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E-mail Gucwa, Entergy Nuclear Northeast, to Ennis, NRR, VY EPU Supplement 30
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Issue date:	08/02/2005
From:	Gucwa L; Entergy Nuclear Northeast
To:	Richard Ennis; Office of Nuclear Reactor Regulation
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Rick Ennis - BW 05-072 Exhibits SPSB-C-52-4, 5, and 6 Page 1 From: "Gucwa, Len" <LGUCW90@entergy.com>

To: "Rick Ennis" <RXE~nrc.gov>

Date: 8/2/05 2:21 PM

Subject:

BVY 05-072 Exhibits SPSB-C-52-4, 5, and 6

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VY Licensing Igucw90@entergy.com 802/451-3193 CC: <Douglas.Rosinski@pillsburylaw.com>

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Created By: LGUCW90@entergy.com Recipients nrc.gov owf4_po.OWFNDO RXE (Rick Ennis) pillsburylaw.com Douglas.Rosinski CC Post Office Route oxxf4_po.0WFNDO nrc.gov pillsburylaw.com Files Size Date & Time MESSAGE 177 08/02/05 02:12PM TEXT.htm 1713 BVY 05-072 Ex. SPSB-C-52-6.pdf 282378 BVY 05-072 Ex. SPSB-C-52-4.pdf 3401670 BVY 05-072 Ex. SPSB-C-52-5.pdf 725499 Mime.822 6038900 Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed

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BVY 05-072 Docket No. 50-271 Exhibit SPSB-C-52-6 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No.'30 Extended Power Uprate Response to Request for Additional Information Operation Procedure OP- 2192, Rev. 31 Total number of pages in this Exhibit I (excludina this cover sheet) is 5.

VERMONT YANKEE NUCLEAR POWER STATION OPERATING PROCEDURE OP 2192 REVISION 31 HEATING. VENTILATING. AND AIR CONDITIONING SYSTEM USE CLASSIFICATION: REFERENCE I RESPONSIBLE PROCEDURE OWNER: Manager, Operations REQUIRED REVIEWS Ycs/No E-Plan 10CFR50.54( ) No I Security Probable Risk Analysis (PRA)

Reactivity Management IOCFR5O.54(p)

I No No No LPC Effective l Affected Pages

-No. Date 1 10/26/04 App A Pg 15 of 24 2 11/16/04 51 & ADDED 51A of 62 3 01/22/05 60 of 62 4 05/26/05 29 of 62 IImplementation Statement: N/A Issue Date: 07/06/2004 OP 2192 Rev. 31 Page 1 of 62

TABLE OF CONTE'NTS PURPOSE.3 DISCUSSION ~~..........................3 DISCUSSION.3 ATTACHMENTS. 6 QA REQUIREMENTS CROSS REFERENCE ................................. 6 REFERENCES AND COMMITMENTS. 7 PRECAUTIONSIUMITTATIONS. 9 PREREQUISITES ...................... 11 PROCEDURE ............ .12 Startup, Shutdown and Transfer of Service Building HVAC ................................................... 12 Startup, Shutdown and Transfer of Turbine Building HVAC ................................................... 15 Startup, Shutdown and Transfer of Reactor Building 1VAC ................................................... 25 Startup, Shutdown and Transfer of Radwaste Building HVAC .................................................... 31 Startup and Shutdown of Intake Structure HVAC .................................................... 33 Startup and Shutdown of Discharge Structure HVAC: .................................................... 34 Startup and Shutdown of Switchyard House IVAC ................................................... 34 Startup and Shutdown of Steam Heat HVAC ................................................... 37 Startup, Shutdown and Transfer of Advanced Off Gas Building HVAC .......................................... 38 Operation of Control Room and Cable Vault Battery Room HVAC ................................................ 42 Operation of Chiller Units SCH-1 and 2 ................................................... 44 Cross-Connecting SAC-1 and 2 Chilled Water Systems ................................................... 46 Startup and Shutdown of UPS-2A-AC1 HVAC ................................................... 48 John Deere Diesel Generator Ventilation Controls .................................................... 50 Startup and Shutdown of Turbine Deck Office HVAC .................................................... 51 Startup and Shutdown of Switchgear Room HVAC ................................................... 52 Loss of Control Room Ventilation (UND98080) ................................................... 53 Local Manual Operation of EDG Room A(B) Exhaust Fan TEF-2(3) (Use VYOPF 2192.01) (ER990738_01) ................................................... 53 Startup and Shutdown of Steam Heat to the CST ................................................... 55 SCH-1-1 and SCH-1-2 Reset After Low Pressure Trip ................................................... 56 Temporary Space Heating ...................... 57 FINAL CONDITIONS . 62 OP 2192 Rev. 31 Page 2 of 62

The Turbine Lube Oil Room fire dampers are controlled by a local hand switch located outside the Lube Oil Room door.

The air is exhausted to the atmosphere by wall exhaust fans, roof exhaust fans or through the station stack. Several areas, such as the Control Room and office spaces recirculate air on a continuous cycle.

The system serving the Control Room is designed to provide cooling during the summer and heating during the winter. Air is circulated through a chilled water cooling coil, steam preheat coil, a steam reheat coil and ductwork by one of two system fans. Fresh air is normally drawn into the system mixing with the recirculated flow. A humidistat, on the west hallway wall in the first fan room, controls the relative humidity between 20% and 50% with a humidifier located in SRHC-1. It is operated with instrument air and controls humidity by spraying steam into the air flow. Two exhaust fans in the North wall of the Control Room, kitchen and rest room, serve to exhaust these rooms. The "Control Room H and V" switch on CRP 9-25 is provided to allow the operator to isolate the Control Room and Computer Room by closing the fresh air dampers and the Control Room kitchen and bathroom exhaust vents during off normal conditions. This is accomplished by moving the switch from "NORMAL" to "EMER". If a report was received of a toxic gas release which could affect Control Room personnel, the operators would don the self-contained breathing apparatus located in the Control Room. If Co om cooling is completely lost, emergency cooling can be initiated using portable smoke ejetrs (ND800 The Control Room and Service Building chilled water cooling coils are located in the SAC-1 and SAC-2 supply fan housings respectively. The cooling coils are cooled by dual compressor refrigeration units SCH-1 and 2 that cycle as necessary to maintain chilled water temperature. Demineralized water from the chilled water pumps circulates through the chiller heat exchanger and gives off its heat to the chiller units. The cooled water passes from the chiller units to the cooling coils. The amount of chilled water flowing into the cooling coils is controlled by the mixing valves. Each mixing valve is controlled by a thermostat that senses supply air temperature. The Services Building chilled water piping system can be valved into the Control Room HVAC because both the NNS piping system and the current SC3 piping system, respectively, were designed and built to the same specifications (i.e., non-seismic), therefore, failure mechanism(s) are the same for each system. In addition, isolation of the NNS and SC3 systems can be accomplished because the valves are in a mild environment area. Continued operation of the Control Room HVAC by valving in the Service Building HVAC to supply chilled water is consistent with the Safety Class Manual and the HVAC DBD.

Air for air compressor cooling is drawn through a wall louver located in the outside wall.

This louver also supplies any required room ventilation air. Discharge dampers which exhaust into the room are located on the air compressor discharge duct to allow for air recirculation.

Two oil-fired steam boilers supply steam for the heating coils and some of the unit heaters. Other unit heaters are run electrically.

All RRUs and TRUs utilize service water as the cooling medium except the drywell RRU-1 through RRU-4 which use RBCCW. (M00ID9502_14)

OP 2192 Rev. 31 Page 4 of 62

7. For minimum ECCS RRU comer room support operation, RRU 7 must be operable for the Northeast corner room and RRU 8 must be operable for the Southeast corner room.

RRUs 7 and 8 can be removed from service for maintenance and the associated Core Spray Pump/RIIR Pump may remain operable. Refer to OP 2181, Service Water/Alternate Cooling Operating Procedure, Precautions and Limitations, for administrative requirements and actions necessary to maintain operability.

8. SP-1, SCH-1 and SAC-1 supply air conditioning for the Control Room. This is a Safety Class 3 system and requires special consideration for its timely repair.

9. To prevent the possibility of reverse air flow, building ventilation should be secured in the following order:

a. Radwaste Building

b. Turbine Building

c. Reactor Building

d. Service Building

10. Minimize the time that TEF-2/3 are operated in manual. The UFSAR specified minimum Turbine Building design temperature, which includes the DG rooms, is 500 F and the AS-2 battery load calculation assumes an electrolyte temperature of 50 0 F.

(ER960055-01)

11. Securing TRU-5 with the condensate pumps running will result in a condensate pump bearing temperature rise. Planned maintenance on TRU-5 should be coordinated such that the time the unit is out of service is minimized.

12. Control Room temperatures in excess of 780 F are indicative of a need for corrective action. Corrective actions need to be completed prior to exceeding 95°F to ensure the l Control Room does not reach 120°F (upper temperature operability limit for Control/

Roo intruentation). (UND98080)

13. HS-139 and HS-140 in the Reactor Building must remain locked closed during plant operation due to House Heating Steam, High Energy Line Break concerns. These valves may only be opened with the permission of the Design Engineering Department.

(ER96-0482, TAGREVIEW_9703-26)

14. The Main Station Battery Room must be maintained at >60 0 F. The main station battery load calculations are based upon this minimum temperature.

15. One of the two standby gas treatment trains should be placed in service whenever normal Reactor Building ventilation is secured.

16. In order to meet environmental qualification program requirements, the RCIC room fan or alternate ventilation from the Reactor Building must be operable and the RCIC room temperature must be less than 1120 F. However, to satisfy station blackout analysis, the RCIC Room temperature must be maintained less than 1040 F. (EPCQ9504)

OP 2192 Rev.31 Page 10 of 62

2. Shutdown

a. Secure the WestS 'te gearRoom exhaust fan SWGR-EF-1A.

b. if erature cannot be maintained in the required range, notify the Operations Manager of the need to initiate actions to provide supplemental Q. Loss of Control Room Ventilation (UND98080)

)1. If a loss of normal Control Room ventilation occurs, refer to Section J and place SAC-lB in service.'

2. If Control Room cooling is lost, perform applicable action:

a. Refer to Section L and cross-connect chilled water from the Service Building to the Control Room.

b. Perform the following:

1) In the Control Room back panel area, remove 11 full size ceiling tiles.

2) Open Control Room panel doors.

3) Notify Security and Shift Engineer that Control Room doors will be opened.

4) Open Control Room doors.

5) Using two smoke ejectors or other portable cooling equipment to create temporary air flow paths, ventilate Control Room.

6) Imiplement the administrative requirements of AP 0077.

R. Local Manual Operation of EDG Room A(B) Exhaust Fan TEF-2(3) (Use VYOPF 2192.01) (ER990738_01)

1. Ensure the selected EDG Room temperature i2-0o[RATS-IA(B)].

2. Obtain Shift Manager pernssior local manual operation of TEF-2(3).

3. Obtain key D

4. ti a dedicated Auxiliary Operator at the selected Diesel Generator Room area.

OP 2192 Rev. 31 Page 53 of 62

BVY 05-072 Docket No. 50-271 Exhibit SPSB-C-52-4 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 30 Extended Power Uprate Response to Request for Additional Information Calculation VYC-2405, Rev.0 Total number of pages in this Exhibit (excludina this cover sheet) is 85.

CALCULATION COVER PAGE

[f IP-2 ElIP-3 0JAF EIPNPS 3 VY CluainN. Delis re'vision incorporates the following MERLIN VYC-2405 Rev. 0 DRNs or Minor Calc Changes: Sheet 1 of 85

Title:

Drywall Temperature Calculation for a Station ZQR ONQR Blackout Event at Extended Power Uprate.

Discipline: Fluid Systems Design Engineering Design Basis Calculation? ZYes ONo This calculation supersedes/voids calculation: N/A Modification NoJIask No/ER No: EPU El No software used 0 Software used and filed separately (Include Computer Run Summary Sheet).

If "YES', Code: GOTHIC V7.0p2 a] Software used and filed with this calculation. If "YES', Code:

System NolName:

Component NoJName:

(Attach additional pages if necessary)

PrintlSign REV # STATUS PREPARER REVIEWER/ OThER APPROVER DATE (Prel, Pend, DESIGN REVIEWER/

A,V,S) VEREFIER DESIGN VERIFIER o Prelim Liliane Alan L. James G.

Schor Robertshaw NA Roget I Sll~l05 7/3-a1- 0 CALcULATION COVER PAGE ENN-DC-126 REV.

ENN-DC-126 ATTACHMENT 9.2 REV.A4 ATTACHMENT 9.2 CALCULATION COVER PAGE

7Entergy Calculation VYC-2405 Rev. 0 Page 2 of 85 :

ENN-DC-126 REV. 4 ATTACHMENT 9.6 CALCULATION RECORD OF REVISIONS RECORD OF REVISIONS Calculation Number: VYC-2405 Rev 0 Page 2 of 85 Drywell Temperature Calculation for a Station Blackout Event at Extended Power Uprate.

Revision No. Description of Change Reason For Change 0 Original Issue N/A

!Entergy Calculation VYC-2405 Rev. 0 Page 3 of 85 -:

ENN-DC-126 REV. 4 ATTACHMENT 9.4 CALCULATION

SUMMARY

PAGE CALCULATION

SUMMARY

PAGE Calculation No. VYC-2405 . Revision No.0 Drywell Temperature Calculation for a Station Blackout Event at Extended Power Uprate.

CALCULATION OBJECTIVE:

This calculation will address the VY drywell temperature for Station Blackout (SBO) at Extended Power Uprate (EPU) Conditions. The calculation will look into means to mitigate the drywell temperature for this event, such that there will be no need for Emergency Depressurization.

CONCLUSIONS:

See Section 7.0 ASSUMPTIONS:

See Assumption in Section 4.0. (see also list of open items - assumptions which need verification or implementation - Section 4.1)

DESIGN INPUT DOCUMENTS:

See Design Input Documents identified in References Section 8.0 AFFECTED DOCUMENTS:

See Assumption Section, Section 4.2 METHODOLOGY:

See Section 3.0

Entergy Calculation VYC-2405 Rev. 0 Page 4 of 85 w TABLE OF CONTENTS Cover Sheet (ENN-DC-126 Attachment 9.2) ................................................................. 1 Record of Revisions (ENN-DC-126 Attachment 9.6) .................................................................. 2 Calculation Sununary Page (ENN-DC-126 Attachment 9.4) .......................................................... 3 Table of Contents .......................................... 4 List of Effective Pages (ENN-DC-126 Attachment 9.15) .......................... .............. 5 1.0 Background .6 2.0 Purpose ...................... 6 3.0 Method of Analysis .7 4.0 Inputs and Assumptions .7 5.0 Input and Design Criteria .................. ; 15 6.0 Calculation / Analyses ................... ;26 7.0 Results and Conclusions ................... ; 67 8.0 References ............... .. 68 Computer Run Summary Sheet (ENN-DC-126 Attachment 9.10).71 Calculation Impact Review Page (ENN-DC-126 Attachment 9.7) ........................................ 72 Calculation Design Verification and Review (ENN-DC-134) .............................................. 77 Files on CD .............................................. 85 Attachments Attachment Al - A39 TOTAL NUMBER OF PAGE (Including Attachments).124

antEntergy . Calculation VYC-2405 Rev. 0 Page 5 of 85 <L ATTACHMENT 9.15 LIST OF EFFECTIVE PAGES LIST OF EFFECTIVE PAGES p.

Calculation Number. VYC-2405 . Revision Number: 0 Page 5 of 85 Torus Temperature Calculation for a Station Blackout Event at Extended Power Uprate.

PAGE REV. PAGE REV. PAGE REV.

All 0

-Entergy Calculation VYC-2405 Rev. 0 Page 6 of 85

1.0 Background

The Station Blackout (SBO) torus temperature calculation (Reference 1) accommodated a higher coping timne of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months versus 10 minutes previously assumed. In addition to an increased coping time, Reference 1 also eliminated the potential need for Containment Overpressure (COP) for the SBO event. In the process, it was determined that in order to implement coping strategies for the two hours, two additional parameters need to be analyzed:

- Drywell temperature and the coping strategy to accommodate an expected higher drywell temperature, and

- Procedural direction for the operators (if needed) to limit the drywell temperature while ensuring capability of HPCI/RCIC to maintain vessel level 2.0 Purpose This calculation will address the VY drywell temperature for. Station Blackout (SBO) at Extended Power Uprate (EPU) Conditions. The calculation will look into means to reduce the drywell temperature for this event, such that there will be no need for Reactor Pressure Vessel Emergency Depressurization (RPVED - Reference 30).

This analysis will address control of the drywell temperature by controlled depressurization (cooldown) and will show that RCIC/HPCI injection is maintained until power is restored and the low pressure pumps (RHR and CS) are available.

As indicated in Section 1.0 of Reference 1, for the SBO event, the Alternate AC (AAC) power source is restored at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months into the event. After the restoration of power, torus cooling and drywell spray will become available.

2.1 Acceptance Criteria To evaluate the results the following criteria are applied:

1. The maximum allowable drywell bulk average temperature should remain below the EQ temperature (340'F for the first 30 minutes and 325TF for the next 270 minutes)

(Reference 19).

2. The maximum allowable drywell surface temperature is 281 0F (Reference 20).

3. The maximum allowable drywell air pressure is 56 psig, (Reference 27).

4 Maintain the torus pressure below PSP curve (Reference 30) during the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months coping duration and the 10 minutes of low pressure pumps restoration period.

5. The analyses should provide assurance that there is no need to spray the drywell in the unsafe region of the DWSIL curve (Reference 30).

Enterg Calculation VYC-2405 Rev. 0 Page 7 of 85 3.0 Method of Analysis The model developed in Reference 1 is modified to accommodate changes related to the purpose described ill Section 2.

The GOTHIC code (Reference 7), Version 7.Op2 has been selected for use in this analysis. This code was used in the original suppression pool temperature calculation (Reference 6) and in the analysis for SBO at EPU conditions, Reference 1. This specific version of the code has been installed and complies with the ENVY SQA procedures ENN-IT-104 (it replaced VY procedure AP-6030) as documented in calculation VYC-2208 (Reference 8).

The following changes to the input SBO-NoLeak-80 to produce SBO-drywell2 are being added:

- drywell heat load

- drywell heat slabs

- leakage from drywell to wetwell

- modifications to the vacuum breaker modeling The GOTHIC input file for the case SBO-dryivell2 is presented in attachment A.

4.0 Inputs and Assumptions The inputs and assumptions for the SBO event were developed in Reference 1. For completeness, they are added to this calculation. The more important modifications to the model have been made, for this analysis, by the addition of the Drywell Heat Loads and Drywvell Heat Slabs (see Section 5.0 for details).

The SBO scenario postulates a complete loss of onsite and offsite AC power. The vessel is assumed to be isolated at the start of the event.

The scenario is modeled as follows:

1) Scram occurs at time zero.

2) The MSIVs are isolated at time zero (this is a conservative assumption for the drywell temperature calculation since the energy transferred to the condenser while the MSIVs are opened will remain in the vessel).

3) The Reactor Vessel level is maintained with HPCI or RCIC in a band between 127-177 inches above Top of Active Fuel (TAF). Level is maintained with HPCI at a nominal flow of 4250 gpm. In reality HPCI flow will be adjusted to keep level in the band and to prevent excessive start/stop cycles. The HPCI (or RCIC) modeling in the GOTHIC input as a continuous flow (lower flow) or as intermittent flow has no effect on the drywell temperature analysis results.

The choice of RCIC or HPCI or the flow capacity has no effect on the analysis since HPCI injects intermittently to maintain inventory or can be throttled as required to maintain level.

If RCIC were used, it would inject more often.

--Enegy Calculation VYC-2405 Rev. 0 Page 8 of 85 -N-

4) HPCI takes suction from CST at 135)F. The CST inventory available for injection is 75000 gal.

The GOTHIC input value in Ibm = 75000 gals

1 ft3 n.48 gals /0.01627 Ibm/ft 3 (Reference 31 for the density a 135 °F) = 616271.7 Ibm

5) Power is restored at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Torus cooling is initiated at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes. Two RHR Service Water pumps are available at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes, -delivering 4700 gpm. The second RHRSW pump is discontinued at 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in the transient to maintain the Corner Room temperatures below the EQ limit (Reference 1, Attachment B). The drywell temperature analysis is performed for only 25000 seconds for the base case and for 14400 (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) seconds for the sensitivity cases since, after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes (7800 seconds),

the low pressure pumps are available to spray the drywell, if needed, hence there is no need to analyze the drywell temperature for a longer duration.

6) An orderly reactor cooldown is initiated at one hour in order to maintain the drywell temperature below the EQ limit (Reference 19) and the drywell shell metal below 281 °F (Reference 20). Two cooldown rates will be analyzed: 80 0 F/hr and 45OF1hr.

7) The RPV level is controlled by HPCI until the CST is depleted or HPCI shutoff pressure is reached. When the pressure permissive is reached, one Core Spray pump starts (after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes) to inject into the vessel . After the level is recovered in the normal range, the Core Spray system is used to maintain the level with the vessel pressure being controlled by an SRV cycling between 50 and 100 psig. The suppression pool is cooled continuously by the RHR system. The reactor vessel is maintained in this configuration. The RHR pump in torus cooling is also available for drywell spray after 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes.

8) The HPCI turbine takes steam from the vessel to provide its motive power. It returns the exhaust steam to the torus. The steam to the turbine is not modeled since the model assumes SRV opening and closing to maintain pressure. Any steam not removed by the HPCI turbine will be removed through the SRV to maintain a certain pressure. The total flow through the SRV is increased, but the details of SRV flow are not important for this applications and the two (SRV flow and HPCI turbine) can be combined for model simplicity.

