3F0897-48, Provides Results of Recent Calculations for Demonstrating 10CFR50 App R,Section III.L.1(d) Cooldown to Cold Shutdown Conditions within 72 H

From kanterella
(Redirected from 3F0897-48)
Jump to navigation Jump to search
Provides Results of Recent Calculations for Demonstrating 10CFR50 App R,Section III.L.1(d) Cooldown to Cold Shutdown Conditions within 72 H
ML20217R324
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/29/1997
From: Rencheck M
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0897-48, 3F897-48, NUDOCS 9709050051
Download: ML20217R324 (3)


Text

_ _ _ _ _.

p Florida Pswer CL Dated No. s0 302 August 29,1997 3F0897 48 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Results of Calculations for Verifying Appendix R Cooldown Requirement to Cold Shutdown Within 72 Hours

References:

A. NRC to FPC letter,3NO397-10, dated March 10,1997 B. FPC to NRC letter, 3F0497-11, dated April 10,1997 C. NRC Memorandum to File, dated July 30,1997 " Transmittal of Attachment D to the Minutes of Restart Panel Meeting for Crystal River"

Dear Sir:

This letter provides the results of Florida Power Corporation's (FPC's) recent calculations for demonstrating 10 CFR 50 Appendix R, Section Ill.L.1(d) cooldown a

to Cold Shutdown conditions (200'F) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This closes item 15 in E

Attachment D of the Restart Panel Meeting minutes in Reference C.

M.

EE.

In Reference A, the Nuclear Regulatory Commission (NRC) requested FPC to E=-

confirm that Crystal River Unit 3 (CR-3) can meet the design basis Appendix R m-requirements for cooldown to Cold Shutdown conditions in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Reference B provided the results of calculations conducted in 1992 which demonstrated that CR-3 could cooldown to 280 F within 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />, it was further estimated that accommodation for natural circulation cooldown limits would add an additional 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to this time and that the remaining time to cooldown from 280 F to 200 F, t'

.h CRYSTAL RIVER ENERGY COMPLEX:1s7so w Po*

une st.. c,vii i %.e. riorio 3442s a70s. <3s23 7ss s4as am L

u m e,me,c n r b

9709050051 970829 PDR ADOCK 05000302 F

PDR

t U. S. Nuclear Regulatory Commission 3F0897 48 Page 2 using the Decay Heat Removal System, was sufficient to assure meeting the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Appendix R Section Ill.L 1(d) requirement.

In support of FPC's restart commitments, under Restart issue OP-19A "ADV's/72-hour Cooldown Calculation for Atmospheric Dump Valves", a re-analysis of the CR-3 Appendix R cooldown requirement to Cold Shutdown conditions has been t

completed. The key input parameters and results of this analysis are provided in. With additional conservative assumptions, the results demonstrate cooldown on natural circulation to 280'F within 57.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (includes an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> hold at Hot Standby) and cooldown from 280'F to 200'F, using the Decay Heat Removal system, in 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This analysis reconfirms the CR-3 design basis requirement under 10 CFR 50 Appendix R, Section Ill.L.1(d) for achloving Cold Shutdown conditions within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The full analysis is available on site for NRC review as desired, if you have any questions regarding this letter, please contact D. F. Kunsemiller, Manager, Nuclear Licensing at (352) 563 4666.

Sincerely, b

M. W. Rencheck Director, Nuclear Engineering and Projects MWR/jnb Attachment xc:

Regional Administrator, Region ll Senior Resident Inspector NRR Project Manager

e N

-- f a

e 6

U. S. Nuclear Regulatory Commission 3F0897-48 Page 3 ATTACHMENT 1 FLORIDA POWER CORPORATION CALCULATION NO. F 97 0010 Revision 1 10 CFR 50 APPENDlX R, SECTION lil.L.1(d) COOLDOWN TO COLD SHUTDOWN CONDITIONS (200'F) WITHIN 72 HOURS Key input Parameters Parameter Description input Value(s)

- ANSI /ANS 5.1 1979 decay heat

- I l

Decay Heat correlation with 3 cycles of core irradiation at 725 EFPD per cycle Initial Power Level 102% core power Post Fire Hold Time at Safe Shutdown / Hot Standby Conditions Before 8 Hours loitlation of Cooldown Maximum RCS Cooldown Rate 10 F/ hour Subcooling Margin 60*F Makeup Temperature

- 125'F Atmospheric Dump Valve (ADV) 301,246 lbm/ hour / valve, T = 540*F, Nominal Flow P = 948 psig (saturated conditions)

Number of ADVs Operable 2

Emergency Feedwater Temperature 95'F i

Containment Temperature

-1 3 0 F._

Key Results Result Description Result Value

-Time to Cooldown to 280*F (includes 8 Hour Hold Time at Hot Standby 57.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Conditions)

Emergency Feedwater Required 284,420 gallons Time to Cooldown from 280'F to 200 F 9.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> -

CONCLUSIOR Cooldown to Cold Shutdown Conditions (200*F) in 66.3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />s-

=

w