ML20125B508
| ML20125B508 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/03/1992 |
| From: | William Cahill, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-92567, NUDOCS 9212100034 | |
| Download: ML20125B508 (6) | |
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EssaiEE Gi Log # TXX-92567 C """"
File # 10010 2-0 905.4 Ref, # 10CFR50.34(b) 77 TUELECTRIC December 3, 1992
% l!!).im J. Cahill, Jr.
Gr~p Ver hmiver U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET N05, 50-445 AND 50-446 ADVANCE FSAR SUBMITTAL - RCS C00LDOWN TIME AFTER RHR INITIATION Gentlemen:
s The attachment to this letter provides an advance CPSES FSAR submittal to facilitate the NRC Staff review of the subject area in support of licensing Unit 2.
The attachment is organized as follows:
1.
A description / justification of each change.
2.
A copy of the revised FSAR paa ", (changes are indicated in the margin by the word 'DR.u,*),
The attached material will be incorporated in CPSES FSAR Amendment 87 which is currently scheduled for December, 1992.
If you have any questions regarding this submittal, please contact Mr. Manu Patel at (214) 812-8298.
Sincerely, William J. Cahill, Jr.
sy:
/
D. R. Woodlan s
Docket Licensing Manager MCP/vid Attachment c-Mr. J. L. Miihoan, Region IV Resident inspectors, CPSES (2)
Mr
- 1. A. Bergman, HRR Mr. B.
E. Holian, NRR l
07n040 ji 9212100034 9212c" bhf
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tt totTXX;92567.- ' CPSES i FINALL SAFTEY ANALYSIS REPORT.(FSAR)-
.jY2 J
' AMENDMENT ~'I REVISION 87-DETA! LED DESCRIPTION.
Pagef1 i
Profix Page 2
(31 magnded)
- faE.gge Descrf otion J
. ]
~5.-4-51 2-
_ Change sentence 2 of paragraph 2 from-350 degree F to 140 degree F within:24 hours."
J to 350 degree F to 140 degree F within 2E hours."
g Revision The Safe Shutdown Impoundment (SSI) temperature.
profile has been re-calculated and found to differ from temperature profile used in the original Westinghouse'RHR cooldown calculations.
Accordingly, i
Westinghouse has utilized the latest temperature profile and revised the RHR cooldown capabilities..
These changes reflect the revised RHR cooldown.
capabilities based on the revised SSI temperature profile.
T'.ange Request Number
- SA-92-8;l.1 Commitment.Pegister Number :
Related SER : 5.4.3.2 SSER :22 5.4.3.2 SER/SSER Impact t No 5,4-51 2
Change first sentence of paragraph 3 from:
350 degrees F to 200 degrees F within 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br />."~
to 350 degrees F to 200 degrees F within 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />."
Revision See Justification from SA-92-811.1.
Change Request Number
- SA-92-811.2 Commitment Register Number.:
Related SER : S.4.3.2 SSER :22 X.4.3.2 SER/SSER Impact
- Yes _
SSER 22, Section S.4.3.2 "Cooldown Time With One Train." states "... the RHR systemLis capable of reducing the temperature of the reactor coolant from 350 degrees F.to 200 degrees F (cold shutdown) within 21-hours.
5.4-51 2
Change last sentence of paragraph 3 from:
350 degrees F to 212 degrees f is 11.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />."
to 350 degrees to 212 degrees F is within 12' hours."
Revision See Justification for'SA-92-811.1.
Change Request Number SA-92-811.3 Commitment Register Number Related'SER :"5.4.3.2 SSER :22 5.4.3.2 SER/SSER Impact No Table 5.4-7' 2
Change "Cooldown time" from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to-28 hours.
Revision See. Justification for SA-90 611.1.
' Change Request Number
- SA-92-811.4 5
2 Attachmnt - to TXX-92567 Pay 2 of 5 CPSES - FINAL SAFTEY ANALYSIS REPORT (FSAR) i AMENDMENT-/ REVISION 87 DETAILED DESCRIPTION Pag 2 Profik Page (n gefnded)
GrovD D.ncription Commitment Register Number :
Related SER : 5.4.3.2 SSER :22 5.4.3.2 SER/SSER Impact
- No Figure 5.4-9 2
A new f?qure reflects the revised RHR system rooldown capabiiities.
Revision See Justification for SA-92-811.1.
Change Request Number
- SA-92-811.5 Commitment Register Number :
Related SER : 5.4.3.2 SSER :22 5.4.3.?
SER/SSER Impact
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CPSES/FSkR Nuclear plants employing the same RHRS design as the CPSES are given
~
in Section 1.3.
5.4.7.1 Desian Bases RHRS design parameters are listed'in Table 5.4-7.
The RHRS is placed in operation approximately 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> = after reactor shutdown when the temperature and pressure of the RCS are approximately V00F and 425 psig, respectively. Assuming that two
' DRAFT heat exchangers and two
- mps are in service and that each heat exchanger is supplied with component cooling water at design flow and maximum temperature, the RHRS is designed to reduce the tempterature of -
the reactor coolant from 3500F to 1400F within 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
The time required, under these conditions, to reduce reactor coolant 68 temperature from 3500F to 2120F is 2.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The heat load handled by the RHRS during the cooldown transient includes residual and decay heat from the core and reactor coolant pump heat. The design heat load is based on the decay heat fraction that exists at 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> following reactor shutdown from an extended run at full power.
Assuming that only one heat exchanger and pump are in service and that DRAFT the heat exchanger is supplied with conponent tooling water at design flow and maximum temperature, the RHRS is capable of reducing the temperature of the reactor coolant from 3%0F to 2000F within 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />. The time required under these conditions, to reduce reactor coolant temperature from 3500F to 2120F is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The RHRS is designed to be isolated from the HCS whenever the RCS pressure exceeds the RHRS design pressure. The FHRS is isolated from the RCS on the suction side by two motor operated valves in series on each suction line. Each motor operated valve is inter'iocked to 83 prevent its opening if RCS pressure is greater than 425 psig. The RHRS is isolated from the RCS.on the discharge side by two check 5
5.4-51 Draft Version w
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t adgt to TXX C2567 CPSES/FSAR TABLE 5.4-7
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DESIGN BATES FOR RESIDUAL HEAT REMOVAL SYSTEM OPERATIQji Residual Heat Removal System startup
~4 hours-after reactor shutdown Reactor Coolant System initihl pressure (psig) 125 Reactor Coolant System initial temperature (OF)-
-350 Component cooling water maximum temperature (OF) 122 68 Cooldown time (hours after initiation of Residual Heat Renoval System operation) 28 DRAFT Reactor Coolant System temperature at cad of cooldown (0 )
140 F
Decay heat generation at 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after reactor shutdown (Btu /hr) 78.2 x 106 1
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m 00MANCHE PEAK S.E.S.
FINAs SAFETY ANALYSIS REPORT UNITS 1 AND 2 5
SINGLE TRAIN RHR COOLDOWN DRAFT.
FIGURE 5.4-9 a
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