9) The liquid leak is modeled as a fixed flow of 8.4585 lb/sec (61 gpm, Reference 3) [(61 gpm

/60 s/min n.4805 gal/ft 3 /0.0161 ft3 /lb = 8.4585 lb/sec)] and it stays on for the entire transient. (Analyses will be performed with and without leak for one depressurization (cooldown) rate: 80 TF/hour). In reality, the leak is variable depending on pressure. Assuming a density of 62 lb/ft3 and fixed flow is conservative for the drywell temperature analysis.

-Analysis. of drywell temperature for a 45 "F/hour cooldown with no RPV leakage was not performed because for the case .with 80 "F/hr cooldown, for the period of interest the drywell temperature stays below -300 "F for both cases (with and without RPV Leakage). For the 45 OF/hour cooldown, the tenfperature in the drywell for the no-leak case is expected to remain below 300 "F as in the 45 TF/hour cooldown case with RPV leakage for the analysis duration.

-Entergy Calculation VYC-2405 Rev. .0 Page 9 of 85'

10) The analysis will assume a fouling of 0.0018 in the tubes and 0.0005 in the shell. This corresponds to an overall RHR Heat Exchanger (RHRHX) fouling of:

d R =Rfi(-2 -)+Rf ff where:

2 Rri and Rfo = tube and shell fouling factors, respectively (hr-ftO-FJBtu) do = outside tube diameter (in) di= inside tube diameter (in) do = 0.625 in (Reference 22) di= 0.527 in (Reference 22) 2 Rf, = 0.0005 hr-fte-F/Btu (Reference 22) 2 Rfi = 0.0018 hr-ft -OF/Btu (from 0.0020)

Overall RHRHX fouling 0.625 R= 0.0018 *( ) + 0.0005= 0.0026 0.527 This number compares well with the maximum fouling calculated in Reference 23 of 0.002307 and 0.002445 for the RHR HX E14- I A and RHR HX E-14-1 B, respectively.

11) A variable SW temperature is used, consistent with Reference 1.

Since this change of depressurization (cooldown) function of service water temperature requires procedure changesjit is added in Section 4.1 as an unverified Assumption.

- For SW> 750F, depressurize the vessel at 800 F/hr or higher.

- For lower SW temperature (SW S 75TF no restrictions on depressurization) rates.

12) - Various assumptions made concerning the added Heat Conductors:

- The heat load decreases linearly when the temperature difference between RPV and drywell becomes smaller.

- For all conductors, only heat conduction is conservatively assumed in the air and concrete layers.

- The outer surface boundary condition is conservatively assumed to be adiabatic (i.e., the heat transfer coefficient is set to zero)

-Entergy Calculation VYC-2405 Rev. 0 Page 10 of 85 "

Table 1 - Vessel and Core Initial Conditions and Parameters, Primary Variables Parametey Nominal Analysis Basis Value Value Initial Reactor Power 1912 Mwth 1950 MWth 100% power +2 % uncertainty (per NEI-87-001, SBO can be performed at 100%

power, however this analysis used 102%

power, consistent with CLTP and the Reference I analysis).

Core Decay Heat ANS 5.1 ANS 5.1 +2 o ANS 5. 11979 standard+2 es uncertainty

-(Reference 24)

MSIV closure time 3.0-5.0 sec 0.0 sec (MSIVs Minimum value allowed retains the not modeled) maximum energy in the vessel.

RPV Pressure 1015-1025 psia 1045.2 psia Higher value, conservative, maximizes (Reference 28) the vessel energy.

Initial Vessel Level 162 inches 172 inches Analysis value conservatively accounts for 3 inches increase above normal (uncertainty and operational fluctuations) and 7 inches for dimensional uncertainties. These assumptions are LOCA assumptions and are judged

._ conservative for SBO.

Core Flow Rate 48.0E6 lb/hr 51.36e6 lb/hr Includes lCF of 7%.

Initial Feedwater FlowxTate 7.876e6 lb/hr 8.076e6 lb/hr Reference 25 (T 2003-20)

Initial feedwater 393.5-393.6 OF 393.9 OF See discussion in Reference 25.

temperature Feedwater is tripped at time .0, due to SBO. The feedwater is used only for the steady state initialization.

SRV Cycling 1080-1047.6 psi 1080-1047.6 psi The setpoints for the SRVs are nominal.

(between RPV (between RPV No additional as found allowable of 3% is and Drywell) and Drywell) added since it will have no effect on the drywell temperature since the. SRVs open to remove the decay heat and, until the depressurization starts, indifferent of setpoints, the SRVs will cycle to remove the decay heat.

The operators will take manual control of the SRV and will cycle between 800 and 1000 psig (EOP Reference 37) to reduce the numbers of times the valves cycle. There is no effect on the calculation since the valves in any operational mode will open to remove decay heat.

Vessel Leak 61 gpm 61 gpm A constant 61 gpm leakage is assumed; (Reference 3). The analysis will be performed with & without leakage, since the drywell temperature will have a different profile for the cases with no leakage.

A-Entergy

Calculation VYC-2405 Rev. 0 Page 11 of 85 A-Table 2- ECCS Initial Conditions and Parameters Parameter Nominal Analysis Value Basis Comments HPCI flow rate 4250 gpm 4250 gpm Tech Spec Flow Since the flow is intermittent there is (Reference 2) no need to use the min flow of 3570 gpm (uncertainty added) (References 2 and 5). In reality the HPCI flow will be adjusted to maintain level to prevent excessive pump stop/start.

HPCI pressure 1135-165 psia 1135-165 psia Reference 5 and 27. HPCI is shut off range if vessel pressure drops below 165 psia.

CST Temperature 120 135 OF OPEN Item CST available 75000 gallons 75000 gallons Available CST Per Reference 3, the Tech Spec value inventory (VY Tech inventory for HPCI can be used.

Spec - injection An administrative limit for the CST Reference 2) level of 25% is required.

Core Spray Flow Curve of flow Same as The core spray The Core Spray System will be used vs. vessel- nominal. flow rate used in for level control only after the CST is torus AP. the SBO analysis depleted and/or the low pressure is of Reference I will reached.

be used. The flow rate is determined OPL4 -Reference 5 as a function of the vessel-torus AP.

(consistent with the LOCA analysis)

RHR Flow 7000 gpm 6400gpm 6400gpm used in Consistent with Reference I (t=7800 seconds) analyses limiting case and Reference 5.

RHR Hx Fouling 0.0005 shell, 0.0005 shell, Assumption input #10, supported by 0.0018 tube 0.0018 tube . Reference 23.

RHR Hx Tube N/A' 5% Allowable Design value providing margin above Plugging plugging margin the current plugging value of 3.6%

RHRSW Flow 4700 4700 gpm (2 4700 gpm (Reference 4)

RHRSW pumps) 4700gpm =

650.98 lb/sec (at 85° F)

RHRSW Inlet 32-85 F Variable, see If SW is > 75 OF, Maximum Allowable Service Water Temperature assumptions, depressurize the Temperature (Reference 2) only for based on RPV with rates 80 depressurization rates > 80 CF/hr depressurization CF/hr or higher. For lower depressurization rates the (cooldown) rate SW has to be below 75 'F. This requirement is derived from the torus temperature calculation (Reference 1). The rate of depressurization was shown in this calculation to have minimal impact on the strategies to control the drywell temperature for SBO.

By

Entergy Calculation VYC-2405 Rev. 0 Page 12 of 85 Hi Table 3- Primary Containment Initial Conditions and Parameters Parameter Nominal Value Analysis Basis Comments Value Drywell 110-170 OF 170 OF Reference 5 The highest drywell Temperature temperature is used.

Drywell Pressure 16.4 psia 16.4 psia VY Tech Spec (Reference 2)

Wetwell 88 OF 90 0F Maximum Tech Spec A 2. 0F uncertainty is applied Temperature Value (Reference 2) via procedure to account for instrument uncertainty (Reference 26)

Wetwell Pressure 14.7 psia 14.7 psia Normal Torus operating pressure (vented to atmosphere via Standby Gas Treatment System)

Drywell Humidity 20 -100 % 100% (base Nominal Values: Use maximum drywell case) VY UFSAR humidity consistent with (Reference 27) Reference I for the base Sensitivity case. Sensitivities performed at performed at 20% drywell 20% humidity humidity.

Wetwell Humidity 100% 100% Nominal Values: Minimal to no impact on the VY UFSAR SBO drywell temperature.

(Reference 27)

Wetwell Water 6 68000 ft4 Minimum Tech.

Volume Spec. Value (Reference 2)

Drywell free 128,370 -131,470 131,470 ft4 Reference 5 The maximum value in volume ft3 (includes OPL4A is used for vents) Consistent with SBLOCA, IBLOCA and Reference 6, the Small Steam Breaks.

The values volume of the Vents: 16703 f 2 (VYC-proposed are drywell side of the 2306 -Reference 32) consistent with torus-drywell vacuum OPL4A breakers of 372.3 ft3 Total Drywell Volume =

will be added to the 131470 - Vents Volume +

proposed value. Drywell side of Vacuum Breakers = 131470 -16703 +

372.3 - 115139.3 ft3 Wetwell free For the minimum Nominal Reference 5 The value at Dp>0 of volume water level of Values used. 105,932.0 ft3 is used for a

'A Entergy P 1o-Calculation VYC-2405 Rev. 0 *Page13of 85 ; :

Parameter Nominal Value Analysis Basis Comments Value 68000 ft3, the Consistent with total volume of 105,932 +

wetwell free The values Reference 6, the 68,000 = 173932 ft3 volume is proposed are volumes of the 107,104.8 ft3 for consistent with drywell side of the Used in calculation: 173932 Dp =0.0 and . OPL-4A torus-drywell vacuum + 99.4 = 174031.4 ft2 105,932.0 for breakers of 99.4 ft3 Dp>0.0 where Dp will be added the

-is the pressure proposed value.

difference between drywell and torus.

Vacuum Breakers- 0.5 psi 0.5 psi 0.5 psi Reference 2 pressure difference between wetwell and drywell for vacuum breakers to be fully open .

Drywell-to Max allowable Base case Reference 5 for the max Wetwell Bypass area =0.12 ft2 =0.12 ft2 leakage, Reference 33 for Leakage Tech Spec Allowable

. Tech Spec Allowable Sensitivity

=0.0033 V2 . =0.0033 ft2

- - - - 4 :-

'~Entergy. Calculation VYC-2405 Rev. 0 Page 14 of 85 '

4.1- Assumptions that need Verification or Implementation

1) Two (2) hour restoration of outside power (coping time).

2) To.(10) minutes to start RHR flow through the RHRHX, and the use of 2 RHRSW pumps and CS.

3) Acceptability of using 75000 gal from CST (change of level setpoint).

4) Maximum CST temperature of 1352F.

5) The depressurization rate function of Service Water temperature needs to be verified and proceduralized as follows:

For SW> 75'F;. depressurize the vessel at 80°F/hr or higher.

- For lower SW temperature (SW < 75°) no restrictions on cooldown rates.

4.2 Affected Documents

1) DBD - for Residual Heat Removal - change the maximum tube side fouling resistance 2

from 0.002 hr-fte-F/Btu to 0.0018 hr-ft2e-F/Btu as well as the total fouling.

2) Change the description of the SBO event in the DBD for Safety'Analysis.

3) Change all DBDs and documents that address the SBO coping time (identify and modify).

4) Change DBD Containment Pressure Suppression System to incorporate results of this calculation.

5) Review following documents for need of modification: VY UFSAR, and PUSAR.

6) Modify SBO procedure (OT-3122-Reference 36) to incorporate cooldown at one hour and provide guidance to the operators such that RPVED is precluded based on the results of this calculation.

Note: Section 4.1. & 4.2 items are being tracked via LO.VTYLO-2005-00135.

-Entergy. Calculation VYC-2405 Rev. 0 ' Page 15 of 85 :

5.0 Input and Design Criteria The GOTHI-JC input from Reference I is modified to implement the features described in this section. The modified input is called SBO-drywell2.

The main features added to the SBO model are the drywell heat load and drywell heat structures.

A schematic of the system modeled is presented in Figure 1 I

WDY Ub" wetI a *:

Figure 1 - VY Containment and the Associated Systems Note: only RCIC pump is shown in this simplified model. Actually, HPCI is assumed to inject.

'Entergy Calculation VYC-2405 Rev. 0 Page 16 of 85 5.1 Drywell Heat Load Calculation The Drywell Heat Load Summary at Current Licensed Thermal Power (CLTP) is summarized in Reference10. The total.amount of heat given to the drywell at CLTP is 1,691,300 Btulhr. The drywell heat load was recalculated in Reference 18 for the Extended Power Uprate (EPU) as 1,700,675 Btu/hr. Since the Extended Power Uprate is performed at constant pressure, only the feedwater pipe and valves will be at higher temperatures (Reference 18), hence a higher Q for this component; (124,000 Btulhr -Reference 10 versus 133,375 Btu/hr at EPU -Reference 18) is calculated.

The total power to the drywell for EPU is presented in Table 4.

Table 4 Drywell Heat Load (Reference 18)

Item Component Cooling Load No. (Btu/hr) 1 Reactor Vessel 459,000 2 Recirc. Pumps, Valves and Pipe 278,000 3 Feedwater Pipe & Valves 133,375 (EPU Modified-Reference 18) 4 Steam Pipe & Valves 212,000 5 Condensate & Instrument Lead Lines 82,000 6 Control Rod Drive Pipe 50,400 7 Clean-up Pipe & Valves 17,800 8 Shutdown Supply Pipe 8,100 9 Steam Safety/Relief Valves 206,600 10 Biological Shield (Gamma Heating) 16,400 11 . Safeguards System Piping 82,000 12 Steam Leak 155,000 Total 1,700,675 Btu/hr

'Entergy CalculationWYC-2405Rev.0 Pagef17of85 -

5.1.1 Drywell Load Modeling The drywell heat is modeled as two heater #5H and lt6H. The heater 5 represents the heat source which varies function of the liquid temperature in the vessel, while heater 6 represents the heat source which varies as a function of the vapor temperature in the vessel. See explanation of these two heaters in Section 5.1.2.

The heat loads which are exposed to the steam atmosphere (for Heater #6H) are:

Table 5 Heat Loads Exposed to Steam Item No. Component Cooling Load (Btu/hr) 1 30% of Reactor Vessel Heat Load 459,000*0.3 = 137700 4 Steam Pipe & Valves 212,000 9 Steam Safety/Relief Valves 206,600 12 Steam Leak 155,000 Total 711,300 The normal level is at about 0.3 of the total vessel height. From Reference 34 the distance from the 152 inches above TAF to the top of the vessel is 21.432 ft in the GOTHIC vessel model and to the vessel bottom is 41.193 ft.

The middle range of 152 inches is calculated as (177 inches + 127 inches)/2 = 152 inches.

The model assumes a normal level of 172 inches (Table 1) which is 20 inches above the 152 inches, hence from 172 inches above TAF to the top of the vessel there are -21.432 - 1.667 =

19.765 ft The liquid height = 41.193 + 1.667 42.86 ft Total GOTHIC vessel height = 62.625ft (from Reference 34 =330.542 - 267.917 =62.625 ft)

Steam region = 19.765 /62.625 = 0.31 (used 0.3)

Heater 6 load = 711300 /3600 = 197.58 Btu/sec Total Heat load = 1,700,675/3600 = 472.41 Btu/sec Thus, Heater 5 load = 472.41 - 197.58 = 274.83 Btu/sec

I

--:Entergy Calculation VYC-2405 Rev. 0 Page 18of 85 W 5.1.2 Transient Heat Load Behavior It is assumed that the heat load decreases linearly when the temperature difference between RPV and drywell becomes smaller. In order to calculate the transient heat load, the following transient heat load procedure is used

1. When the difference between the vessel temperature and the drywell temperature is less than or equal to zero, the power of the heat source is zero.

2. When the temperature difference is greater or equal with to Tset, the heater power will increase above the nominal value.

3. When a temperature difference exists between T.,,and zero, the power is linearly interpolated between the nominal value and 0.0.

Tsa is defined in the way that the calculated power of the heat source is equal to the nominal value at the beginning of the transient. Two GOTHIC control variable CV 41 and CV 42 are defined as the temperature difference between the vessel internal water temperature and the temperature inside the drywell (CV41) and between the vessel steam temperature 'and the temperature inside the drywell (CV42), respectively. The model shows higher steam ternperature than saturation because of the heat slab exposed to steam which represents the heat structures in the Reactor Pressure Vessel (RPV) exposed to a steam environment. Sensitivity studies which placed this heat structure in liquid eliminated the steam superheat, as expected. This is a conservatism of the model. In reality all structures will be exposed to Tsat = Tliq= Tvap The control variables are used as the independent variable of the functions, which gives the transient heat loads to the drywell, as described above.

5.2 Drywell Thermal Conductor Model Development The following thermal conductors are being added to the model.

There are several types of heat sinks and thermal conductors inside the drywell. The components included as heat sinks are the metal mass of 4 RRUs, vent pipes and the drywell liner.

Miscellaneous steel exists in the drywell, but has not been previously quantified in detail.

Minimum heat sink components are considered conservative; therefore, miscellaneous steel is not included as heat sinks.

Drywell liner divided in (Reference 21):

1) Lower Drywell spherical portion,

2) Upper Drywell cylindrical portion, and

3) Drywell head.

The drywell wall consists of the concrete, the inner surface steel plate and the air gap. Zero heat flux boundary condition on the outside surface of the drywell wall is used.

- - - - 1--'1;'.-!L! : . '4.

i- Entergy CalculationVWC-2405 Rev. 0 Page 19 of 85 The data on OPL-4A (Reference 5) is used to model the steel liner. The surface area calculation for the liner was performed in Reference 9.

9' Table 6 - Drywell Steel Liner Elevation Steel Thickness (in) Surface Area (ft2) GOTHIC Item #-from Ref. 9 thermal conductor No.

2, page 47 of Ref. 9 El. 237.74'-EI 1.0 page 47 of Ref 9 1856.24 5 257.75' 3,page 47 of Ref. 9 El. 247.24'-El 0.8125 page 51 of Ref 9 2041.28 6 257.75' 4.1, page 47,48 of Ref. 9 El. 257.75'-EI. 0.6875 page 51 of Ref 9 1250.47 9 259.92' 4.2, page 48 of Ref. 9 El. 259.92'-EI 0.6875 page 51 of Ref 9 3802.73 7 283.69' 5, page 48 of Ref. 9 El. 283.69'-EI. 2.5 page 51 of Ref 9 780.68 8 289.61' 6, page 48 of Ref. 9 El. 289.61'-El 0.635 page 51 of Ref 9 1898.24 10 308.00' 7, page 48,49 of Ref. 9 El. 308.00'- El 1.25 page 51 of Ref 9 1114.72 11 318.50' 8, page 49 of Ref. 9 El 318.50'- El 1.25 page 51 of Ref 9 783A 12 327.75' 9, page 49 of Ref. 9 El. 327.75'-top 1.3125 page 51 of Ref 9 1718.3 13

_ _ _ _ _ _ _ of drywell A _

Total 15246.06 ft' The items 2 through 7 have 0.0025 inches of paint per Reference 13 and Reference 9, Appendix VI (for properties) and a 2 inches thick air gap (Reference 14) and a conservative low thickness of concrete of 24 inches is used from Reference 21.

Item 8 (side of drywell head -small cylinder) is modeled, with a 2.5 ft air gap outside the steel wall and conservatively low thickness of 1.5 ft of concrete (scaled from Reference 21). The thermal conductor has an adiabatic heat transfer boundary condition. Only heat conduction is assumed in the air and concrete layers. This is conservative.

Item 9 (top of drywell head) is modeled with a 6.7ft air gap outside the steel wall and a conservative low thickness of 24 inches of concrete (part of the concrete plugs) - (scaled from Reference 21).

RRUs (References 11 and 12)

ARRU = 1272.8 ft2, thickness =0.125 inches (used in OPL-4A-Reference 12).

-En!ergy Calculation VYC-2405 Rev. 0 Page 20 of 85 - ;-;

Vent Pipes Vent pipes surface area A vent pips= 2885.7 ft2 , thickness =0.125 inches (used in OPL-4A-Reference 12)

NOTE: The total Surface Area of the steel components adds up to the value obtained from OPL-4a (i.e., Table 6 Total = 15246.06 ft2 , RRUs = 1272.8 ft2 , Vent Pipes = 2885.7 ft2 , thus Total = 19405 ft)

Total Surface area of Concrete Exposed to Drvwell Air Space The surface area of the pedestal is the only concrete component quantified in OPL-4A. The drywell floor is ignored because it may be covered with liquid and not directly exposed to the drywell airspace. Only the outer surface area of the pedestal was considered in OPL- 4A as well as Reference 9 because the inner surface has limited communication with, the drywell atmosphere. The biological shield wall (BSW) is a concrete structure surrounding the reactor pressure vessel and located above the reactor pedestal. Because of the proximity to the reactor pressure vessel the BSW is at a temperature greater than the drywell (DNV) ambient and thus a heat source (already incorporated into the drywell heater) and a heat sink only when its temperature drops below *the DW temperature. Because . of the uncertainty of the. BSW temperature and its limited value as a heat sink, the BSW is not considered here.

The OPL-4A value for the area is used and = 2068 ft2 (A value of 2108 ft2 was used in the model, addressed in Case 5).

Thickness of Concrete Exposed to Drvwell Air Space' From Reference 5 = 4ft.

