.78000E+07

.13677E+08 00

.408 4

.40857E-04

.13677E+08

.4 11

.79000E+07

.13614E+08

.OOOOOE+OO

.29052E-04

. 13614E+08

.46385E+11

.80000E+07

.13552E+08

.OOOOOE+OO

.20657E-04

. 13552E+08

.46762E+11

.81

.134 00

.14689E-04

.13491E+08

.47138E+11

"A" Sheet 18 of 18

, FNP Units 1 & 2 No.

TIME

(

07

. 83000E+07

. 84000E+07

. 85000E+07

. 86000E+07

.87000E+07

.88 07

. 89000E+07

. 91000E+07

. 92000E+07

.93000E+07

.94000E+07 07 07

.97

. 98000E+07

. 99000E+

.1 Rev. 6 FP (BTU/HR)

. 13432E+08

.13373E+08 133

.13258E+08

.13201E+08

.13146E+08

.13091E+08

. 13038E+08

.12985E+08

.1

.12881E+08

.12830E+08

.12780E+08 B

.12681E+08

.12633E+08

.12585E+08

.12538E+08

.12491E+08 U-239

.OOOOOE+OO

.OOOOOE+OO OE+OO

.OOOOOE+

.OOOOOE+OO 00

.OOOOOE+OO

.OOOOOE+OO 00

.OOOOOE+OO

.OOOOOE+OO NP-239

.10445E-04

.742 5

.52808E-05

. 26700E-05

.18985E-05

. 13500E-05

. 95990E-06

.682 6

.48 6

.34510E-06

.24539E-06

.17448E-06

.12407E-06

.88220E-07

.62730E-07

.4460

.31716E-07

.22552E-07 U239+NP239 (BTU/HR)

.10445E-04

.74267E-05

.528

.26700E-05

.18985E-05

. 13500E

.95990E-06

.682 06

.48533E-06

.34510E-06

.24

.17448E-06

.124 6

.88220E-07

. 62730E-07

.44604E-07

.3 16E-07

.22552E-07 TOTAL

. 13432E+08

. 13373E+08

. 13315E+08

'.13258E+08

. 13201E+08

. 13146E+08

.13091E+

. 13038E+08

.12985E+08

.12932E+08

. 12881E+08

.12830E+08

. 12780E+08

. 12730E+08

.12681E+08

. 12633E+08

. 12585E+08

. 12538E+08

. 12491E+08 INTEGRAL

(

.47512E+11

. 47884E+ 11

.48255E+11

.48624E+11

.48991E+11

.49357E+11

.49721E+11

.50084E+11

.5044 6E+11

.50806E+11

.51164E+11

.51521E+11

.51877E+11 31E+11

.52584E+11

.52936E+11

.53286E+11

.53635E+11

.53983E+11

Attachment 'WI Sheet 1 of 1 FNP Units 1 & 2 Calculatfon No. U'V'-::7"-lJ'"

Rev. (:,

AiTAcJIMl!IVT A I SHEeT

.1W"I 1),1#. MUIlP~'( lz..jnh?

1200 1204 1202 1200 11g8 i

119(5 i ~

<Xl w

1194 1192 1190 Has 1188 1184 100 300 soo 700 900 PSIA Saturation Preuura file

C:~'*:-"Io\\enthalpy.wk4

Attachment "B" Sheet 1 of 2 Jennings, Willie J.

fNP Units 1 & 2 Calculation No. BM-95-0961-Q01, Rev.

From:

Nesbit, Thomas H.

Sent:

Wednesday, June 27. 2012 4:32 PM To:

Jennings, Willie J.

Co:

Williams, Clarence Daniel; Isler, Jerry Lee

Subject:

RE: CST Sizing Verification* MSLB and MFWlB Events (Mass Flow Question)

Willie, We ran simulator scenarios this morning, but I've been on a teleconference all day since. All scenarios were done with a three man crew and intentionally done at a slow pace to bias the timeline towards a longer completion. There were no failures.

The first scenario was a 12 mpph (million mass per hour) MSlB in 1B SG upstream of the MSIVs with Reps in service. The time line was as follows:

07;37;30 Event start (MSIVs automatically close) 07:42.:00 AFW isolated to IB SG per early action by UO 07:43;00 EEP-O steps 8 & 9 reached (these steps direct the actions which the UO performed at 07:42:00) 07:46:30 Transition from EEP-O to EEP-2 07:53;00 FinallB SG isolation per EEP-2 The second scenario was a 20 mpph MFWlB inside CTMT with Reps in service. The time line was as follows:

08:02:00 Event start (M5IVS automatically automatic 51 occurs EEP-O immediate actions requiring longer time for completion) 08:08:00 AFW isolated to 18 SG per EEP-O (early UO action intentionally not allowed) 08:10:00 Transition from EEP-O to EEP-2 08:16:00 FinallB SG isolation complete per EEP-2 I was not able to talk to you this before the simulator runs so our break sizes differ from those used in your calculations. Also, I dropped the ball and left the Reps on during the MFWlB. I don't think that either of these differences would measurably affect the time lines up to AFW isolation to the faulted SG. As you can see, AFW flow to the faulted SG was isolated in 6 minutes or less in each case and there was only Nl minute difference when operator action was allowed instead of forcing the crew to wait for direction. Please review these results and let me know If you need more but I believe these time lines support a 30 minute time for AFW isolation to the faulted SG as a conservative value. As an the initial total AFW flow rate to all three SGs was Nll00 gpm in each case and the final throttled total AFW flow rate to the two intact 5Gs was N180 gpm with stable SG levels and RCS temperature.

Turbo From: Jennings, Willie ].

Sent: Wednesday, June 27, 2012 10:'49 AM To: Nesbit, Thomas H.

__'_... _..._. RE: CST Verification - MSLB and MFWLB Events Flow Question)

Thom; 1

Attachment uB" Sheet 2 of 2 FNP Unit!; 1 &2 Calculation No. BM-95-0961-001, Rev. "

Here's the mass flow rates taken from the AFW flow balance WhlCl) defines flows to the faulted S?G as well as the intact I've taken these flow in gpm and converted them to mass flow rates at the max. temperature of the CST. I not sure if you should use the flow to the faulted or flow to all But here is flow to both.

MFWlB: Faulted S/G - 2.47 X10115 lBm/Hr.; All

- 3.25)( 10"5 lBm/Hr. ; the difference is what is flowing to the intact MSlB w/o LOSP: Faulted

- 3.79 x 1011 5lBm/Hr.; All S/Gs 1.02 x 1O"6lbm/Hr.; the difference is what is flowing to the intact

Original Appolntment----

from: Nesbit, Thomas H.

Sent; June 22, 2012 9:30 AM To: Jennings, Willie J.

Accepted: CST Verification - MSlB and MFWlB Events When: Monday, June 20129:30 AM-I0:30 AM (GMT-06:00) Centraillme (US &

Where: Conference Call 2

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