Properties of Materials Table 7 - Thermo physical properties of Passive Heat Sink Materials (Reference 5)

Material Density (lbm/Wft) Specific Heat Thermal References (Btuflbm- 0F) Conductivity (Btu/hr-ft OF)

Carbon Steel 489.0 0.11 32 F 31.8 15 68T 31.2 2120 30.0 3920F 27.8 572OF 26.0 Concrete 145 0.156 0.92 16 Paint 288 0.2 0.125 9

Entergy Calculation VYC-2405 Revt. 0 Page 21 of 85" Air Thermal Properties From Reference 15.

T (1F) K,(Btulhr-ft-F) Cp (Btu/Ibm-°F) p(lbnlft3) 100 0.0157 0.24 0.07092 150 0.0167 0.241 0.06511 200 0.0181 0.241 0.06017 250 0.0192 0.242 0.05593 300 0.0203 0.243 0.05225 400 0.0225 0.245 0.04617 Heat Transfer Boundary Conditions On the inner surface of all the thermal conductors, the heat transfer coefficient is calculated by the GOTHIC code. The following options are used:

-Direct'Heat transfer Option.

-Summation of the condensation and convection heat transfer.

-Max of Uchida and Guido-Koestel condensation heat transfer option (sensitivity with Uchida for the limiting cases).

- Radiation heat transfer option is OFF for all heat structures with exception of the drywell-dome.(sensitivity with option OFF for the limiting case).

- The surface orientation is "FACE DOWN for the drywell dome", thermal conductor

13,and "VERT SURF' for heat conductors 5 through 12.

-All thermal conductors use 'VAP" option.

The outer surface boundary condition is conservatively assumed to be adiabatic. The heat transfer coefficient is set to zero.

5.3 GOTHIC Drivell SBO Model Development The following changes to the input SBO-NoLeak-80 (Reference 1) to produce SBO-drywell2 are being added:

- drywell heat load

- drywell heat slabs

- leakage from drywell to wetwell

- modifications to the vacuum breaker modeling The GOTHIC input is presented in Attachment A.

The GOTHIC model used for all cases is presented in Figure 2.

.. 71' - :

Entergy ., Calculation VYC-2405 ReV. 0

- Page 22 of 85 -

SBO - 8OF-Noleak-drywelli Mar/15/2005 14:09:56 7GOTHIC Version 7.0p2(QA) - April 2002

. File: /home/achor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2

- Long Tern Contaitent SmLOCA I I I BI I marnual C0014 loci Or T.CIC Figure 2 - GOTHIC SBO Model

iEntergy Calculationi VYC-2405 Rev. 0 Page 23 of 85 ;

Flow Paths

.Flow path 21 is added to model the vacuum breakers leakage path from the drywell air space to.

the wetwell air space. Per Reference 5, the maximum leakage area is 0.12 ft2 . The elevations and the height of this junction were elected to be the same as the vacuum breaker junction since the leakage is 'airound.the vacuum breakers.

The K reverse =K foward = 1.5 (expansion & contraction) (Reference 29)

Thermal Conductors Twelve new thermal conductors were added. The description of the thermal conductors was given in Section 5.2.

The temperatures of 11 of the thermal conductors were set at 160 TF, the pedestal thermal conductor is set at 152 'F. On page 73 of Reference 9 the average temperature for the middle and the top drywell node is calculated as 151.94 'F. Hence, the thermal conductors are set, conservatively at i 60 OF. The pedestal is in the lower drywell and middle drywell hence 152 'F is used (average for middle and top drywell is conservative). In Case 5, the temperatures of the heat slabs which represent the drywell wall were set at 170 'F (very conservative assumption).

Functions Two new functions are added Function 17 (FF17) represents the power to the drywell from the structures exposed to steam.

The function multiplies Q inita and represents (Tiquid - Tdzywci.)

The FF17 is:

AT (CV41)

-500 0

,0 0 380 1 380000 1000 The independent variable is the temperature difference between (Tliquid - Tdrywe 1u), CV4 1.

Function 18 is identical to the Function 17, but the independent variable is .CV42 (T vapor- TdiyweI1)

Tref = Initial Vessel temperature - Initial Drywell temperature = 5500 F -170TF =380 'F where 550 'F is the initial vessel temperature, and 170 'F is the initial drywell temperature. (550 is determined from the GOTHIC model at time zero and 170 'F is the maximum drywell temperature, OPL4A-Reference 5).

'Entergy - Calculatiorn VYC-2405 Rev. 0 Page 24 of 85 Valves A new valve (V5) was added to represent the vacuum breaker. It opens on trip 33 (0.5 psi difference between wetwell and drywell (Reference 2) and it closes on trip 34 (0.3 psi-arbitrary, since the vacuum breaker valves.reseat when the pressure difference becomes less than 0.5 psi. A quick close valve is used for this component since the valve will close as soon as the 0.5 psi difference between wetwell and drywell disappears.

The vacuum breaker valve is modeled as Valve Type 3, with an area of 17.6737 ft2 (Reference 9). Note: the area of the valve from Reference 9 is slightly larger than the area of the flow path in which it is located. The valve area will have minimal impact on this analysis because the flow is limited by the area of the flow path. The area of the valve was changed to the area of the flow path in the final case analyzed, Case 5.

Materials Four new materials are added. The properties for the new materials are described in Section 5.2.

Trips and Controls Trip 18 is modified to ADS when the vessel pressure difference between RPV and drywell is lower than 100 psi instead of 50 psi in the original model. This trip is not used, however, the SRV valves will open at a AP of 100 psi, not 50 psi .

Trip 21 is modified to start depressurization (cooldown) at one hour (3600 seconds) in order to limit the drywell temperatures.

Trips 33 and 34 are added to open the vacuum breakers valves at 0.5 psi pressure difference between wetwell and drywell (trip 33) and close it on a AP of 0.3 psi.

Coolers & Heaters Two new heaters are added, 5H and 6H to model the vessel heat to the drywell. These heaters are described in Section 5.1.

For heater 5H the heat rate of 274.83 is multiplied by the FI 17, while for heater 6H the heat rate of 1997.58 is multiplied by FF 18.

Entergy Calculation VYC-2405'Rev. 0 Page 25 of 85 Heat Transfer Coefficients Types Two heat transfer coefficients are added.

The following options are used:

-Direct Heat transfer Option.

-Summation of the condensation and convection heat transfer.

-Max of Uchida and Guido-Koestel condensation heat transfer option (sensitivity with Uchida for the limiting cases).

- Radiation heat transfer option is OFF for heat transfer coefficient type 6.

- Radiation heat transfer option is ON for heat transfer coefficient type 7.

The use of the radiation option has no effect on the results at these low temperatures

- The surface orientation is "VERT SURF' for heat transfer coefficient type 6.

- The surface orientation is "FACE DOWN for the drywell dome", heat transfer coefficient type 7.

The use of the surface orientation is appropriate since this is the thermal conductor physical arrangement.

-The heat transfer coefficient types 6 and 7 use 'VAP" option since this is the drywell medium.

-Convection bulk T model: Tg-Tf. The bulk temperature is the calculated vapor temperature. Tf is the maximum between the calculated wall temperature and the calculated saturation temperature.

- Condensation heat transfer Bulk T Model : Tb -Tw used. Tb is the minimum between the calculated vapor temperature and the calculated saturation temperature.

Control Variables Two control variables are added, 41 and 42 they represent the AT between Tliq in RPV and TV drywell and between Tvap in RPV and Tv drywell, respectively. See Section 5.1.2 for additional information on the operation of these Control Variables.

-Entergy. Calculation VYC-2405 Rev. 0 Page 26 of 85 6.0 Calculation / Analyses Five (5) cases are analyzed:

Case 1 is called SBO-drywell2. It is the base deck, developed from Reference I and described in Section 5.3. Case I assumes no RPV leakage, depressurization (cooldown) with a rate of 80 /F/houra 100% humidity and base deck inputs as described in Section 5.0.

Case 2 is called Case SBO-dryvell2-80-sensy2-NoLeak. Case 2 is identical to Case I with the change in humidity, changes in the leakage area and minor changes in the heat transfer type 6 and 7. Case 2 assumes 20% humidity and minor changes in the heat transfer type 6 and 7. These changes are described in Section 6.2.1.

Case 3 is identical to case SBO-drywveI2-80-sensy2-NoLeak but with leak. It is called SBO-dryivell2-Leak-80-sensy. These changes are described in Section 6.3.1.

Case 4 is called SBO-dryiell2-Leak45-sensy and is identical to Case 3 but with a slower depressurization (cooldown) rate. It assumes a depressurization of 45 0 Flhour with leak in order to show that with an early depressurization and slower cooldown rate the results are not changed and the drywell temperature is not impacted negatively by a slower cooldown. Consistent with Reference 1, the RHRSW temperature is changed to 75 'F.

Case 5 addresses changes found during documentation and as part of review. These changes are described in Section 6.4.1.

Case 5 is called SBO-drywell2-cornments. The following changes are made in Case 5 to address changes found during documentation and review:

. change the temperatures of the steel structures from 160 OF to 170 OF (very conservative assumption),

. change the K reverse for the Junction 3 from to 3.93 from 3.964,

set the V3 Valve with the same area as the junction, and

. change the area for the pedestal from 2108 ft2 to 2068 ft2, consistent with OPL-4A.

Case 5 changes are described in Section 6.5.1.

Entergy Calculation VYC-2405' R6V. 0 Page 27 6f95 6.1.1 SBO-drywell2 Model Development SBO-dryvell2 represents the base model for this calculation. The modification to the input are presented in Section 5.0 and the GOTHIC input deck is presented in Attachment A.

6.1.2 Case SBO drywell2 Results Figure 3 through Figure 11 present the main parameters for the base case SBO-drywell2. Figure 3 presents the drywell temperature. The drywell temperature increases to about 285 0 F after one hour. The heatup is arrested due to depressurization. At about 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months into the'transient the temperature in the drywell starts increasing due to lower heat removal into the passive heat sinks (walls). The maximum drywell temperature is 290 'F. The air gap acts as an insulation and the steel liner is almost at 245 'F. However, after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available so the operators can spray the drywell with the RHR pump, if needed. The results indicate that the temperatures in'the drywell stay below the EQ limit and the drywvell liner is well below the 281 'F for the SBO coping duration.

Figure 4 presents the containment pressure. Due to the higher leak area the drywell and the wetwell are at the same pressure. At about 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months the pressure in the drywell is too low to spray the drywell, (unsafe area of DWSIL(EOP-3 -Primary Containment Control -Reference 30))

however the pressure increases to about 6 psig at about 12000 seconds at which point the operators would able to spray the drywell with the RHR pump, if needed.

Figure 5 presents the RPV pressure. At one hour into the event it is assumed that the operators start depressurization (cooldown). The pressure drops to the HPCI shutoff pressure of 165 psia at about 12000 seconds. At that point only about 450000 lb were injected from CST (Figure 12). At this point the RPV is depressurized and the CS is available to inject.

Figure 7 presents the RPV level. The core stays covered. There is a dip in the no'rmal level at about 12000 seconds when HPCI stops injecting and CS pump has not yet injected. This is due to the fact that the CS pump was set to inject at 14000 seconds; however CS is ready to inject at 7800 seconds.

Figure 8, Figure 9, and Figure 10 presents the drywell liner temperature. The drywell liner stays below 260 'F for the 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months analyzed. After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available for suppression pool cooling, drywell spray and maintaining vessel inventory.

Figure 11 presents the suppression pool temperature. Since the vessel is depressurized early, the suppression pool temperature is below the maximum of 182.2 'F calculated in Reference 1, hence no containment overpressure is required.

~Entergy Calculation VYC-2405 Rev. 0 Page 28 of 85 .

SBO - 80P-Noleak-drywelll Mar/03/2005 13:28:01 GOTnIC Version 7.0p2(QA) - April 2002 File: /hone/schor/vyc-2120ccn/SENSITIVITY/SBD/drywell-SBO/SBO-drywell2 Drywall Temaperataxt TV] YLI, 1 vLI a!r ie jitat r

'iaI ryw : 1 4

. I3.1 7.2 1 U.@144 iS 26.2 2 .S 32.4

. .TIt (see) 9&21 11*1AOI IeJSflhI 2,41.4 _

Figure 3 Drywell Temperature Case SBO-drywell2 SBO - SOP-Noleak-drywelli Mar/03/2005 13:33:59 GOT8IC Version 7.0p2(QA) - April 2002 Pile: /bome/schor/vyc-2120ccn/SENSITIV I /SDO/drywell-SBO/SBO-drywe112 7 ~ Cm I-Mt vzttSS~

o- - - -I.

I 1.1 1 p.2 I~e Bs I 12 be i I ,

LLI :~ ILL :UC; 24 2S 32 J TIm. (Ste) srnn ?...2f"%g-,S/2.1S 114,41 -

Figure 4 Containment Pressure - case SBO-drywell2

Entergy Calculation VYC-2405 Rev. 0 Page 29 6f 85 SBO - SOF-Noleak-drywelll Mar/03/2005 13:29:48 GOTHIC Version 7.0p2(QA) - April 2002 Pile: /bome/schor/Jvyc-2120c/SENSITIVITY/SBO/drywell-SBO/SBO-dryweIl2 24 PT ?essoxtS

, n4 16.*

0.* . 1 (se

° 3 I 14.4I 1.

?Jae (Sto) 1-&S If.hAl W..,IS/1215 11,49,09 Figure 5 - RPV Pressure - Case SBO -drywell2 SBO - SOP-Noleak-drywell Mar/03/2005 13:30:33 GOTHIC Version 7.Op2(QA) - April 2002 File: /home/scbor/vyc-2120ccn/SNSITIVITY/SBO/drywell-SB0/SBO-Crywe112 Rtactar vesstL T ytrata SY4 SL4 S~t4 TD4 I-_ _ _ _ _ _

^o -

A i'

_ _.. . ?.. e.. 2 TS64t (see) o.mw V.ftetonl P...dS/2605 X1MA4 Figure 6- RPV Temperature - Case SBO-drywell2

.Entergy Calculation VYC-2405 Rev. 0 Page 30 of 85 -

SBO - SOP-Itoleak-drywelll Mar/03/2005 1.3:01:07 GOTHIC Version 7.0p2fQA) - April 2002 File: /hoze/schor/vyc-21220cC/SESITIVITY/SBO/dryvell-SBO/SDO-drywell2 21 PY Liqzd ti -

1.4 M _ _

° . I

- 0 7

. XX

-%A AS .12,4],

1+/- (see)

Figure 7- RPV Level - Case SBO-drywell2 SEO - 80P-Noleak-drywelll Mar/03/2005 13:29:11 GOTHIC Version 7.0p2(QA) - April 2D02 File: /hoce/s cor/vyc-220ccn/SENSITIVITY/SBO/dryweil-SO/SBo-drywell2 48 SurfAet Tentrature 715 135 T7I I

T7M (sea) lmA ,Xf§^)"w§X/@S11.4C.42 Figure 8 - Surface Temperature for Heat Slabs 5,6 & 7 - Case SBO-drwell2

l<A,' -

.tEnergy I Calculation VYC-2405 Rev. 0 Page 31 of 85 ;

SBO - 80F-Noleak-drywelll Mar/03/2005 13:28:24 GOTHIC Versio= 7.0p 2 (QAJ - April 2002 File: /hoiw/scbar/vyc-2120ccn/SENSITIVfTY/SBO/drywell-SBO/SBO-dsywe12 51 Surface 7*pratut Ts$ T., T.IO TB11 I A le'-a a Mil ;17 'M Ss '2 I

" .571 7.143 1O.7 14.23 17.8 21.43 25 TiAt (Seo) 4T 7219AI l-09112*15 11,4641 Figure 9 Surface Temperature for Heat Slabs 8,9,10,11 - Case SBO-drwell2 SBo - S0P-Noleak-drywelll Mar/14/2005 14:45:07 GOTEIC Versiom 7.0p2(QA) - April 2002 File: /home/schor/vyc-2 12Occn/SNSrITlVITY/SBO/drywell -SBO/SBO-drywell2 52 Ouf~cetaapra~te a _'

-O 5.04 IC TJin (see) 4eXT8 7.St¢2C^A s../14/2*5 sltS2SSS Figure 10 - Surface Temperature for Heat Slabs 12 and 13 - Case SBO-drwell2

!Entergy Pag .

Calculation VYC-2405 Rev;.0 Page 32 of 85 '"'- -

SBO - SOP-Noleak-dryvelll Mar/03/2005 13:31:38 GOTHIC Version 7.Op2(OA) - April 2002 Pile: /bome/schor/vyc-2l2Occn/SENSITIVITr/SBo/dywell-SEBO/SBO-drywell2 Z VtetwtU 7mperathme 2T2 5X2

? -- ir- s riA b

E YA I e

40 .. 3,S2017.4$

2661 14,4

. STi (see)

Figure 11 Suppression Pool Temperature case SBO-drywell2 SBO - SOP-Noleak-drywelll Mar/14/2005 14:02:38 GOTIIC Version 7.0p2(QA) - April 2002 Pile: /bome/schor/vyc-212Occn/SSSITIVITY/SBO/drywell-SBO/SEO-drywell2 4 I:,tgrated IIPCX Plow

- I i 1i

-^ .°-I e O-C 1 f 0 3.C 7.2 20.2 14.4 is 21.6 2 .2 S ($to)

Figure 12- Integrated HPCI Flow - SBO-drywell2

ofEntergy Calculation VYC-2405 Rev. 0 Page 33 of 85 6.2 Case SBO-d'well2-80-sensy2-NoLeak 6.2.1 Model modification Table 8 presents the modifications to the base deck SBO-drywell2 to produce SBO-drywell2 sensy2-NoLeak.

The following modifications were made:

The Heat Transfer Coefficient Types 6 and 7 were modified to use Uchida correlation for.

condensation heat transfer instead of MAX (maximum of Uchida or Guido-Koestel). For this case since there is no RPV leakage, the choice of condensation correlation should have a minimal impact on results.

For the Heat Transfer Coefficient Type 7 the radiation option was turned off. Again, at these small temperatures, the radiation has a minimal impact on results.

The humidity in Volume I (Drywell) was modified from 100% humidity to 20% humidity to encompass all the humidity range in the drywell (Reference 5).

The reverse loss coefficient for the vacuum breakers was changed from Iel8 to 3.964 (equal to the forward loss coefficient).

A coefficient of 3.93 should have been used. This is corrected in Case 5.

The vacuum breaker reverse coefficient is the weighted sum of the flow paths 7, 8 & 9 of Reference 9. (Same as the forward loss coefficient)

K reverse = 1.168 (15.63/16.23)2 + 2.528 (15.63/16.23)2 + 0.5 (1.53/1 53)2 = 3.93 (A K of 3.96 was used, less than a 1% difference)

The area ofjunction 21 is changed from 0.12 ft2 , maximum leakage to 0.0033 ft2 (allowable Tech Spec leakage) -Reference 33.

Table 8; Input Modifications -SBO-drywell2-80-sensy2-NoLeak vs. SBO-drywell2

-- Entergy CalcufationVYC-2405 Rev. O Page 34 6f 85 Modifications in /hctne/schor/vyc-2120ccn/SENSI TIVITY/SBO/drvel 1-SBOISBO-drywel 12-80-sen Mar/10/2005 10:42:03 GOTHIC Version 7.Op2(QA) - April 2002 File: /home/schor/vyc-212Occn/SENSITIVITY/SBO/dryel 1-SBO/SBO-dryel 12-80-sensy2-NoLeak Graphs (continued)

Graph Curve Hunter Title Mon 1 2 3 4 5 42 Heat to the sup CQ4H CM 43 Leak Flow FL4 FL19 FL20 44 Integrated Leak cv4D 45 Title cv39 46 FV18 FL18 FD18 47 cv38 48 Surface Tempera TB5 TB6 T87 49 Surface Tempera TA8 TA9 TA10 50 Surface Tempera TAI TA12 TA13 51 Surface Tempera TB8 TB9 TB10 1T11 52 Surface tempera TB13 T812 53 TP8t600 TP9t600 TPlOt60 TPllt60 54 TP13t5O TP12t50 55 Dryhll Tempera TY1 TI Heat Transfer Coefficient Types - Table 1 Healt Cnd Sp Nat For Type Trans fer Nominal Cnv Cnd Cnv Cnv Cnv Rad

Opt1l on Value FF Opt Opt HTC Opt Opt Opt 1 Corre' lat 0 VERT SURF P11 [E FLOW OFF 2 Corre ]at 0 VERT SURF PIFiE FLOW OFF 3 Corre ]at FACE DOWN PIFPEFLOW OFF 4 Corre lat FACE UP PIF ,E FLOW OFF 5 Sp Hegat 0.

6 Oirecl t ADD UCHI VERT SURF PIF'E FLOW OFF 7 Direclt ADD UCHI FACE DOWN PIF'E FLOW OFF Run Control Parameters (Seconds)'

Time DT DT' IT End Print Gra h Max. Phs Chn Int Min Max Ratio Time- Int In CPU Int Tie ScaYe 1 le-06 1. 1. 100. 5. 0.1 le-f06 0. DEFAULT 2 le-06 1. 1. 1200. 50. 1. le+06 0. DEFAULT 3 le-06 1. 1. 1300. 500. 10. le+06 0. DEFAULT 4 le-06 1. 1..25000. 600. 10. le+06 0. DEFAULT

.. Entergy Calculation VYC-2405 Rev.O ' Page 35 of 85 - '

Modifications in /hone/schor/vyc-212Dccn/SENSITIVITY/SBO/drywell-S8O/SBO-drywel12-80-sen Mar/10/2005 10:42:03 GOTHIC Version 7.0p2(OA) - April 2002 File: /home/schorlvyc-2l2Occn/SENSITIVITY/SBO/dryxell-SBO/SBO-drywel12-80-sensy2-NoLeak 9'. Volune Initial Conditions Vapor Liquid Relative LiquId Ice Ice Vol Pressure Tempo. Te.7. Humldlty Volume Volune Surf.A.

(psia) (F) F (S) Fractio Fract. (ft2) def 14.7 80. . 80. 60. ' 0. 0. 0.

1 16.4 170. 170. 20. 0. 0. 0.

2 14.7 90. 90. 100. 0.39497 0. 0.

3 16.4 90. 90. 100. 0.00595 0. 0.

4 1045.2 549.97 533.12 100. 0.60794 0. 0.

Graphs Graph i 1 Curve Number Title Mon 1 2 3 . 4 5 1 Drvwell Tempera TY1 T11 2 Wetwell Terpera TV2 TL2 3 Contalnment Pre PRI PR2 4 Reactor Vessel TV4 TL4 ST4 TD4 5.- RHR Heat Exchan xqlH 6 Reactor Vessel AL4 7 Torus Water Vol AL2 8 Heat Exchanger tllH t21H 9 Wetwell. Vessel 112 TL4 TL1 10 Conductor Tempe TA1 TA2 TA3 TAM 11 Integral Vessel QL4 QV4 12 Vapor & Conduct. TV4 13 Liquid & Conduc 114 TA2 14 Vapor & Conduct TV2 TA3 i5 Liquid & Conduc TL2 TM 16 Vapor Heat Tran HA1 17 Liquid Heat Tra hA2 18 Vapor Heat Tran HA3 19 Liquid Heat Tra hA4 20 Feedwater & Bre FL9 FL4 21 RPV Liquid Leve LL4 22 SRV and ADS Flo FV1O FV11 23 Feedwater Entha cv29 24 RPV Pressures PR4 25 Feedwater Contr cv27 cv28 26 Integrated Feed cv4 27 RHR Flow FL5 28 Vessel Droplet' AD4 29 ECCS Injection' FL7 FL12 FL14 30 RPV Pressure PR4 VC2V FL7 31 ADS Valve Posit VC3V 32 SRV Position VC2V 33 Cooldomn FLow FV16 34 Vessel Drop Dia D14 35 Reactor Vessel PR4

36 Suppression poo 112 37 Reactor Vessel PR4 38 Suppression Poo 112 39 HPC1 Flow Rate FL18 40 Integrated HPCI cv39 41 Core Spray Flow FL8

o AdEntergy . . Calculation VYC-2405 Rev. 0 Page 36 of 85 "

Modifications -1in /hconelschor/vyc-2l2OccnISENSITIVITY/SBO/drywell-SBO/SBO-drywel 2-80-sen Mar/10/2005 10:42:03 GOTHIC Version ?.0p2(QA) - April 2002 File: /home/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-80-sensy2-NoLeak N Flow Paths - Table 2 Flow Flow Iyd. Inertia Friction Relative Dep Mom Strat Path Area Diam. Length Leinth Rough- Bend Trn Flow i (ft2) (ft) (f ) (f) ness (deg) Opt 1 283.529 6.75 89.13 0. 0. - NONE 2 286.114 1.948 4.16' 0. -1. - NONE 3 15.63 1.5625 44.925 28.72 0. - NONE 4 0.001005 0.03568 0.1 0. - NONE 5 3.14 2. 0.01 0. - NONE 6 3.14 2. 0.01 0. NONE 7 3.14 2. 0.01 0. - NONE 8 3.14 2. 0.01 0. - NONE 9 3.14 0.01 0. - NONE 10 0.09945 0.35584 0.01 0. - NONE 11 0.3978 0.35584 0.01 0. - NONE 12 3.14 2.

2. 0.01 0. - NONE 13 3.14 2.

0.01 0. - NONE 14 3.14 2. 0.01 0. - NONE 15 3.14 2. 0.01 0. - NONE 16 3.14 2. 0.01 0. - NONE 17 3.14 2. 0.01 0. - NONE 18 3.14 2. 0.01 0. - NONE 19 0.5454 0.8333 0.1 0.1 - NONE 20 0.5454 0.5454 0.1 0.1 - NONE 21 0.0033 1. 1. 0. - NONE Flowr Paths - Table 3 Fl ow FWd. *Rev. Critical Exit Drop Path Loss Loss D. Fl1 Loss Breakup Coeff. Coeff. OR. 1oe Coeff. Model I 4. 2243 4.2243 ON TABL ES 1. OFF 2 1. 0.78 ON TABLES 1. OFF 3 3 .964 3.964 ON OFF 0. OFF 4 0. OFF TABLES 1. OFF 5 OFF OFF OFF 6 OFF OFF .0. OFF 7 OFF OFF *0. OFF 8 OFF OFF 0. OFF 9 OFF OFF 0. OFF 10 OFF TABLES 0. OFF 11 OFF TABLES 0. OFF 12 OFF OFF 0. OFF 13 OFF OFF 0. OFF 14 OFF OFF 0. OFF 15 OFF OFF 0. OFF 16 Ie*18 OFF OFF 0. OFF 17 OFF OFF 0. OFF 18 OFF OFF 0. OFF 19 OFF OFF 0. OFF 20 OFF OFF 0. OFF 21 1.5 1.5 OFF OFF 0. OFF

.Entergy Calculati6o VYC-2405 Rev. O Page 37 of 85 6.2.2 Case SBO drywell2-80-sensy2-NoLeak Results Figure 13 through Figure 20 present the main parameters for the case SBO-drywell2-80-sensy2-NoLeak. Figure 13 presents the drywell temperature. The maximum drywell temperature is about 289.4 TF "and is reached after one hour and 30 minutes.. The heatup is arrested due to depressurization. At about 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months into the transient the temperature in the drywell starts increasing due to lower heat removal into the passive heat sinks (walls) . The air gap acts as an insulation and the steel liner is almost at 255 'F. However, after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available so the operators can spray the drywell with the RHR pump, if needed. The results indicate that the temperatures in the drywell stay below the EQ limit and the drywell liner is well below the 281 'F for the SBO coping duration.

Figure 14 presents the containment pressure. Due to a lower leak area the drywell and the wetwell are at not at the same pressure, the vacuum breaker opens to relieve the pressure difference at about 14000 seconds. At about 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months the pressure in the drywell is too low to spray the drywell, (unsafe area of DWSIL (EOP-3 -Primary Containment Control -Reference 30)) however the pressure increase to about 6 psig at about 10800 seconds at which point the operators would be able to spray the drywell with the RHR pump, if needed.

Figure 15 presents the RPV pressure. At one hour into the event it is assumed that the operators start depressurization. The pressure drops to the HPCI shutoff pressure of 165 psia at about 12000 seconds. At this point only about 450000 lb were injected from CST (Figure 17). The RPV is depressurized, and the CS pump is available to inject.

Figure 16 pump presents the RPV level. The core stays covered. There is a dip in the normal level at about 12000 seconds when HPCI stops injecting and CS does not inject yet. This is due to the fact that the CS pump was set to inject at 14000 seconds; however CS is ready to inject at 7800 seconds, provided the pressure permissive is reached.

Figure 18, Figure 19, and Figure 20 presents the drywell liner temperature. The drywell liner stays below 260 'F for the 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months analyzed. After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available for suppression pool cooling, drywell spray and maintaining vessel inventory.

The suppression pool temperature for this case is very similar to the case SBO-drywell2 since the input changes results in minor changes to the drywell temperature and pressure but not in the suppression pool temperature since the heat transferred to the drywell is not subtracted from the vessel energy.

AdEntergy *. Calculation VYC-2405 ReV.:0 Page 38 ofB:

85' :

SWO - 80F-Nolea3c-drywell2-sensitivities-set2 Mar/10/2005 10:36:15.

GOTHIC Vergion 7.Op2iQA) - April 2002 File: /home/schor/vyc-2120ccn/SENSlTIVITY/SBO/drywell-SBO/SBO-drywel12-80 Figure 13 - Drywell Temperature -Case SBO-drwell2-80-sensy2-NoLeak SSO - 80F-Noleak-drywell2 -sensitivities-set2 Mar/10/2005 10:56:11 GOTHIC Version 7.0p2(QA) - April 2002 .

File: /home/schor/vyc-2120ccn/SENSITIVIlTY/sO/drywell-SBo/SEO-drywell2-80 CoteaiptAt Presswt 1.. 1.2..

an o- -- 1_1-_

e l *l I>

iI I 3.~~~~rs M.z 'Pr;t4l Ad 21s

'Time (set) w oaf14tta) ""t/?26205 11,0153 Figure 14-Containment Pressure - Case SBO-drwell2-80-sensy2-NoLeak

'Enfergy Calculation-WC-2405 Rev;. Page 39 of'85 -

SBO - 80F-Noleak-drywell2-sensitivities-set2 Mar/10/2005 11:11:35 GOTHIC Version 7.Cp2(QA) - April 2002 File: /home/schor/vyc-2120cccf/SENSITIVIT/SBO/drywell-SBO/SBO-dxywel12-B0 24 24MT YtsIs3rts

.n 3 01oa' I o _ f, rLL Time Cie) arms *.04a

8242 110121S *t t.,5t Figure 15 - RPV Pressure - Case SBO-drwell2-80-sensy2-NoLeak SBO - 6OF-Noleak-dryveIl2-sensitivities-set2 Mar/10/2005 11:15:46 GOTHIC Version 7.Op2(CA) - April 2002 File: /hane/schor/vyc-2120ccn/SSITlVITY/SEO/drywell-SBO/SBO-drywell2-80 p2 Pv Liqmii Laval

- LL 1W .

t 7 I

.3 0

i TA" (see)

Figure 16 - RPV Level - Case SBO-drwell2-80-sensy2-NoLeak

. -Enfergy -. Calculation VYC-2405 Rev. 0 Page 40 o6f85 W.-Will 17 , -

SBO - 80P-Nioleak-drywel2-sensitivities-set2 Mar/10/2005 11:10:47 GOTHIC Version 7.0p2(QA).- April 2002 File: /hoe/scbor/vyc-212 0Ccn/SmSITIVITY/SBO/drywell-SBO/SBO-drywe 12 -80 4attgrated IGCG r -

, cvfl Tixk (sea)

= 7.V0i1- "-IIii ,1t,52 Figure 17 Integrated HPCI Flow - Case SBO-drwell2-80-sensy2-NoLeak SBO - 8OP-Noleak-drywell2-sencitivities-set2 Mar/10/2005 10:33:12 GOMHIC Version:7.0p2(QA) - April 2002 File: /hocre/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-dryvel12-80 7 rface Tespetatre TZS TDG 237 O _i CD (See) 4t?0IF W a.'.,j1g2

-. 71.1.32 Figure 18- Surface Temperature for Heat Slabs 5,6 & 7 - Case SBO-drwell2 sensy2-NoLeak

MPf

~Entergy. Calculation VYC-2405 Rev. 0 Page 41 of!85>.: N SWO - 8OP-;oleak-dry-iell2-sensitivities-Set2 Mar/20/2005 10:34:30 GOTUIC Version 7.0p2WQA) - April 2002 File: /home/schor/vyc-2l2Occn/SENSlTVIT'Y/SBo/drywell-SBO/SBO-dywell2 -80 T

Srf ace F erature SI nurface Tyetratwe 1r23T3 TuG lull 0- _ - _ -- -_

I.

Z4 D.

sl ,(see)

?."2(0A tr II-118.1200 *6,4t52_

Figure 19 - Surface Temperature for Heat Slabs 8, 9, 10 & 11 - Case SBO-drweJJ2-80-sensy2-NoLeak SEO - EOF-Noleak-drywell2-sensitivities-set2 Mar/10/2005 10:32:24 GOTHIC Version 7.0p2(QA2 - April 2002 File: /bone/scbor/vyc-2120cc/JSESITzvz/Y/SBO/drywell-SEO/SBO-drywell2-80 52 ~rutace tftptratnre

. fleat Slab 32 o Xat 5 12 I

2 , *Iz,,g,,,.~l,,,..,

3.6 7.2 .4.4 It.8 i TIMe (see)

IUMtY ?.ft~f eilS-f2 31.1t 5MESA Figure 20 Surface Temperature for Heat Slabs 12 & 13 - Case SBO-drwell2 sensy2-NoLeak

.. Enery "' - Calculation VYC-2405 ReV. 0

Page42of 85 6.3 Case SBO-drywell2-Leak-80-sensy 6.3.1 Model modification Table 9 presents the modifications to the deck SBO-drywell2-80-sensy2-NoLeak to produce SBO-dMyMell2-Leak-80-sensy The following modifications were made:

On BC 13, the ON trip is set to zero (0). This allows for a constant leak of 8.4585 lb/sec to leave the vessel.

The end time was changes to 14400 seconds (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ) since the purpose of this calculation was to show that the drywell temperature stays below the EQ drywell temperature and the drywell shell stays below 281 "F for the duration of 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes.

Table 9 SBO-drywell2-Leak-80-sensy vs SBO-drywvell2-80-sensy2-NoLeak

.. .Entergy Calculation VYC-2405 Rev. 0 'Page 43'of'85' :

Modifications in /home/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/S8O-dryweU12-Leak-8 Mar/14/2005. 15:38:40 GOTHIC Version 7.Dp2(QA) - April 2002 File: /home/schor/vyc-2120ccn/SENSITIVITY/SBO/dryewell-SBO/SBO-drywell2-Leak-80-sensy Fluid Boundary Conditions - Table 1 Press Tem. Flow ON OFF BC# Description (psiaj FF (F) FF (lbrn/s) FF Trip Trip IF RHR/LUCI Suctlo 20. 160 v-O.002 8 1 13 2C RHR/LPCI Discha 20. 160 3F LPCS Suction 20. 160 v-0.002 7 30 31 4C LPCS Discharge 20. 160 5F Feedwater 1000 el 5 1000 9 1 5 6F RHR/Torus Suct1 20. 160 v-0.002 6 21 1 i 7C RHR/Torus Disch 20. 160 0 i 8F HPCI/RCIC Sucti 20. 160 -326.1 9 1 0 9C HPCI/RCIC Disch 20. 160 loP Cooldown Inlet 1. 10 111 21 0 I

.lF Cooldown Outlet 1. 10 1 11 112 12F CST Tank - 14.7 135 587 13 28 27 13F Vessel Leak 1050. 554. -8.4585 13 0 14C Vessel leak to 1050. 0 554 i

Run Control Parameters. (Seconds)

Time DT OT DT End Print Graph Max DumPhsChng Int Min Max Ratio Time Int . Int CPU In Time Scale I le-06 1. . 1. 100. 5. 0.1 le-06 0. DEFAULT i 2 le-06 1. 1. 1200. 50. I. le+06 0. DEFAULT 3 le-06 1. 1. 1300. 500. 10. le+06 0. DEFAULT 4 le-06 1. 1. 14400. 600. 10. le4+06 0. DEFAULT Graphs

Graph Curve Number T Title Mon 1 2 3 4 5 1 Drywell Teapera TV1 TL1 2 Wetwell Teapera TV2 TL2 3 *Contaimnent Pre PR1 PR2 4 Reactor Vessel TV4 TL4 ST4 TD4 5 RHR Heat Exchan xqIH 6 Reactor Vessel AL4 7 Torus Water Vol AL2 8 Heat Exchanger thlH t21H 9 Wetwell. Vessel 1L2 TL4 TL1 10 Conductor Tempe TAI TA2 TA3 *TM 11 Integral Vessel Q4 OV4 12 Vapor & Conduct J4 TA1 13 Liquid &Conduc TL4 TA2 14 Vapor & Conduct TV2 TA3 15 Liquid & Conduc TL2 TA4 16 Vapor Heat Tran HAI 17 LIquid Heat Tra hA2 18 Vapor Heat Tran HA3 19 Liquid Heat Tra hA4 20 Feedwater & Bre FL9 FL4

' Entergy

Calculation VYC-2405 Rev. 0 44 of 85 .Page Modifications in /hane/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywel12-Leak-B Mar/14/2005 15:38:40 GOTHIC Version 7 Op2(QA) - April 2002 F1le: /home/schor/vyc-2120ccn/SENSITIVITY/SBO/drywll-SBO/SBO-drywell2-Leak-80-sensy Graphs (continued)

Graph Curve Number Title Mon 1 2 3 4 5 21 RPVOLiquid Leve LL4 22 SRV.and ADS Flo FV10 FY11 23 Feedwater Entha cv29 24 RPV Pressures PR4 25 Feedwater.Contr cv27 cv28.

26 Integrated Feed cv4 27 RHR Flocw FL5 28 Vessel Droplet AD4 29 ECCS Injection FL7 'FL12 FLl4 30 RPV Pressure PR4 VC2V FL7 31 ADS Valve Posit VC3V 32 SRV Position VC2V 33 Cooldown.FLow . FV16 34 Vessel Drop Dia DI4 35 Reactor Vessel PR4 36 Suppression poo TL2 37 Reactor Vessel PR4 38 Su ression -Poo LL2 39 HPEI Flow Rate FL18 40 Integrated HPCI cv39 41 Core Spray Flow FLB 42 Heat to the sup CQ4H CQ2H 43 Leak Flcw FL4 FL19 FL20 44 Integrated Leak cv4O 45 Title cv39 46 . FV18 FL18 FD18 47 cv38 48 Surface Tempera TB5 TB6 TB7 49 Surface Tempera TAB TA9 TAM 50 Surface Tempera TAll TA12 TAN3 51 Surface Tempera TB8 TB9 TB10 TB11 52 Surface teTpera 1B13 TB12 53 . TPWt600 TPqt600 TP1Ot60 TP11t60 54 TP13t5O TP12t5O JOO Xmoo , xxx xxxxxxx xxx)OO xxxxXX XXXXx x

nEntergy Calculation VYC-2405 Rev. 0 Page 45 of 85 6.3.2 Results Case SBO-drywell2-Leak-80-sensv Figure 21 through Figure 29 present the main parameters for the case SBO-drywell2-Leak sensy. Figtre 21 presents the drywell temperature. The maximum drywell temperature is about 290 °F and is reached at about 12240 seconds (3.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). The drywell heatup rate is arrested due to depressurization, however the leak brings enough energy from the vessel to continue the heatup. At 7800 seconds the drywell temperature is 285.8 0F, well below the EQ limit of 325 OF.

Figure 22 presents the containment pressure. The available water to spray the drywell (Reference

30) is the Diesel fire pump per Appendix M of OE 3107 (Reference 35) and it takes about one hour for aligning the fire pump for drywell spray. The drywell pressure is high enough to allow for drywell spray, if needed. The drywell temperature does not exceed the EQ drywell temperature limit and the drywell shell temperature stays below the limit of 281 TF hence the analysis shows that drywell spray is not needed for the coping duration. At about 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 30 minutes the wetwell pressure reaches equilibrium with drywell and slightly exceeds the drywell pressure. The vacuum breakers do not open during the time of interest.

At about 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the wetwell pressure is about 26 psig, close to the PSP limit of 27 psig.

However at this time the RHR pump is available for containment spray.

Figure 23 presents the RPV pressure. At one hour into the event it is assumed that the operators start depressurization. The pressure drops to the HPCI shutoff pressure of 165 psia at about 12000 seconds. At that point only about 540000 lb were injected from CST (Figure 25). At this time the RPV is depressurized, and the CS pump is available to inject.

Figure 24 pump presents the RPV level. The core stays covered. There is a dip in the normal level at about 12000 seconds when HPCI stops injecting and CS does not inject yet. This is due to the fact that the CS pump was set to inject at 14000 seconds; however, CS is ready to inject at 7800 seconds, provided the pressure permissive is reached.

Figure 27, Figure 28, and Figure 29 presents the drywell liner temperature. The dryweil liner stays below 280 °F for the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months analyzed. After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available for suppression pool cooling, drywell spray and maintaining vessel inventory.

The suppression pool temperature is not a parameter of importance for this calculation. In Reference I it was shown that the suppression pool temperature is lower for the cases RPV with leakage and lower for earlier depressurization hence the maximum suppression pool temperature will be lower that 182.2 TF, calculated in Reference 1.

.. .I 'Entergy Calculation VYC-2405 Rev. 0 Page 46 of 85 -.^-

SBO - 80F-Noleak-dryve112-Leak-80-sersitivities Mar/14/2005 11:02:51 GOTrIC Vervion 7.0p2(QA) - April 2002 File: /hone/schor/vyc-2120ccn/SSI VITTY/SBO/drywell-SBO/SBO-dryweli2-Le X Drpve1ttekeratxe Tryt-1 Liai eir

- 6 7. ! 0.

B.

Tiae (5*e)

nTx tt1.Uq " VuV03/244S II II 31 Figure 21 -Drywell Temperatures - SBO-drywell2-Leak-80-sensy SBO - SOP-Noleak-drywel12-Leak-SO-sensicivicies Mar/14/2005 11:03:43 GOTEIC Version 7.Op2(QA) - April 2002 File: /home/schor/vyc-2120ccn/SxNSTrITY/SBO/drywell-SBO/SBO-drywell2-Le I* eeutaizmtnt pre smrt tont 32 t r"Sr rk 2 t6 e

.. ° L

. , 112.2 Figure 22 - Containment Pressure - SBO-drywell2-Leak-80-sensy

.. Entergy Calculation VYC-2405 ReV. 0 Page 47 oF85 SSO - 8OP-)oleak-drywell2-Leak-80-sensitivities Y.ar/1412005 11:05:31 GOTHIC Version 7.0p2(QA) - April 2002 File: /bhoe/ecc.or/vyc-2l2Occn/SENSITIVITY/SBO/drywell-SDO/SBO-drywell2-Le 24 n Pressurcs

' t4- '-------

c; 7 -'

CfiG slk p8 . 2f X_ / _ 0 5 _ _ _ I_ _ _

-4 .3.

Figure 23 - RPV Pressure - SBO-drywell2-Leak-80-sensy SBO - 8OP-Noleak-drywell2-Leak-80-sensitivities Mar/14/2005 11:04:51 GOTEC Version 7.0p2(QA) - April 2002 File: /hoae/schor/vyc-2220ccn/SNS1TIV1TY/SfO/drywe1l-SBO/SBO-drywe1l2-Le

? ZL.Ld LeVtI U

I21 3t4 ad L l L4 .

4, w I I4 _§.,\

_m '

el'\

° V 'st LL1 L.tLI TiSe (Sao)

Figure 24 RPV Level - SBO-drywell2-Leak-80-sensy

Entergy Calculation VYC-2405 Rev. 0 Page 48 of 85S SBO - 80F-Noleak-drywell2-Leak-8O-sensitivities Mar/14/2005 11:09:57 GOTHIC Version 7.0p2(QA) - April 2002 File: /bome/acbor/vyc-2220ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-Ie 140 Uttegrate.I NPX Y10W I

3 .

vag (sec) 1fe.0yMOs 8_141nies Mts.ts.

a 25 - Integrated HPCI Flow - SBO-drywell2-Leak-80-sensy SBO - 80F-Noleak-drywell2-Leak-80-sensitivi ies Mar/14/2005 11:10:57

-GOTEIC Version 7.0p2(QA) - April'2002 File: /home/schor/vyc-2120ccn/SVISITIVITY/SBO/drywell-SBO/SBO-drywell2-Le 3 Leak 71W n4 nis me 11.97L13 116.20 6Ai S.ee Tine (see) 1.2 3~ 32.8 4 Figure 26-Leak Flow - SBO-drywetl2-Leak-80-sensy

^'Entergy Calculation VYC-2405 Rev: 0 Page 49 of 85 :

SZO - SOP-Noleak-drywell2-Leak-80-sensitivities Mar/14/2005 11:07:22 GOTHIC Version 7.0p2(QA) - April 2002 File: /hoe/schor/vyc-2120ccn/SENSITIVITY/SBO/drywe1-SBO/SBO-drywel12-Le 4$ 3u1r0e Teaptraurts TDS TUB T27 C a- . -

0 _

I-.

$-M ?.Z1h_q132# 2,1 1 r ** C IC C C CI

t *I 14 t C J .6 7. 10.a Time (sea)

Figure 27 - Surface Temperature, Heat Structures 5,6,7 - SB0-drywell2-Leak sensy SBO - SOP-Noleak-drywell2-Leak-80-sensitivities Mar/14/2005 11:06:34 GOTHXC Version 7.0p2(QA) - April 2002 Pile: /hoce/scbor/vyc-2120cc/SXNSITIVITY/SBO/drywell -SBO/SBO-drywell2-Le SSsurface Teperatur DaSJ 118 T1 aeB11 I.

, S (set) 7 .*.

/* 1225 ,11.22 11809 Figure 28 - Surface Temperature, Heat Structures 8, 9, 10, 11 - SBO-drywel/2-Leak-80-sensy

.. Enter y .. Calculation'WC-2405 RbM. 0 Page 50 of 85 SBO - 8OP-Noleak-drywell2-Leak-80-sensitivities Mar/14/2005 11:C0:22 GOTUIC Version 7.Cp2(QX) - April 2002 File: /horme/schor/vyc-212 0ccn/SENSITIVITY/SBO/drywell -SBO/SBO-drywell2 -Le Figure 29 - Surface Temperature, Heat Structures 12,13 - SBO-drywell2-Leak sensy

Entergy t '-CalcUlation VYC-2405 Rev. 0 Page 51 o6f85' 6.4 Case SBO-drywell2-Leak-45-sensy 6.4.1 Model modification Table 10 presents the modifications to the deck SBO-dryivell2-Leak-80-sensy to produce SBO-dryivell2-Leak-45-sensy.

Two modifications are made, the depressurization (cooldown) table, is changed from 80 0 F/hour to 45 bF/hr (same cooldown curve as in Reference 1- Function 10).

The RHRSW temperature is changed from 85 0F to 75 °F consistent with Assumption 13 and Reference 1.

Table 10 SBO-dryvell2-Leak-45-sensy vs SBO-dryvell2-Leak-80-sensy

'~Entergy. CalculationVYC-2405 ReV. 0 - - Page 52 of 85 Modifications in /hare/schor/vyc-2120ccn/SENSITIVITY/SBO/drywvell-SBO/SBO-dryell12-Leak-4 Mar/14/2005 17:49:07 GOTHIC Version 7.0p2(Q A) April 2002 File: /harne/schor/vyc-212occ~nSENS ITIVITY/SBO/drywell1-SBO/SBO-dry,6sll12-.Leak-45 -sensy P' Functions FF# Description Ind. Var. Dep. Var. Points.

0 Constant 0 1 RHR HK Tube Reynolds N Nusselt Nu 34 2 RHR Hx Shell Reynolds N Nusselt Nu 34 3 Decay Heat Time (sec) Decay Heat 50 4 Pump Heat Time (sec) Heat Rate 6 5 Feed Enthalpy cv4 Dep. Var. 34 6 RHR/Torus Time (sec) Flow (gpm) 3 7 LPCS Flow Curve cv26 Flow (gpm) 13 8 LPCI Flow Curve cv26 Flow (gpm) 12 9 Feed Flow cv28 Dep. var. 3 10 Cooldown Pressu Time (sec) Pressure ( 39 11 Cooldown Tenper cv33 Dep. Var. 3 12 Cooldown Flow cv32 Dep. Var. 3 13 Constant Ind. Var. Dep. Var. 6 14 ECCS PUTP Heat Time (sec) Heat Rate 6 15 Check Valve Ind. Var. Dep. Var. 6 16 SW Time (sec) Service Wa 6 17 Drywell Power C cv41 Dep. Var. 4 18 Drywell Power C cv42 Dep. Var. 4 Heat Exchangers - Table 2 Heat Scndy Scnd Scndy Scnd Ext. Ext. Ext. Ext.

Ex. Flow Flow Temp Temp Flow Flow Heat Heat f (ltin/s) FF (F) Ff (lbmts) FF (Btu/s) FF

1H 1. 16 75.

Graphs Graph Curve Number Title Mon 1 2 3 4 5 I Drywell Tempera TV1 TL1 2 Wetwel 1 Tempera TV2 TL2 3 Contaimient Pre PRI PR2 4 Reactor Vessel TV4 TL4 ST4 TD4 5 RHR Heat Exchan xqlH 6 Reactor Vessel AL4 7 Torus Water Vol AL2 8 Heat Exchanger t1lH t21H 9 Wetwell. Vessel TL2 TL4 T11 10 Conductor Tempe TAI TA2 TA3 TAM 11 Integral Vessel OL4 OV4 12 Vapor & Conduct TV4 Al 13 Liquid & Conduc TL4 TA2 14 Vapor & Conduct TV2 TA3 15 Liquid & Conduc TL2 TA4 16 Vapor Heat Tran HA1 17 Liquid Heat Tra hA2 18 Vapor Heat Tran HA3

g5.M

-.. - 'r. Entergy Calculation VYC-2405 Rev. D "' Page 53 of 85 -

Modifications in /hcme/schor/vyc-2120ccn/SENSItIVITYISBO/drywell-SB0/SBO-drywel12-Leak-4 Mar/14/2005 17:49:07 GOTHIC Version 7.0p2(QA) - April 2002 File: /hcme/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-dryweI 2-Leak-45-sensy Graphs (continued)

Graph Curve Number

. Title Mon 1 2 3 4 5 19 Liquid Heat Tra hA4 20 Feedwater & Bre FL9 'FL4 21 RPV Li quid Leve LL4 22 SRV and ADS Flo FY10 FV11 23 Feedwater Entha cv29 24 RPV Pressures PR4 25 Feedwater Contr cv27 cv28 26 Integrated Feed cv4 27 RHR Flow .. FL5 28 Vessel Droplet AD4 29 ECCS Injection FL7 FL12 FL14 30 RPV Pressure PR4 VC2V FL7 31 ADS Valve Posit VC3V 32 SRV Position VC2V 33 Cooldown FLow FY16 34 Vessel Drop Dia DI4 35 Reactor Vessel PR4 36 Suppression poo 1L2 37 Reactor Vessel PR4 38 Suppresslon.Poo LL2 39 HPCI Flow Rate FLIB 40 Integrated HPCI cv39 41 Core Spray'Flow FL8 42 Heat to the sup . CQ2H 43 Leak Flow FL4 FL19 FL20 44 Integrated Leak cv4O 45 Title cv39 46 FV18 FLIS FD18 47 cv38 48 Surface Tempera 185 11B6 TB7 49 Surface Tempera TA8 TA9 . TAI0 50 Surface Tempera TAll TA12 TA13 51 Surface Temipera TB8 TB9 .T110 TB11 52 Surface tempera TB13 TB12 53 TP8t600 TP9t600 TPIOt6O TPllt6O 54 TP13t5O TP12tSO 55

Calculation VYC-2405 Rev. 0O

'Enteiy Page 54 6f'85 Modi ficati ons in /hcr e/schor/vyc-2120ccn/SENSITIVITY/SBO/drywel 1-SBO/SBO-drywel 12-Leak-4 Mar/14/2005 17:49:07 GOTHIC Version 7.0p2(QA) - April 2002 File: /hcine/schor/vyc-2120ccn/SENSIT IVITY/SBO/drywel 1-SBO/SBO-dryel 12-Leak-45-sensy Function 10 Cooldctn Pressure Ind. Var.: Time (sec)

Dep. Var.: Pressure (psia)

Ind. Var.- Dep. Var. Ind. Var. Dep. Var.

0. 1078.5 600. 1014.5 1200. 953.5 1800. 895.3 2400. 839.8 3000. 787.

3600. 736.8 4200. 689.1 4800. 643.7 5400. 600.7 600 559.9 6600. 521.3 7200. 484.8 7800. 450.2 8400. 417-6 9000. 386.8 9600. 357.8 10200. 330.5 10800. 304.9 11400. 280.8 12000. 258.2 12600. 237.1 13200. 217.3 13800. 198.9 14400. .181.7 15000. 165.6 15600: 150.8 16200. 136.9 16800. 124.2 17400. 112.3 18000. 101.4 18600. 91.3 19200. 82.1 19800. 73.6 20400. 65.8 21000. 58.7 21600. 52.3 22200. 46.4 1000000. 46.4

AEntergy Calculation VYC-2405 Rev. 0 Page 55 of 85 6.4.2 Results Case SBO-drvwell2-Leak-45-sensy Figure 30 through Figure 38 present the main parameters for the case SBO-dryivell2-Leak sensy. Figure 30 presents the drywell temperature. The maximum drywell temperature is about 293 TF and is reached at the end of the run (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). The run was not extended beyond the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months even though the drywell temperature continues to increase because at 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the RHR pump is available for drywell spray, if needed. The mission time of 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and .10 minutes is.

achieved. The drywell heatup rate is arrested due to depressurization; however the leak brings enough energy from the vessel to continue the heatup. At 7800 seconds the drywell temperature is about 290 TF, well below the EQ limit of 325 F .

Figure 31 presents the containment pressure. The drywell pressure is high enough to allow for drywell spray after one hour into the transient, if needed. The available water to spray is the.

Diesel fire pump (Reference 30) per Appendix M of OE 3107 (Reference 35) and it takes about one hour for aligning the fire pump for drywell spray. The drywell temperature does not exceed the EQ drywell temperature limit and the drywell shell temperature stays below the limit of 281 "F for the mission time of 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes hence spray from Diesel fire pump is not needed.

The vacuum breakers do not open during the time of interest.

At 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the torus pressure is about 25 psig and increasing, close to the PSP limit of 27 psig.

However at this time the RHR pump is available for containment spray.

Figure 32 presents the RPV pressure. At one hour into the event it is assumed that the operators start depressurizaiion. The vessel pressure during the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the run time does not reach the shutoff pressure for the HPCI pumps, so at 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the HPCI pumps still inject to maintain inventory. At 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months into the event only about 540000 lb were injected from CST (Figure 34). At this time the RPV is not depressurized, and the HPCI pump continues to inject.

Figure 33 presents the RPV level. The core stays covered and HPCI maintains inventory for the duration of the analyses. There is no need to continue the calculation beyond 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months because the.

coping time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months was demonstrated.

Figure. 35 shows that the leak is maintain constant for the duration of the transient.

F Figure 36, Figure 37, and Figure 38 presents the drywell liner temperature. The drywell liner stays below 280 TF for the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months analyzed. After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available for suppression pool cooling, drywell spray and maintaining vessel inventory.

. The suppression pool temperature is not a parameter of importance for this calculation. In Reference 1 it was shown that the suppression pool temperature is lower for the cases with leak and lower for earlier depressurization hence the maximum suppression pool temperature will be

. *lower that 182.2 "F calculated in Reference 1.

Entergy. Calculation VYC-2405 Rev. 0 Page 56 o6f85' N SSO - drywell2-Leak-45-sensitivities Mar/09/2005 18:54:07 GOTEIC Version 7.0p2 QA) - April 2002 Pile: /home/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le DrzywllTmperature l ?V1 712 Dr-.ei Vapor TepelatI p.0 S.1 vDrpvall Li 2mwseraf

-0 o ~.,,l ._

10.6 . i3 T1.t (sec) 4*2a I2^ k-M,11*41 tsIA2.6 Figure 30 -Drywell Temperature -Case SBO-drywell2-Leak-45-sensy SBO - drywell2-Leak-45-sensitivities Mar/14/2005 17:59:16 GOTHIC Versioun 7.0p2(QA) - April 2002 File: /kse/schor/vyc-2l20ccn/SENSITIVITY/SBO/drywell-SBO/SBO-dywell2-Le Prw5sit f

3 Cot.a+/-D..t eontaimet *ntin"r

,R 712:

u

.o-_

p a.

p

.P " ..

a0 w .

Tise (sec)

IVX2 ?.epU"k n.,JSS,/26S 1S,12,4 Figure 31-Containment Pressure - Case SBO-drywell2-Leak-45-sensy

Entergy . . Calculation VYC-2405 Rev.O Page 57 of 85 .

SBO - dlrywell2-1,cak-45-sensitivities Mar/09/2005 18:59:19 GOTHIC Version 7.0p2(QA) - April 2002 File: /hon /acbor/vyc-2120ccn/SEtSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le Figure 32- RPV Pressure -Case SBO-drywell2-Leak-45-sensy SBE - drywell2-Leakc-45-sensitivities Mar/09/2005 19:05:53 GOTHIC Version 7.0p2(QA) - April 2002 Pile: /bome/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le

-

T Liq%4d it4vL LL4 I

~~., I -, -

N

. Tint (see)

------ _-l,-,- ,- --- ,- -

Figure 33 - RPV Level - Case SBO-drywell2-Leak-45-sensy

`Entergy Y.

Calculation VYC-2405 ReV. 0 Page 58 of 85; .

SBO - drywell2-Leak-45-sensitivities Mar/09/2005 19:14:51 GOTHIC Version 7.0p2(QA) - April 2002 File: /home/schor/vyc-212Occn/SZNSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le 40 Xntagratad JWac Y1cw

-_ evI

'3. . I1

__1 ST __tt)w-/s2/ I o 3 ;e'72 I... .....-

$*m .ft( NW 9100 1t.2e8 Figure 34 - Integrated HPCI Flow - Case SBO-drywell2-Leak-45-sensy SBO - drywell2-Leak-45-sensitivities Mar/09/2005 19:16:54 GOTHIC Version 7.Op2(QA) - April 2002 File: /hcme/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le 43 Leak Flow n14 7.13 YL!2 Sn

.C

_-4 p..

o 1.6 3.2 4.8 6.4 S 3.6 11.2 1.8 TUne (sec) 4rmtD .2<) "W01/280 5.152.S4 Figure 35 - Leak Flow -Case SBO-drywell2-Leak-45-sensy

Entergy Calculation VYC-2405 Rev. 0 Page 59 of 85 SBO - drywcll2-Leak-45-sensitivities Mar/09/2005 19:06:59 GOTHIC Version 7.0p2 QA) - April 2002 Pile: /hoce/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell-SBO/SBO-drywell2-Le 41 Surflae Tmpratunr 735 Tai 237 C __ _ _ _

I' t I'

_ _ _F

- II .* 4 S1M (S46)

GMT 7.0,0WNtIV210 "/5,1@* SStt4 Figure 36 - Surface Temperature, Heat Structures 5,6,7 - SBO-drywell2-Leak sensy SBO - drywell2-Leak-45-sensitivities Mar/09/2005 19:08:37 GOTHIC Version 7.0p2(QA) - April 2002 File: /home/schor/vyc-2120ccn/SEXSITIVITY/SBO/drywell-SB0/SBO-drywell2-Le SI $nrfaca 2s~tcr ir 738s 733 7310 731 I

01 vi 1*0 S.

V I29.

.. .,z)"sn rss,

_{

Figure 37 Surface Temperature, Heat Structures 8,9,10,11 - SBO-drywell2-Leak sensy

.. .. Entergy Calculation VYC-2405' Rev. 0 Page 60 of 85

-N-,-

,71I . .

SBO - drywell2-Leak-45-sensitivities Har/09/2005 19:11:15 GCTHIC Version 7.0p2(QA) - April 2002 File: /homne/schor/vyc-2 120ccn/SENSITIVITY/SBO/d-ywell-SBO/SEO-drywell2 -Le s2 Surf ace teaprature 7323 7712

. If_

'r'0 2.8 .

T1,e (sto) 7.-liqffi

B~~t 1-1./XS S12.04 Figure 38 - Surface Temperature; Heat Structures 12,13 - SBO-drywell2-Leak sensy

Entergy. Calculation VYC-2405 Rev. 0 Page 61 of:85_t 6.5 Case SBO-drywell-comments 6.5.1 Model Modifications This case addresses the reviewer comments and also some discrepancies found during the documentation. The following changes are being made:

-change the initial temperature for Heat Structures 14 from 160 OF to 170 OF.

-change the Kreverse injunction 3 to 3.93 from 3.964.

-change the flow area of the valve V3 to 15.63 ft2 , same as the flow path flow area

-change the surface area of the concrete pedestal to 2068 ft 2 The changes are made to case 2 but it could be done to any of the other cases.

Table 11 presents the modifications made to file SBO-drywell2-80-sensy2-NoLeak to create SBO-drywell2-comments.

Table 11 Comparison between SBO-dryvell-comments vs SBO-drywell2-80-sensy2-NoLeak.

-Entergy Calculation VYC-2405 Rev. 0 Page 62 of 85. ;.

Modifications In /hane/schor/vyc-2120ccn/SENSITIVITY/SBO/dryl 1-SBO/SBO-drywel 1-ccrnent Mar/1512005 14:07:44 GOTHIC Version 7.0p2(QA) - April 2002 File: /.Jhoe/schor/vyc-2120ccnlSENSITIV1TY/SBO/drywl 1-SEO/SBO-drywel 1-cccwents Flow Paths - Table 3 Flow Fwd. Rev. Critical Exit Drop Path Loss Loss Comp Flow Loss Breakup Coeff. Coeff. opt: Model Coeff. Model 1 4.2Z43 4.2243 ON. TABLES 1. OFF 2 1. 0.78 ON TABLES 1. OFF 3 3.964 3.93 ON OFF 0. OFF 4 0. OFF TABLES 1. OFF S OFF OFF 0. OFF 6.- OFF OFF 0. OFF 7 OFF OFF 0. OFF 8 OFF OFF 0. OFF 9 OFF - OFF 0. OFF 10 OFF TABLES 0. OFF 11' OFF TABLES 0. OFF 12 OFF *OFF 0. OFF 13 OFF OFF 0. OFF 14 OFF OFF 0. OFF 15 OFF OFF 0. OFF 16 le+18 OFF OFF 0. OFF 17 OFF OFF 0. OFF 18 OFF OFF 0. OFF 19 OFF OFF 0. OFF 20 OFF OFF 0. OFF 21 :1.5 1.5 OFF OFF 0. OFF Thermal Conductors - Table I Cond Vol HT Vol HT Cond S. A. Init.

Description A Co B Co Type (ft2) T.(F) Or 1 Steamr Eposure 4 1 4 i 1 2965.72 609.23 I 2 Liquid Exposure 4 2 4. 2 1 11521.8 647.4 I 3 Torus, Vapor 2 3 2 5 2 13553.7 90. I 4 Torus, Liquid 2 *4 2 5 2 13553.7 90. I 5 Lower Drywell 1 5 1 6 3 1856.24 170. I 6 Lower Drywell 1 5 1 6 4 2041.28 170. I 7 Middle. Drywell 1 5 .1 6 5 3802.73 170. I 8 Middle Drywell 1 5 1 6 *6 780.68 170. I 9 Middle Drywell 1 5 1 6 5 1250.47 170. I 10 Middle drywell 1 5 1 6 7 1898.24 170. I 11 Middle Drywel l I 5 1 6 8 1114.72. 170. I 12 Top Orywell 1 5 1 6 13 783.45 170. I 13 Too Drywell I 5 1 7 14 1718.3 170. I 14 RRUs 1 5 1 6 11 1272.8 170. I 15 Vent Pipes 3 5 3 6 11 2885.7 160. I 16 Concrete Shield 1 5 1 6 12 2068. 152. I Modifications in /hcwne/Schor/vyc-2120ccnl/SENSITIVITY/SBO/drywel l -SBO/SBO-drywel 1-coment Mar/15/2005 14:07:44 GOTHIC Version 7.0p2(QA) - April 2002 File: /he/schor/vyc-212Vc//SENS TypeVITY/SBO/drywell-S80/5B0-drywel1-camnents Valve/Door Types Valve Stem Loss Flow Type Valve Travel Coeff. Area j 0ption Curve Curve (ft2) 3 QUICK OPEN 0 0 1.

12 CNECK VALVE 0 15 3.141 3 QUICK CLOSE 0 0 15.63

_Entery. Calculation VYC-2405 Rev. 0 Page 63 of 85 Y.

6.5.2 Case SBO-drvwell-comments Results The results of this case are presented in Figure 39 through Figure 40. Figure 39 presents the drywell tergperature. Due to the fact that the initial temperature for the drywell thermal conductors increase by 10 'F, the drywell temperature is increased from 289.4 TF to 295.2 OF.

The containment pressure (Figure 40) is identical to the Case 2, hence the changes in the vacuum breaker inputs have no effect on results, as described in section 6.2.1.

Figure 41, Figure 42, Figure 44 presents the drywell liner temperature. The drywell liner stays below 260 0 F for the 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months analyzed. After 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the low pressure pumps are available for suppression pool cooling, drywell spray and maintaining vessel inventory.

SWO - 8 0F-Noleak-drywell2 -snitivities-cents Mar/15/2005 14:03:50 GOThIC Version 7.Op2CQA) -April 2002 File: /homc/schor/vyc-2120ccn/SENSITrVITy/SBO/drYywell -SBO/S10-drywell-com

. [

Drywell Tenperatxlre TV1 L e - - - -

X.

UE1 e

Tixe (sec) s___ ___ ......2@ 2141s Figure 39 - Drywell Temperature - Case SBO-drywell-comments

7Entergy CalculatioriVYC-2405 Rev. 0 Page 64 of 85 w SDO - BOF-Noleak-dzrywell2-sensitivities-corients Mar/l5/2005 14:05:35 GOTHIC Version 7.0p2(QA) - April 2002 File: /homre/schor/vyc-2120ccn/SENSITIVITY/SBO/drywell -SEO/SBO-drywell-com Figure 40 - Containment Pressure - Case SBO-drywell-comments SDO - 80P-Noleak-drywell2-uensitivities-cocrents Mar/15/2005 14:04:06 GOTHIC Version 7-0p2(QA) - April 2002 File: /bome/s chor/vyc-212Dccn/SmSITIVITY/SBO/drywell-SEO/SBO-dzywell-com Figure 41 - Surface Temperature, Heat Structures 5,6,7 - SBO-drywell-comments

Entergy. .. CalculationVYC-2405 Rev. 0 Page 65 of 85 -

SBO - BOP-Noleak-dryveil2-sensitivities-coasentts Mar/15/2005 S.14:04:52 GOTHIC Version 7.op2(CA) - April 2002 Pile: /bome/schor/vyc-212 0ccn/SNSITIVITY/SBO/dxywell-SBO/SBO-drywell-comi Surface Teiperature 87 BT9 10 711 CD _-_---_

Si .,

CD

.v B

0 a.

-. 2 xle3 Tne (saec) 7-1i?*te a M.15/ZSOI 11.46,5 Figure 42 - Surface Temperature, Heat Structures 8,9,10,11 - SBO-drywell-comments SBO - 80F-Noleak-drywell2-sensitivities-cc ents Mar/15/2005 14:05:12 GOTHIC Version 7.0p2(QA) - April 2002 File: /home/schor/vyc-2220ccn/SENSITI.VTY/SBO/drywell-SBO/SBO-drywell-com Surface temperature TH13TB12 o _- . _ _ .

1.0 i

Time (sec)

.. J. ... S.

Figure 43 - Surface Temperature, Heat Structures 8,9,10,11 - SBO-drywell-comments

- - Entergy. ; Calculation WC-2405 Rev. 0 'P6.a Page 66 of 8 ^

SEO - 80P-Noleak- drywe12-sessitivities-comments Mar/15/2005 14:05:12 GOTIC Version 7.0p2(QA) - April 2002 File: /home/schor/vyc-2120ccn/SENSITfYIY/SBO/drywell -SBO/SEO-drywell-comn S2 Surface tenperature

=13=12 r"

co C4 neat Slab 12 B

d

$I. £41 L4 Cs

Nl

/Beat L 13.

.... I...t .. I.

I .

J. . .............

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Oa 14.4 (e 18 121.6 .2

'XSe3 Tize (seec)

-~n 9 l2tt*) -RtS12011 1A,5a1 Figure 44 - Surface Temperature Heat Structures 12,13 - Case SBO-drywell-comments

rEntery Calculation VYC-2405 Rev; O Page 67 of85 7.0 Results and Conclusions Assurringea Station Blackout with RPV depressurization (cooldown) at I hour after the event the following results and conclusions are found:

1) The drywell temperature .for all cases analyzed stays below the EQ drywell temperature profile for the entire SBO coping period of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and the additional 10 minutes to power the low pressure pumps (i.e., the drywell temperature for all cases analyzed stays below 300 TF for more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of transient).

2) The drywell liner temperature stays below the design temperature of 281 F for more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after the SBO event.

3) The drywell pressure stays below the design pressure of 56 psig.

4) For 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes the wetwell pressure stays below the PSP curve for. all cases analyzed.

5) The analysis shows that there is no need to spray the drywell when in the unsafe region of DWSEL.

6) There is enough inventory in the CST to insure that the CST is not depleted before the time of low pressure pumps availability such that the core stays covered. A CST inventory of 75000 gallons was assumed.

7) The maxim suppression pool temperature for all cases stays below 182.2 'F.

8) The analysis predicts a conservatively high drywell temperature. Several factors contribute to this conservatism:

The heat transfer from the vessel to the drywell -is based on a constant heat transfer coefficient at normal operating differential temperatures. However, this heat transfer coefficient will vary with the temperature difference to the 1/4 power based on the dependence on the Grashoff number.

The heat transfer to the drywell from the drywell heaters is not subtracted from the vessel.

The reactor building side of the thermal conductors are considered adiabatic.

A constant leakage is assumed; the leakage will decrease as the vessel is depressurized.

9) No restriction on the rate of cooldown is applied to protect the drywell temperature beyond the restriction of depressurization (cooldown) function of RHRSW temperature (Reference 1).

Note: "Unverified Assumptions" and "Affected Documents" items are being tracked via LO-VTYLO-2005-00135 (also see Section 4.1 and 4.2).

Entergy. Calculation VYC-2405 Rev. 0 Page 68 of 85 8.0 References The References are divided into Section 8.1 and General References (Section 8.2). Section 8.1 includes all references.

8.1 Design Input References and General

References:

1 VYC-2398 Rev 0 Torus Temperature Calculation for a Station Blackout Event at Extended Power Uprate, dated March 2005.

2 VY Tech Spec.

3 NUMARC 87-00, dated 11/20/87, including NRC accepted errata and Q&A from NUMARC seminars and Topical Report F.

4 VYC-2397, Maximum RHRSW Flow to RHRHX for SBO & Appendix R, dated 1/24/2005.

5 DRF 0000-0011-5646, OPL-4A (Containment Analysis Input Values) for Vermont Yankee Nuclear Power Station EPU/MELLLA+, dated 2/6/03.

6 Calculation VYC-1628 Rev 0, Torus Temperature and Pressure Response to Large Break LOCA and MSLB Accident Scenarios, dated 4/27/98.

7 George, T. L., et. al, GOTHIC Containment Analysis Package, Version 7.0, July 2001.

8 VYC-2208 "GOTHIC 7.0 Code Installation Validation and Verification at VY", dated July 18, 2002.

9 VYC-1457, VY Containment Heatup Analysis - Appendix R Application, dated 8/19/96.

10 GE Design Specification, No. 22A1 184, "Drywell Atmosphere Cooling System", Table I, Drywell Cooling Load Summary, #8 on Sheet 9.

11 VYC-1254 Rev 3, Containment and RPV Volume Calculations, dated 5/21/98.

12 VYC-1850 Rev I, OPL-4A Input Preparation, dated 6/22/99.

13 GE Design Specification # 22A1 182 Rev] "Protective Coatings-Special" 14 Drawing G191526 Rev 2.

15 J. P. Holman, "Heat Transfer", McGraw Hill Book Company, 1981.

16 Standard Review Plan Branch Technical Position CSB 6-1.

17 VYC-1628D Rev 0 CCN02, Torus Temperature and Pressure Response for to Appendix R and Station Blackout Scenarios, dated 06/23/2003.

.Entergy Calculation VYC-2405 Rev:0 Page 69 18 VYC-2279, Evaluation of EPU Impact on Ambient Space Temperatures During Normal Operation, dated 8/26/2003.

19 EQ Manual Vol 1.

20 22A12M5, Rev 1, Reactor Containment Design Specification, September 1969.

21 VY Drawing G191489 Rev 2..

22 VYC-1290 Rev 0, Vermont Yankee Post-LOCA Torus Temperature and RHR Heat Exchanger Evaluation, approved Augustl, 1994.

23 VYC-2045 Rev 0 Residual Heat Removal Heat Exchangers Fouling Factors and Projected Heat Rates for Cycle 21, dated 12/1/99.

24 GE-VYNPS-AEP-146, Letter Michael Dick (GE) to Craig Nichols (ENOD), VYNPS EPU Task T0400: Decay Heat for Containment Analysis dated March 10, 2003.

25 TE-2003-020, Feedwater Parameters for Power Uprate, April14, 2003.

26 VY Memo VYS 2000/39, P A Rainey/T. P. Bowman to J. R. Lynch, 'Torus Temperature/SW Design Temperature Recommendations", Aprill6,2000.

27 VY UFSAR Rev. 19.

28 OP 0105 Rev 11, Reactor Operation.

29 Crane Technical Paper No. 410, Flow of Fluids through Valves, Fittings, and Pipe, 1976 Crane Co.

30 EOP-3 Primary Containment Control, Rev3, dated 10/19/02.

31 ASME Steam Tables -Third Edition, 1977.

32 VYC-2306, Torus Temperature for Appendix R events at EPU Conditions, dated 08/29/2003.

33 VYC-1850A Rev 0, "OPL 4A Input Preparation", dated 7/28/99.

34 VYC-1628B Rev 0, "Torus Temperature and Pressure Response to Small Break LOCA Scenarios, Model Development", dated 11/3/98.

35 OE-3107 Rev 17, EOP/SAG Appendices dated 04/29/2004.

36 OT 3122 Rev 19, Loss of Normal Power, dated 04/18/2000.

37 EOP-1 Rev2 RPV Control, dated 10/19/02

!Entergy. CalculatioriVYC-2405 Rev. 0 Page 70 of 85 8.1 General References Georgej. L., et. al, GOTHIC Containment Analysis Package, Version 7.0, July 2001 GOTHIC 7.0 Code Installation Validation and Verification at VY, dated July 18, 2002.

ASME Steam Tables -Third Edition, 1977 J. P. Holman, "Heat Transfer", McGraw Hill Book Company, 1981 Crane Technical PaperNo. 410, Flow of Fluids through Valves, Fittings, and Pipe, 1976 Crane Co.

-Entergy - Calculation VYC-2405 Rev. 0 Page 71 of 85' -

ATTACHMENT 9.10 COMPUTER RUN

SUMMARY

SHEET COMPUTER RUN

SUMMARY

SHEET Page I of I Calculation No. VYC-2405 Revision 0 Date 16 March 2005 Sheet I of 1

Subject:

Drywell Temperature Calculation for a Station Blackout Event at Extended Power Uprate Code GOTHIC V7.0p2 Catalog No.02543 Version 7.0 SQA Classification Level A Run Title (variable, described in Section 6.0 and Att. A)

Run No. No Run Date ___By Output Use: Q Variable Values As Noted 0 Plot Attached 0 Disk. D File No._

Description Of Output:

Figures in text.

Input file on Disk.

Multiple cases were run, all are described in Section 6.0.

One case (base case) is attached in attachment A).

The Figures in text, for each case, have the date of the run & the run name.

Comments: None (Attached additional pages if necessary)

Review: 0 Information Entered Above is Accurate 0 Input Entry Accurate 0 Code Properly Executed (Based on User Manual) 0 Output Accurately Extracted or Location Specified Reviewer Comments /V,/ . e, Preparer (Print/Sign) Date Reviewer (Print/Sign) Date Liliane Schor Alan L. Robertshaw q 31 If g,-3//7/0

- Entergy . CalculationrVYC-2405 Rev;0 .. Page 72 of 85 '

Calculation Impact Review Pages (ENN-DC-126 Attachment 9.7)

From System Engineering ENN-DC-126 IREV. 4 I

PAGE 35OF57 ArrAcTAuE 9.7 CALtLATn IMPACTO R£VEW PAGE CALCULATION IMPACT REVIEW PAGE Date: 14 Febftearv 2005 §3OR . ONIQR (Note: X Indicates required distribuiion)

To: - Mechanical Engineering X ficensing X Operations

- I&C Engineering __Elect Maintenance - Chemistzy

- Electrical Engineering __I&C Maintenance _=HPfRadiological 1 , CNO Engineering __Mech Mtaitenance - Computer Applications X..System Engineering Component Engineering Rad Engineering lReactor Engineering Program Engineering ISI Engineering

=D0D0 Owner RHR. P. Perez __Nudear Engineenng - IST Engineering X DBD Owner SA. P. Perez _ EO - PSA (Name) (Other)

From: Lliane Schor 802-451-3013 (Orig~nator Print Name and Phone extension)

Calculation No VYCWC-2405 Revision No.0

Title:

Drywefl Temperature Calculation for a Station Blackout Event at Extended Power Uprate.

Reference:

NWA Dale Response Requtrort 16 February 2005 lESSAGE: Work organizations are requested to review the subject calculation (parns attadewd) to .

Identify Impacted calculations, procedures. Technical Specifications, FSAR sections. other design documnents (e.g.. EO files, DBID, Appendix R. ISIAIST, PSA, MOVs/AOVs, etc.) and other cdocuments.

which must be updated because cf the calculation results. Also provide the name of the individual responsibe for the action and the tracking nunber. The tracking item should include a requirement to ensure that any ER implementation associated with the Item is completed prior to revising the Impacted document. Sign and returm the form to the originator.

IMPACT REVIEW RESULTS:

Atfected Documents Responsible Tracking Remarks Individual Number RespordingSupervisor/Manager (ordesignee): &<re-m Ao-_ecw. 1 _ !Y_ as NaeSignature Date

~Entergy . Calculation VYC-2405 Rev. 0 Pagb 73 of 85 .

Calculation Impact Review Pages (ENN-DC-126 Attachment 9.7), Continued From System Engineering

@ I NUCLEAR Qcr RTS ENNlDC)12M I -REV. 4

-Enfery BIANAGfMTh UbL&-NtAL LO1 r PAGE 350F57 ATACHIJEWT 93 CALCULAuno 1PACT REvxw PAGE CALCULATION IMPACT REVIEW PAGE Date: 14 February 2005 001R E NOR (Note: X indicates required distributicn)

To: __Mechanical Engineering ) _Ucensing , _XOperaf5ons

- I&C Engineering _ Eled Mainlenance __Chemistry

_ Electrical Enginecring - I&C Maintenance HPIRadiogigcal Civil Enginering McchMaintenarce _ComputerApplitions

_XSystem Engineering - Component Engineering Rod a Engineering

Reactor Engineering - Program Engineeoing _ ISI Engineering X DBD Owner RHR. P. Perez _ Nuclear Engineering - 1ST Engineering X DBD Owner SA. P. Perez _ EO_ PSA

. (Name) (Other)

From: Liliane Schor 802W-451-3013 (Originator Print Name and Phone extension)

Calculation No.: VYC-2405 Revision No. O

Title:

Drywen Temperaturp Calculation for a SWton Blackout Event at Extended Power Uprate.

Reference:

WA Date Response Required: 16 February 2005 MESSAGE: Work organizaions arO requeosed to review the subject cakculation (parts attached) lo Identfy impacted calculations. procedures. Technical Specifcatons, FSAR sections, other design docirents (e.g.. EQ fliles, DD, Appendix R. ISS PSA, MO~s/AOVs. etc.) nd other documents, which must be updated because of the cakulation resuts Also provide the name of the irefdual responsble for the action and the racking number. The rackig item should include a requirement to ensure that any ER implemerdatoin'associaled with the Item Is cmnpleted prior to revising the impacted doament. Sign and retm the form to the onginator.

IMPACT REVIEW RESULTS:

Affected Documents Responsible Tracking Remark

_dividual Hunter '_

OP 4032 S. Jonaseb See attached cocnmemts Responding Supevisor/Manager (or designee): Stephen onasch 1 Name/5"ture I v Date

'E~Entergy Calculation VYC-2405 Rev. 0 Page 74 6f 85 1`

Calculation Impact Review Pages (ENN-DC-126 Attachment 9.7), Continued From RHR and SA DBD Owner AnTACHENT 9.7 CALCULATION hPAcT RErvEw PAGE CALCULATION IMPACT REVIEW PAGE Date: 14 Febntary 2005 on O NOR (Note: X indicates required distribution)

-To: MechanicalEngineering aX Ucensing *XOperations

= I&C Engineering __Elect Maintenance _ Chemnistry

- Electrical Engineering I&C Mantenance HPinadiological

_ CM1 Engineering __Mech Maintenance ComputerAppflcations

X System Engineering Component Engineering _ Rad Engineering

- Reactor Engineering - Program Engineering

__ ISI Engineering Xt DBD Owner RHR. P. Perez _ Nuclear Engineering IST Engineering X DBDOwncrSA..P.Perez = EQ PSA (Name) . (Other)

From: Utlane Schor 802-451-3013 (Originator Print Name and Phone extension)

Calculation No:-VYC-2405 Revision No. 0

Title:

Drywell Temperature Calcutation for a Station Btackout Event at Extended Power Urrate.

Reference:

.- A

Dat Response Required. 16 February 2005 MESSAGE: Work organizations pre ,requested to review the subject calculation (parts attached) to identify impacted calculations. procedures, Technical Specifications. FSAR sections. other design.

.docirnents.(e.g., EQ files, DBD. Appendix R. iSt/iST. PSA. NtOVs/AOVs. etc.) and cther documents, which must be updated because of the calcutation results. Also provide the rane of the individual -

responsile for the action and the tracking number. The tracking item should Include a requirement to -

.- ensure that any ER implementation associated wbh the Rem Is completed priorto revising the impacted document Sign and retrnm th lorrnito the originator.

IMPACT REVIEW RESULTS:

Affected Documents Responsible Tracking Remarfks

. individual Number .

. SA DBD P. Perez LO-TYLO- May need update for DryweU -

2005-00135 SBO assumptlons t Methodology

._ _ __ _ of VYC-2405.

Responding Supervisor/Manager (or designee): J :3-16f- Os

Name/k tr-" Is Date

-- Entergy Ca!culation VYC-2405 Rev. 0 Page 75 of 85 .'. .

Calculation Impact Review Pages (ENN-DC-126 Attachment 9.7), Continued From Operations - EPU Engineering P.

ATfACHmENT 0.7

CALCULAfON IMPACT REVIEW PAGE CALCULATION IMPACT REVIEW PAGE Dale: 14 February 2005 DOR QNOR (Note: X Indicates required distribution)

To: _ Mechanical Engineering X Licensing . XOperatLons

- I&C Engineering _ Elect Maintenance _-Chemistry

_ Electrical Engineering _ I&C Maintenance _ HPlRadiological

- Civil Engineering _ Mech Maintenance _Computer Applications XSystem Engineering ___Component Engineering . Rad Engineering

_-Reactor Engineering - Program Engineering _ ISI Engineering X DBD Owner RHR. P. Perez __Nuclear Engineering IST Engineering X DBD Owner SA. P. Perez _ EO _ PSA (Name) (Other)

From: Llliane Schor 802-451-3013 *

(Originator Print Name and Phone exlenslon)

Calculation No.: VYC-2405 Revision No. 0

Title:

Drywell Temperatuve Calculailon for a Station Blackout Event at Extended Power Uprate.

Reference:

N!A Date Response Required: 16 February 2005 MESSAGE: Work organizations are requested to review the subject calculation (parts ailached) to identify Impacted calculations, procedures. Tectnical Specifications. FSAR sections. other design documents (e.g.. EO files, DBD, Appendix RFISUIST. PSA, MOVs/AOVs. etc.) and other documents, which must be updated because of the calculation results. Also provide the name of the individual responsmble for the action and the 'trackingnumber. The tracking item should include a requirement to ensure that any ER implementation associated vith the rtem is cornpleted prior to revisig the impacted document. Sign and return the form to the originator.

IMPACT REVIEW RESULTS:

Aftected Documents Responsible Tracking Remarks

._ . indviduat Number EOP-3 Study Guide OT-3122 Lesson Plan for EOP-3 ON-3147 . .

ON 314S I Responding SupewvisorlManager (or designee): Bryan Croke 3/16/2005 Name/Signature Date.

'FEnterV

Calculation VYC-2405 Rev. 0 Page 76 o6f85 '

Calculation Impact Review Pages (ENN-DC-126 Attachment 9.7), Continued From Licensing

__NUCLYA1R QVALMnRZATID ENI4-DC-126 REV. 4

.gEne MIANAGENMENT MAUNUAL LNTOsmxONALVII PACE 35 OF 57 ArTACHMET 9.7 CALCULAloMN ImPpcT Rrvmew PAG9 CALCULATiON IMPAC1 REVIEW PAGE Date: 14 February 2005 OCR 0 NOR (Note: X indcales required distribution)

To: _ Mechanical Engineering X Ucensing _XOperations 1&C Engineering Elect Maintenance Chemistry Elredricai Engirneertg = I&C Maintenance =_HPRadiloglcal

- Civi Engineering _ Mech Maintenance __Computer Applications

_XSystem Engineering _Component Engineering Rad Enrineering Reactor Engineering - Program Engineering ISI Engineering X DBD Owner RHR P. Penez _ Nucdear Engineering IST Engineering X DBD Owner SA. P. Perez EQ . _ PSA (Name) (Other)

Frorn: Liliane Schor 802-4II-30Dt3 (Originator Print Name and Phone extension)

Calculation No.: YrC-2405 Revision No. 0

Title:

Diyeeil Tempreraire Calculation for a Statlon Blackout Event at Extended Power Uprae:

Reference:

NWA Date Response Requred: 16 February 2005 MESSAGE: Work organizations am requested to review the subject ccaiuation (parts attadhed) to Iderntly impacted calculations. procedures, Technictl Spocifcations. FSAR sections. othler design documents (e.g.. EQ files. DBD. Appendix R, tSVST, PSA. MOVsJAOVs. etc.) and other documents.

which must be updated because of the calculation'results. AJso provide the name of the individual responsible for the adcion and the traching number. The rack!ng ilem should Include a requ Fement to ensure that any ER implerentation associated vith the item is completed prior to revising the Impacted document Sign and return the form to thC originator.

IMPACT REVIEW RESULTS:

Affected Documents Responsible Tracking Remarks Individual J Number 05G

.7Pk ..C Ctl; Z','Aft4 __________

6 Responding SupervfsorManager (or designee): 5 OI;1A, cA n

_ la7?2- Ole NameJ1Sigkriatrz~e Date 60 61

~~ c~v.4~C~d-1-' - 7V !

P - IE7 -,q

.- , Entergy . Calculation VYC-2405 Rev.,0 " Page77df85' .1...

Calculation Design Verification and Review (ENN-DC-134)

'ENN-DC-1 34 REMsioN I ATTACHMENT 9.1 DESIGN VERIricAnoN COVER PAGE DESIGN VERIFICATION COVER PAGE El IP-2 OIP-3 ElAF [lOPNPS VYY Document No. VYC-2405 Revision O Page Of 8.

Title:

Drywell Temperature Calculation for a Station Blackout Event at Extended Power Uprate N Quality Related LiNon Quality Related DV Method: 0 Design Review JAltermate Calculation EJQualffication Testing VERIFI CATION DICPIEVER IFICATION CONMPETE AND COM.MENTS.

REQUI RED DISC.PLJNE RESOLVED (DV pinl, sigIn ard d3Ic)

O Electrical O] Mechanical Ol Instrument and Control

.DCivil/Structural Desien Eneineerint, Fluid SystemS c a p(

Alan L Robertshaw Q 2/I7/05 Puin Have Been Resolved nAlterComments Onginator Date:

Liliane Schor f l 5 I I Design Verification for VYC-2405 Page I of 8

Entergy Calculation VYC-2405 Rev.:O Page 78 of 85 1ENND<C-1 34 REVISION I ATTAcHMENT 9.7 CALCutIAnoN DESIGN VERFICAnON CHECKU5T IDENTIFICATION: DISCIPLINE:

Document

Title:

Drywell Temperature Calculation for a Station

Civil/Structural Blackout Event at Extended Power Uprate El Electrical Doc. No.: VYC-2405 Rev. 0 QA Cat. I T& C Verifier: Alan L. Robertshaw l EE Mechanical ula tmSitgn El2 Nuclear l.Esa dahiLetjif ror wri;wr tpforring 1 Other:

ON/A. Sip Desien Enzineering.

Fluld Systems METHOD OF VERTFICATION:

Design Reiew 0 Alternate Calculations E] Qualification Test' I Design Inputs -Were the Inputs correctly selected and Rercrecec Incorporated Into the design? Pagc No. Swigm 5 grVYC-2405 Desin inputs include desin bases, ptarnoerational codiitirns, perOrrflance OR requirenents, regulatory requirements and comnmtments, codes, standards, field data. etr. Al infornation used as desgn ksuts should have been P~rae~pb No. _______

reviewed and approved by the responsibe design orSnlzatiton. as applable.

AJtiputs need to be retrkievable or excerpts of docunents used should be Complteion orlthe Refeence Boses Is sttaahed. optional for as questionso.

See site specific design kIput procedures for quldance In Idenitrifyln hiputs.

Yes E No M NJA El Verifier Comments:

Sectiori 5.0, Input and Design Criteria, of VYC-2405. has been satisfactorily reviewed. Any identified Design Input needing verification is listed in Section 4.1 of VYC-2405 and tracked via LO-VTYLO-2005-00135 (see Itern #2of this Calculaition Design Verification Checklist). All other Design Tnput has been verified in VYC-2405.

Resolution: None needed.

Attachment 9.7 Calculation Design Verification Checklist Design Verification for WC-2405 Page 2 of S

-3Entergy - CalculatioiWVYC-2405 ReV. 0 Page 79 of 85 '

Assumptions - Have the assumptions been verified? Reference Page No. Cocnadon smhmir Pge mid Sea 4 1ot VYC-2405 Yes al No 0 N/A El OR Pa-.-pb No.

Verifier Comments:

Section 4. 1, Assumptions that need Verification or Implementation, and LO-VTYLO-2005-00135 CAD2, document identified "Unverified Assumptions" from VYC-2405 Drywell Temperature Calculation for a Station Blackout Event at Extended Power Uprate. The following lists the various "Unverified Assumptions' from VYC-2405:

1) 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months restoration of outside power (coping time).

2) 10 minutes to start RHR through the RHRHIX, 2 RHRSW pumps and CS.

3) Acceptability of using 75000 gal from CST (change of level setpoiit).

4) Maximum CST temperature of.135F.

5) The depressurization raie function of Service Water temperature needs to be verified and proceduralized as follows:

- For SW> 757F; depressurize the vessel at 800 F/hr or higher.

- For lower SW temperature (SW < 75MF) no restrictions on depressurization rates.

Upon verification of these assumptions, the calculation should be revised to convert the assumptions to Design Input and the calculation Status should be changed.

Resolution:

LO-VTYLO-2005-00135 CA02 has becn issued to track thcsc Unvcrificd Assumptions.

Upon verification of these assumptions, the calculation should be revised to convert the assumptions to Design Input and the calculation Status should be changed.

3. Quality Assurance - Is the Quarrty level corred? Rcfcrencc Page No. (2ovr Mxx4 of VYC-2405 Yes No El NIA Or-:phNo Verifier Comments: VYC-2405 is correctly designated 'Quality Related."

Resolution: None needed.

Attachment 9.7 Calculation Design Verification Checklist Design Verification for VYC-2405 Page 3 of 8

-'Entergy . .

Calculation VYC-2405 Rev. 0 Page 80 of 85 I;<;-3

!Codes,Standards and Regulatory Requirements'-

Are the applicable codes, standards and regulatory NpCeNn.

requirements, induding issue and addenda properly OR identified and are their requirements fordesign met? PagnphNo.

Yes Nofl NIA __

Verifier Comments: Appropriate use of requirements (inputs, assumptions, methodology) set forth in the VY Technical Specifications and UFSAR have been followed in VYC-2405 as needed.

Resolution: None needed.

5. Operating Experience - Have applicable construction and Rcferiiiee operating experience been considered? Page No. _ _ _ _ _ _ _

. OR Yes No a N/A [3 Parawr`111o.

Verifier Comments:

Consideration (discussions and reviews) has been given to various timelines for operator actions, equipment start times, cooldown rates, etc. Some Unverified Assumptions exists which will rely on. in part, to VY operating experience (e.g., two hour restoration of outside power (coping time of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 10 minutes), ten minutes to start .RHRflow through the RHRHX, the use of 2 RHRSW pumps and CS, and the acceptability of using 7O5O gal from CST (change of level setpbint). See Item #2, Assumptions, of this Calculation Design Verification Checklist.

Resolution: Consideration has been given to VY operating experience. Some Uriverified Assumptions exist (for which commitments have been issued). See Resolution of Item iW2, Assumptions, of this Calculation Design Verification Checklist.

6 Interfaces - Have the design interface requirements been Refrence satisfied and documented? Page No.

OR Yes ED No El N/A El rParm ph No.__

Verifier Comments:

The relationship between the Fluid Systems ("design group") and other organizations within W have been satisfactorily met using the Calculation Impact Review Page. The Calculation Impact Review Page was completed by persons in the Operations Department, System Engineering, Licensing, and various DBD owners.

Resolution:

None Needed.

Attachment 9.7 Calculation Design Verification Checklist Design Verification for WC-2405 Page 4 of 8

- Entergy CalcUlation VYC-2405 ReV. 0 Page 81 of 85

7. Methods -Was an appropriate analytical method used? Rrefrcaz P. PaeNa. Sectin 3 otfWC-2405 Yes 0 No .[ NIA fl OR Pmgnsphl4To.

Verifier Comments:

The GOTHIC code (Reference 7 & 8 of VYC-2405), Version 7.0p2 was selected for use in VYC-2405.

Resolution: None Needed.

8 Design Outputs - Is the output reasonable compared to the Rtcrvrtcv inputs? lye No.

OR Yes.[O No l N/A 0 hwrvuphNo.

Verifier Comments- The output is reasonable compared to the inputs. Previous, similar Drywell SBO analyses are familiar with the preparer and reviewer of this'SBO calculation and thus the output given in VYC-2405 was reasonable for the various changes and rnodifications made to the previous input.

Resolution: None Needed.

9. Acceptance Criteria -Are the acceptance criteria Rtcrczncr incorporated inthe calculation sufttident to allow verification Pas No. S&xtion 2.1 yrVYC-2405 that design requirements have been satisfactorily OR accomplished? Pngapi No.

Yes 0 No D N/A 0 Verifier Comments:'

Section 2.1 nus added to include the Acceptance Criteria.

Resolution:

None Needed.

Attachment 9.7 Calculation Design Verification Checklist Design Verification for VYC-2405 'Page 5 of 8

.-- Entergy ."* CalculationiVYC-2405 Rev. 0 '- Page 82 of'85 . ,. . . -

Records and Documentation -Are requirements for Refervace record preparation, review, approval, retention, etc-, T'ae No. ~Somnniw4.2 of V C-240S adequately specified? OR Are addocurnmnts prepared in a cyear lWOWk marner suitable formicrofitrning andlor paniraapb No. _ _ _ _ _ _ _

Mter documentation storage rnetthod? Have at irrpacted documents been identried for update?

Yes E No -11 NIA El Verifier Comments: VYC-2405 was prepared in a clear legible manner suitable for microfilming and/or other ddcumentation storage method. All impacted documents (Design Output) have been identified for update in Section 4.2 of VYC-2405 and in LO-VTYLO-2005-00135 CAO.L Resolution: LO-VTYLO-2005-00135 CA01 has been issued to track these affected documents.

If any other documents are identified during the Calculation Impact Review process, other commitments will be generated.

It. Software Quality Assurance- For a calculation that utilized Rererenace software applications (e.g., GOTHIC, SYMCORD). was it page )zo. Sacejnr, 3 of VYC-24(5 properly verified and validated in accordance with ENN IT- OR 104 or previous site SQA Program? P es-agraph No. _ _ _ _ _ _ _ _ _

Yes E No [E N/A El -

Verifier Comments: The GOTHIC code (Reference 7 & 8 of VYC-2405), Version7.'0p2 was selected for use in VYC-2405. This code was used in similar SBO analysis (References 1 of VYC-2405). This specific version of the code has been installed and complies with the ENVY SQA procedures ENN-IT-104 (replaced VY procedure AP-6030) as documented in calculation VYC-2208 (Reference 8 of VYC-2405).

Resolution: None Needed.

OTHER COMMENTS See Attached list or General comments from review of VYC-Z405 RESOLUTIONS Attached General comments have been made to reviewer's satisfaction.

All comments for "NO" answers have been resohled satisfactorily.

Attachment 9.7 Calculation Design Verification Checklist Design Verification for WC-2405 Page 6 of 8

.. AdEntergy Calculation VYC-2405 Rev. 0 ' Page 83 of85" General Comments from Alan L. Robertshaw from Review of VYC-2405 (Attached to Calculation Design Verification Checklist)

In Section 2.0, Add addition Section (2.1) entitled "Acceptance Criteria" and add appropriate acceptance criteria.

Done

In Secton 3.0, discussion of GOTHIC code and V&V calculation need appropriate references.

Done

In Section 4.0:

1. For Assumption #4. please correct the units for density (value is correct)..

2. For Assumption #9. add that 61 gpm is from Reference 3.

3. Add VYC.2306 to Reference (from Diywell Free Volume of Table 3).

Added

In Section 5.0:

1. In Section 5.3.1 , show in more detail how total Heater #5 loads are calculated.

Done

2. In Section 5.4, recommend addition of"simple' drawing ofDrywelI Done

3. In Section 5.4 show that the total Surface Area adds up to the Value obtained from OPL-4a (i.e.. Table A Total = 15246.06 ft2, RRUs = 1272.8 ft2 , Vent Pipes - 2885.7 f 2 ,thus Total - 19405 ft2 ).

Atded

4. Add to description of Item 8 "Side of Drywell Head."

5. Add to description of Item 9 'Top of Drywell Head."

Done, both items

6. Is RRU area Re&rcnce 11 or 12 or other? Please correct if needed.

Both, added

7. Flow Path 21 Forward and Reverse loss coefficients should reference CRANE (or similar), data not found in steam table. Need to add CRANE to references Done

8. Please add additional information on new valve added (vacuum breaker, Valve #5.

e.g.. size, type, etc.).

Done Design Verification for WC-2405 Page 7 of 8

.Entergy . Calculation VYC-2405 Rev. 0 Page 84 bf 85

9. Also for Valve discussion, note that the valve area'is different from the line area used in Flow Path 21 Added

10. Initial Temperatures of the Thermal Conductors are not given (and reference).

Added I 1.Please further explain why a loss coefficient of 3.964 was used instead of the calculated value of 3.93 for the vacuum breaker flow path. Any impact on analysis?

I added this discuvsion in thre document, I also said that the difference is less than 1% and will make no difference on the analysis. Anyway, wvas correctedin Case S.

In Section 6.0:

1. List Five case individually to add clarity.

Done

2. See minor grammatical / spelling concerns noted in marked-up calc draft Done

3. Section 6.2.1 please add info on Flow Path 21 (Leakage) area change.

Done

In Section 8.0, Reference Section:

1: Need to add Reference for ASME Steam Tables and one for CRANE Technical Paper (if needed)

Added

2. Are References 11 and 13 used?

Yes, Reference 11 and 12 are RRU references and 13 ivfor thepaint (addedsome more dEscusvion about the paint)

In the GOTHIC Input Deck, Thermal Conductor #16, Concrete Shield, a surface area value of 2108 f 7 was used. A value of 2068 ft2 was given in the text of VYC-2405 (Section 5.4). Both of these numbers are found on page 35 of VYC-1 850, Rev. I for OPL-4A preparation. The larger value (2108 ft2) is for total surface area, the smaller value (2068 fi2) subtracts the

'Slots." The value used in VYC-1 850, Rev. 1 CCN-01 (OPL-4A, Resolved for Analysis) uses the 2068 ft2 value. Please discuss this in the analysis and determine which value to use, any sensitivities, etc.

Case 5 addresses this.

In Attachment A, it appears that Figure on page Al4is a duplicate figure and should be removed.

Removed Design Verification for VYC-2405 Page 8 of 8

'Entergy - Calicultiof VYC-2405 Rev. 0 Page 85 of 85' Files on CD

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Wednesday. March 16.2005 5.03:11 PM

BVY 05-072 Docket No. 50-271 Exhibit SPSB-C-52-5 Vermont Yankee Nuclear Power Station Proposed Technical Specification Change No. 263 - Supplement No. 30 Extended Power Uprate Response to Request for Additional Information Calculation VYC-2279, Rev.0 l Total number of pages in this Exhibit I (excludina this cover sheet) is 14. l

This documcnt contains Vermont Yankee proprietary information. This information may not be transmitted in whole or in part, to any other organization without permission of Vermont Yankee.

VY CALCULATION T1TLE PAGE VYC-2279 0 NIA N/A_

VY Calculation Numbnr Revision Number Vendor Calculation Number Revision Number

Title:

Evaluation of EPU impact on Ambient Space Temperatures During Normal Operation QA Status: 0 SC O NNS El OQA Operating Cycle Number N/A lThe Operating Cycle Nuniber should only be entered here if the results of the calculation only apply during a specific operating cycle otherwise enter "NIA'.

Calculation Supports A Design Change/Specification? 0 Yes O No VYDC 2003-008_ _

VYDC/MMflM/Spec No.

Implementation Required? ED Yes Ol No Calculation Done as a Study Only? [ Yes [ No Safety Evaluation Number. N/A Superseded Calculation Number, Title and Revision: NIA For Revisions: List CCNs, lUs, or SAs incorporated/superseded by this revision: N/A Computer Code(s): None used Are there open items in this calculationlrevision? 0 Yes E No Review and Approval: (Print and Si am Preparer. Gene O'I3rien Dat 12K103 Interdiscipline (Heat Balance, Att. B only) Preparer(s): N. Zevos Dat:

Interdiscipline (ileat Balance, Ant. B only) Revie V ): R. SriniDat:

IndependentReviewers tansour ojibian Approved: PA Date: ?OW 02 Accepted (only for 0p 1,fugti s performedb vendors) l N/A 7V _ E A .I ph10D

-c:,Y2-003 1_ .

Final Turnover to DCC (Section 2):

1) All open items, if any. have been close&

2) Implemcntation Confirmation (Section 23.4) Total No. Pages in Package 64 (including all attachments) 0 Calculation accurately reflets existing plant configuration, (confirmation method indicated below) o Walkdown [l As-Built input review Q] Discussion with (Print Name)

OR El N/A, calculation does not rclect existing plant configuration

3) Resolution of documents identified in the Design Output Documents Section ofVYAPF 0017.07 has been initiated as required (Section 2.3.6.23.7)

/ I Printed Name Signature Date Page I of 28 Pages I For calculations performed using AP 0017 this is the number of pages in the body of the calculation. VYAPF 0017.01 For vendor calculations, this is the number of pages of AP 0017 forms added. AP 0017 Rev. 8 (Title page, review forms, data sheets, 50.59, etc.) Page I of 1 LPC *2

Calculation Number: VYC-2279 Revision Number: 0 CCN: 0 Page 6 of 28 TABLE OF CONTENTS SECTION PAGE NO.

VY CALCULATION TITLE PAGE ........................................ I VY CALCULATION DATABASE INPUT FORM .2 TABLE OF CONTENTS .6 I Calculation ........................................ 7 1.1 Objective .7 1.2 Summary of Results .7 1.3. Method of Solution .. 8 1.4 Inputs and Assumptions ..................................... 10 1.4.1 Inputs .10 1.4 .2 Assumptions .14 1.5 Calculation .14 1.6 Results .............. 26 1.7 Conclusion .27 Attachments .............. 28 Attachment A. Al Attachment B.. BI Attachment C .CI Attachment D. D Attachment E. El

CALCULATION NUMBER VYC-2279 Rev. () CCN 0g I'a-e,7 of 28 I Calculation 1.1 Objective The purpose of this calculation is to evaluate ambient temperature increases in several plant spaccs following the increase in reactor power level to 102% of 120%, hereafter referred to as Extended Power Uprate (EPU). The EPU will increase core thermal power from the current licensed level of 1593 MWt to 1912 MWt. For bounding purposes, the 122% (1950.9 MWt) heat balances are used for EPU HVAC evaluations.

This calculation evaluates the EPU impact on ambient air temperature in the following buildings or areas during normal plant operation:

Reactor Buildina a Drywell Sem un ai -(eiherReactor Building Areas Turbine Building

Reactor Feed Puump Room

Condensate Pump Room

I]P Heater Area (including steam line shelf containing main steam lines)

LP Heater Area Note: Comments to this calculation provided by letters l'UIPVY-03-208 dated 7/16/03 and PUPVY 212 dated 7/18/03 have been reviewed and incorporated (see Attachment D).

Increases in area heat gain and ambient air temperatures, as a result of El'U, are predominately caused by increases in operating temperature of piping systems, and equipment, and air-cooled motors operating under increased loads. The preuprate piping system temperatures are selected or extrapolated fi-om a PEPSE Neat Balance that is tuned to match preupr-ate (cunrcnt) plant data. The EPU piping system temperatures are selected or extrapolated from a PEIPSE Heat Balance that provides the most conservative results.

Affected areas are evaluated to determine the temperature gain due to increases in heat loss from piping and mechanical equipment.

1.2 Summary of Results The results of this calculation show the effects of the EPU in terms of increased ambient temperature and heat load are due to increased feedwater temperature, as well as increased horsepower from the condensate and feedwater pumps. The ambient temperature increases are specified in Section 1.6 (Results).

Calculation Number: VYC-2279 Revision Number: 0 CCN: 0 Page 8 of 28 1.3. Mlethod of Solution This calculation evaluates the temperature increase in a specified area using current fluid and ambient air temperatures and EPU fluid temperatures to predict the EPU ambient air temperature and corresponding temperature rise. PEPSE Heat Balances at 100% CTP and EPU at 122% CTP (References 7 and 8) are used to obtain preuprate and EPU piping temperatures. The increase in heat loss from piping is determined by comparing the ratio of "temperature differential between EPU pipe and area air temperatures" to "differential temperature between pre-uprate pipe and pre-uprate area ambient air".

The basis for using this scaling approach to determine increased heat loss from piping and equipment can be obtained by referencing the ASHRAE Fundamental Handbook (Reference 12) Section 20.

Formula (9) - ASHRAE 20.9 is used for flat surfaces FIX=tj-t .*/

Formula (10) -ASHRAE 20.9 is used for cylindrical flat surfaces q%=(t^,-t os) / [r, In (r1/ri)]/k, + [r, In (rj/r 1)]/k, Formula (11) -ASIHRAE 20.9 for determining heat flow per area of pipe surface

q. =q, (r,^ A ;)

Where q, = rate of heat transfer per unit area of outer surface of insulation q0 = rate of heat flow per unit arca of pipe surface, Btu/(hr)(ft2 )

R = surface to surface thermal resistance k thermal conductivity of insulation at calculated mean temperature.

ti, = Temperature of inner surface t= Temperature of outer surface T= inner radius of insulation rl, r2 = outer radius of intermediate insulation r,= outer radius of insulation In = natural or Napernian logarithm For the purposes of this calculation it can be assumed that there is one layer of insulation, therefore Formula 10 can be simplified as follows:

q, =(t[k-t u.. / [rs In (r1/rj)]/kj The increase or delta in heat transfer per unit area of insulation can be stated as follows:

Aq =EPU [(tr-t iS) / [i^ In (r1/rj)]/k,] / pre-EI3U[(tj.-t no) / [rI In(r/r 1)]/k1 ]

There is no change in either: ri, r,, or rl,.

Calculation Number: VYC-2279 Revision Number: () CCN: 0 Paige 9 ot 29 Based on the predicted temperature increases in the various process streams it can be assumed that there is no appreciable change between the preupratc and EPU values for k.

Therefore Aq = EPU [(t1,-t O / pre-EPU[(t;,-t ,^)

Present station operating ambient air temperatures are used in the evaluation. If operating data is not available, plant design area temperatures are used. An iterative process using an Excel spreadsheet is utilized. First, an EPU ambient air temperature is estimated. Next, the EPU area heat gain multiplier is obtained using the ratio of the EPU pipe / ambient air temperature difference to the preuprate (current) pipe / ambient air temperature difference as shown below:

(EPU pipe temperature - EPU ambient air temperature) = EPU Area Heat Gain Multiplier (preuprate pipe temperature - preuprate ambient air temperature)

The EPU factor is obtained by subtracting I from the EPU heat gain multiplier.

The EPU factor is then multiplied by the preuprate temperature difference between the air in and out of a particular air handling unit to calculate the estimated EP'U temperature rise. The temperature rise is then compared to the difference of estimated EPU and preuprate ambient air temperatures. If required, a new EPU ambient air temperature is estimated and the process repeated until the temperature rise is equal to the difference of estimated EPU and preuprate ambient air temperatures.

rQr Feedwvater and Condensate pumps, flows from preuprate and EPU PEPSE Heat Balances along with appRriate pump curves will be used to determine horsepower changes in the respective pump motors to determ thbee heat gain increase to the room. The percentage increase in heat gain to the room will be utilized with e temperature rise of ventilating/cooling air currently being supplied to the room or area being evaluated\

The heat load from the ensate and feedwater pumps is evaluated by calculating brake horsepower (BHP) at preuprate and EPU ws. BlIP is calculated using the following equation from page B-9 of Refercnce ]14:\

Bhp (hp) = Q(gpm)*H(tl)* p(lbWft 3 ) / [2 0

pump efficiency]

The flow, Q, is calculated from the mass flow rate cified on the heat balance using the fluid density, p, calculated at the average of pump inlet and outlet tem natures. The pump head, 1S, and efficiency are obtained from the pump curve.

The heat generated is due to pump motor inefficiency and is cal ted using Chapter 26, Equation 21 from Reference 12:

q (BTU/hr) = BHP (hp)*2545 (BTU/hr hp) *[100-% efficiency]/ % effici The heat load due to the pump motor inefficiency is calculated for preuprate and conditions. The overall heat removal capability of the coolers at preuprate conditions is determined an sensible heat load due to piping is obtained by subtracting pump heat load from cooler heat removal capac The piping heat load at EPU is scaled due to the increase in fluid temperature and added to the EPU p heat load to obtain total heat load for the room. The temperature increase across the coolers is calculated u g Equation 39.6(b) from Reference 13:

Calculation Number: VYC-227'9 Revision Number: 0 CCN: 0 l1a;> 1 0 ot2X

__hr cfm*I 108 Btumin(R3hr °F))]

Boththe eedwter~aluated nd in this manner.

1.4 Inputs and Assumptions 1.4.1 Inputs The inputs for this evaluation are the fluid temperature in system piping and ambient room temperature of the areas considered. The pre EPU fluid temperatures are obtained from a PEPSE heat balance based upon current plant operating data adjusted to 5.00" Hg. condenser backpressure to obtain maximum fluid temperatures (Reference 7). For those cases where the fluid temperature is not explicitly listed, the temperature is obtained based upon the pressure and enthalpy listed using ASME steam tables (Reference 9). The EPU fluid temperatures arc obtained from the 122% heat balance with a condenser pressure of 5.00" Hg (Reference 8) which provided the highest, and therefore conservative, temperatures.

The current ambient steam tunnel and pump room temperatures are obtained from HVAC system design criteria (Reference 5). The main steam tunnel design temperature is ] 30 0 F, the reactor feedwater pump room and condensate pump room design temperatures are 105'F. The current HP and LP heater area temperatures are 125 0F as taken firom the Environmental Qualification Program Manual (Reference 6, page I1). The 20'F Pre-EPU Vent/Cooling Air AT contained in the Table below for the HP and LP heater area spaces is based upon transfer air at ] 05'F.

The design conditions for the air handling units are obtained from Reference 4, except for TRU-5 and TSFIAIIB, which have their design conditions specified in Reference 19.

Table 1.4-1 Area Equip. ID Flow, cfm Tin( 0 F) Tout(0 F) AT Reactor Feedwater Pump Room TRU- ],-2,-3,-4 16,750 1 05 85 20 Condensate Pump Room TRU-5 21,400 105 85 20 -

Condensate Pump Room TSF-IA/]B 5,000 90 105 15 Drywell RRU-],-2,-3,-4 16,000 1 35 97 38 Main Steam Tunnel RRU-17A, -17B* 5000 130 105 25

Per Reference 18, the coils for these coolers are incon ectly piped as parallel flow rather than counter flow The design inputs for piping are summarized in the table below:

Table 1.4-2 Pre-EPU pipe Temp EPU pipe Temp Pre-EPU ambient air Pre-EPU Vent/Cig

'F (Ref. 7) 'F (Ref. 8) Temp 'F Air AT 'F la1P Heater Are-a--_

ESS to FWHI _ 3 403.7 125.0 20.0 FWHI Shell _____3.7383.3 125.0 20.0 FW to FWH1 330.7 346.4 125.0 20.0 FW Ivg FWH1 374.4 392.6 125.0 20.0 Drains lvg FWH I 343.6 356.9 125.0 20.0

Calculation Numher: VYC-2279 Rlevision Number: 0 CCN'3: () lI'; I11 of 28 Prc-EPU pipe Temp EPU pipe Temp Prc-ElU ambient air Prc-EPU Vent/CIg

°F (Ref. 7) . F (Ref. 8) Temp °F Air AT °F ESSto FWII.2'l 338.0 358.1 1 125.0 __ 20.0 FWI12 Sell 338.0 358.1 125.0 20.0 FWtoFWI 299.3 312.5 125.0 20.0 FW FW112 \ _g 330.7 346.4 125.0 20.0 Drains Jvg FWH2 309.7 322.6 125.0 20.0 IJI' lleater Area \_l _ __ _

ESS to FWI-]3 3NA.4 321.2 125.0 20.0 FWH3 Shell 305.4 321.2 125.0 20.0 CND to FWI-3 227.6 238.4 125.0 20.0 CND lvg FWH3 296.6 \309.8 125.0 20.0 Drains lv-g FWH3 235.0 24 4 125.0 20.0 ESS to FW114 239.0 252.1 \ 125.0 20.0 FWH4 Shell 239.0 252.1 125.0 20.0 CND to FWH4 167.9 180.9 \ 125.0 20.0 CND lvg FWH4 227.6 238.4 12 0 20.0 Drains lvgFWIJ4 175.1 189.1 125.0 \ 20.0 ESS to FWH5 173.9 181.8 125.0 20.0 FWH5 Shell 173.9 181.8 125.0 20.0 CND to FWH5 135.1 134.7 125.0 \20.0 CND Ivg FWH5 167.9 180.9 125.0 20 Drains Ivg FWH5 '145.1 141.8 125.0 20.0 CND Pump Rloomr CND to CNP 133.8 133.8 105.0 20.0

Calculation Number: VYC-2279 Revision Number: 0 CCt.N: () line L-12 of 28 Pre-EPU pipe Temp El'U pipe Temp Pre-EPU ambient air Pre-EPU Vent/CIg

°F (Ref. 7) °F (Ref. 8) Temp °F Air AT OF 133.1 . __ 133.1 _ 105.0 20.0 CND to RFP 296.6 _105.0 20.0 FW lvg RFP 299.3 2 312.5 200_

Main Steamn lunnel l . .

-.. FW Ivg FWI13 374.4 392.6 _130.0 25.0 Main Steam 547.6 547.6 130.0 25.0_

Pump information:

Reactor Feedwater Pumps Tabne 1.4-3 Preuprate (Reference 7) EPU (Reference 8)

Flow 64 8048044 lb/hr P!of RF2's 21 3 per pump 3203763 Ib/hr 2 6 826 -STWhw Tin 296.6 °F 309.8 °F Tout 299.3 °F 312.51°F Condlensate P'umpls Table 1.4-4

_Preuprate (Reference 7) l El'U (Reference X)

Flow ~ --6-5261Ib/hr 8076444 Ib/hr f/ of CNrs 3 -- _ 3 per pump 2145842 lb/hr _2692148 Ib/hr lTin 133.8 °F -OF ITout 133.1 OF 133.1 ° Drywell information (Reference 17):

Drywell Cooling Load Summary*

Table 1.4-5 Comp one Btu/hr Reactor Pressure 459,000 Recire. Pumps, Valves, a 278,000 Feedwater Pipe & Valves 124,000 Steam Pipe & Valves 212,000 Condensate & Instrument Lead 82,000 Lines

Calculation Number: VYC-2279 Revision Number: () CCN: () Page 13 of 28 Component Btu/lhr l Control Rod Drive Pipe __0,400 Control Rod Drive Pipe 569,000**_/

Clean-up Demineralizer Pipe & 17,800 Valves _ _

Shutdown Supply Pipe 8,100 Steam Safcty/Relief Valves 206,600 Biological Shield (Gamma 16,400 H-leating) /

Safeguards system Piping (RCIC, 82,000 LPCI, ]PCI, and core spray) l_ _

'Sensible l eat Gain Total, Normal 1,536,300

/ Operation Steam Lea}, Valves /155,000 Latent Heat Gain Total, Normal 155,000

/~ Oeration Total Cooling Load, Normal Operation 1,691,300

Excluding allowance for drywcll cooler motors

- Temporaiy initial load immediately following scram

Calculation Number: VYC-2279 Reischiion Number: 0) CCN: 0 Page, 14 of 28 1.4.2 Assumptions For the piping in the e e, it is assumed the feedwater piping contributes 1/3 to the total heat gain and the main steam piping contributes 2/3 due to their respective surface areas. This is based upon the fact there are four 18" main steam lines and two 16" feedwater lines. From Reference 14, the external surface area of four 18" pipes is4* 4.712 ft2 per foot of pipe= 18.848 ft2 per foot of pipe and the external surface area of two 16" pipes is 2

4.189 ft2 per foot of pipe 8.378 ft2 per foot of pipe. No confirmation is required.

It is assumed there is no appreciable change between the preuprate and EPU values for the thermal conductivity, k, of the pipe insulation based on the predicted temperature increases in the various process streams.

1.5 Calculation Piping:

A sample calculation for the estimated temperature rise from the feedwater piping in the steam tunnel is shown below.

Preuprate pipe temp. (0 F) 374.4 Reference 7 EPU pipe temp. (0 F) 392.6 Reference 8 Preuprate ambient air temp. (0F) 130 Reference 5 Preuprate Air Handling Unit 25 Reference 4 (RRU-I 7A, 130 - 105 = 25)

(AlIU) AT ( 0F) I I The EPU ambient air temperature is initially estimated at 131 'F. [used for initial iteration and checked later]

The EPU Area Heat Gain Multiplier is obtained using the equation in Section 1.3.

EPU Area Heat Gain Multiplier = (EPU pipe temperature - EPU ambient air temperature)

(preuprate pipe temperature - preuprate ambient air temperature)

EPU Area Heat Gain Multiplier = (392.6 - 131))F (374.4 - 130) 'F EPU Area Heat Gain Multiplier = 1.070 The EPU factor is obtained by subtracting I from the EPU Area Heat Gain Multiplier:

EPU factor= 1.070 -1 = 0.070 From Assumptions section, the feedwater piping contributes 1/3 to the total heat gain in the main steam tunnel, so the EPU factor becomes:

EPU factor= 0.070 *1/3 EPU factor= 0.023

Calculation Number: VYC-2279 RevisiOnl Numiber: 0 CCN: () Page 15 of 28 The temperature rise is then calculated by multiplying the EPU factor by the AHU temperature differential.

Temp. rise = 0.023

25.0F = 0.586 The difference between estimated EPU and preuprate ambient air temperatures is:

131 - 130 = 1 (this is not close enough to the calculated temperature rise of 0.586'F)

Try a different EPU ambient air temnperature of 130.6 and repeat the process.

Preuprate pipe temp. (F) 374.4 Reference 7 EPU pipe temp. (0F) 392.6 Reference 8 0

Preuprate ambient air temp. ( F) 130 Reference 5 Preuprate AHU AT (0F) 25 Reference 4 (RRU-1 7A, 130 - 105 25)

The EPU ambient air temperature is estimated at 130.6 'F.

The EPU Area Heat Gain Multiplier is obtained using the equation in Section 1.3.

EPU Area Heat Gain Multiplier = (EP'U pipe temperature - EPU ambient air temperature)

(preuprate pipe temperature - preuprate ambient air temperature)

EPU Area Heat Gain Multiplier = (392.6 - 130.6)

(374.4 - 130)

EPU Area H-leat Gain Multiplier = 1..072 The EPU factor is obtained by subtracting I fiom the EPU Area Heat Gain Multiplier:

EPU factor= 1.072 -1 = 0.072 From Assumptions section, the feedwater piping contributes 1/3 to the total heat gain in the main steam tunnel, so the EPU factor becomes:

EPU factor= 0.072 *1/3 EPU factor = 0.024 The temperature rise is then calculated by multiplying the EPU factor by the AHU temperature differential.

Temp. rise = 0.024

25.00 F = 0.6 0 F The difference between estimated EPU and preuprate ambient air temperatures is:

130.6 - 130 = 0.6 (this equals the calculated temperature rise of 0.6 CF)

The temperature rises for the remainder of the pipelines was calculated using the same method using an Excel spreadsheet.

The results are shown in Table 1.5-1.

CALCULATIONNI.UINIERVYC.2279Rev.0 CCNO Page 16of 28 Table 1.5-1-@Design Tenperature DifferentbaI ess.in I 7 AMs J7 nIS

07 PS e_. C... 0 075 a t A rws" VI w* 07 s 12 0 INS to c S. or o-at 2D IWIA " "Do Yl, '50 *75 '070 S. C- Dooe Mt D_3 b 16 79 *70 12 IRA I CI S.XC7- A. 00% me *s _ It ~_ .

,- P4 3's pal21 w s0 in AM?8 'S.CA-A 0S .700 I rWa sat Y e In 1 4 5 I M t70 C- ~ _*cm e s X t4 3- 4r-+Q r07t l m7S Azmls 5'o S. 0050 eo 1 cmn r* 7wA]Is 7r0

i Iwo S. C-.,- ace 0 050JO A 260 139 M 5'C-S.sr 'm . Me o .

eze P-0 ne 7.M

. 7l@_

rM r7r0Dt*7 0 0. _ .1" " ' ~

CSft. C- 0W m. elz7' S_7190 7 52 750 . _ ! s . -

Ae 4e O .,en eoW1 cgrwW 7A A ~o m . e c ~ to ._s _

rnI ~ oa tn*o P a . IV is S. C_- 0". ntrO 21

k It rvn e . 70 7log...!"-ce-Ze x

on., t ~ Im o I l M_7V~ 1 en Dpa. e ~ o a ' 'n 5u _ ~t ~ 2e l #--

oC-s0 ~s 7`6 d _.-Aw _

. 5. . `. _ l .,P C.; W. A-X rWw"4AAA. . " . .. 1 M~~ seoZe0 /b*1

_, rVO Zee*

5"_oo cro431 c WAn, - OTVmO0 oosts tsc. wrw IIe_00N _3D 1_.o AA -I AA_1_. sa _-

KM Z S. . I-o r *non ej oosw'w",o i_ De_ , t0WE S St l . ~~wroatOloe m s _c or (A)

Calculation Number: VYC-2279 Revision Number: 0 CCN: 0 Page 2() of 28 The Total Cooling Load for Normal EPU Operation is: 1.700.675 BDm The ratio of cooling loads to differential temperatures is qcp1 / qpre = ATcpi, / ATpre ATp, = (qep.

ATprc)/ qprc = (1,700,675 B y (135- 97) 0F) / 1,691,300 BTU/hr 0

ATtp,, = 38.21 F Since ATpre = 135 - 97 = 38'F The increase in dryw perature due to the higher feedwater temperature is:

AT = ATCpT 38.2- 0 F38 0 F Pallmmbient drywel I temperature at EPU is 135 'F + 0.2 'F = 135.2 '

Main Steam Tunnel (RRU-17A, -17B )

q (Btu/hr) = cfm

1.08 (Btu min/fl3 hr "F) * [Tin - Tout]rF q ='5000 cfm

1.08 (Btu min/fl 3 hr TF) * [130 - 105]°F q = 1.35 x 105 Btulhr The main steam tunnel piping is evaluated using the Excel spreadsheet described above. As stated in the assumption section, the temperature rise fi-om the feedwater piping is "weighted" at 33% based upon its surface area ratio when compared to main steam piping. The increased feedwater temperature will result in an ambient temperature increase of approximately 0.6TF to 130.60 F. As previously noted, the service water to RRU-17A&B is piped backwards, such that there is parallel flow rather than counter flow (Reference 18). Because of this, both coils are in continuous operation rather than the initial design of one in operation and the other as a back-up. The minimal increase in ambient temperature due to EPU will not adversely affect current operation due to the fact the current peak allowable tempcrature in the tunnel is 1500 F (Reference 6, pg. 10). Also, per Reference 6, Section 7.5.2.5, the high space temperature alarm set point is 160 0 F and the MSIV close/scram set point is 200TF.

Reactor Feedwater Pump Room (TRU-1,-2,-3,-4 Theat removal capability of the reactor feedwater pump room is:

q (Btu =cfm

1.08 (Btu min/fl 3 hr TF) * [Tin - Tout]rF q =4

167 fm

1.08 (Btu minft hr 'F)

1105 - 85]rF q=I.45xI0 6 B w From above, the preuprate hi oad due to two pumps operating is 0.97 x 1O6 Btu/hr and the EPU heat load due to three pumps operatin.47 x l Oh Btu/hr.

Using the heat removal capability with a olers running, the preuprate heat load due to the piping is:

1.45 x 1O0Btu/hr - 0.97 x 106 Btufhr = 0.50 x 10I Btu/

The temperature scaling method using the preuprate and EPU e ances shows the ambient temperature will increase 1.27F.

The EPU increase in piping heat load due to higher feedwater temperature can bea imated using:

qpre = MCpATp, and qep,, = nCAT,, \

Since mC. is the same preuprate and EMU, qepu / qp, = AT~p / ATpr, or qCpu = qpr. *(ATp,, / ATpre)

Calculation Number: VYC-2279 Revision Number: CCN: 0 Page 26 of 28 Ti ireas tlha contain condensate and feedwater piping are the only areas that will expieicnce an ambient tempeN re increase during normal operation due to EPU. The following systems will not experience an ambient teniperaturc increase during normal operation due to EP'U: Reactor Recirculation (RRS), Reactor Core Isolation Ong (RCIC), Residual Heat Removal (RIIR), Reactor Water Clean Up (RWCU), High Pressure Coolant Injec HPCI) and Core Spray (CS) (References 20 through 25).

Reactor Building open areas Temperatures in the open areas of the reat iding will not increase during normal operation as a result of EPU (Reference 26).

Control Room As shown in Calculation VYC-1502 (Reference 28), Section 2.1, heat sour the control room are from electrical equipment, ambient outside air temperature, and personnel. None se sources will increase at EPU. Therefore, the Control Room HVAC system's ability to provide appropr mperature and humidity conditions for personnel and equipment during all modes of operation and emergen condition is not impacted by EPU.

1.6 ]Results The results of this calculation are shown in Table 1.6-1 below.

Table 1.6-1 Area EPU Ambient Temperature Increase (TF)

DTgcll 0.2 Main Steam Tunnel 0.6 Ll' Heater Ai-ea 4.1 1-11' Heater Area 1.7 Feedwater Pump Room 7.6 Condensate Pump Room 3.5 T inc r t heigp *i5ac- is The ncrasein ainsteam tunnel ambient temperature due to the hi-her EPU fecdwtater temperature is T e results of the piping evaluation are shown in Table 1.5-1. At normal operating EPU conditions, the amazs i temperature in the LP heater area will increase approximately 4.1 0 F to 129.1 F and the HIP heater area will in e I .70 F to 126.71F.

The increase in feedw mp room ambient temperature due to the higher EPU feedwater temperature is 7.6 F to 1 2.6 OF. This res as achieved using both design and empirical information.

The increase in condensate pump roomemperature due to the higher EPU feedwater temperature is 3.5 'F. The ambient temperature in the condens ump room at EPU based upon design information is I 13.2 'F and 122.5 0F based upon empirical data.

It is noted that the temperatures obtained in this calculation are conse c maximum temperatures for the purposes of obtaining bounding temperature increases within the subjecta Actual EPU maximum temperatures are anticipated to be lower than those calculated.

ML052220464

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