ML20071D251: Difference between revisions

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Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:233 MAR 0 71983 Dr. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:233 MAR 0 71983 Dr. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555


==Dear Dr. Grace:==
==Dear Dr. Grace:==
DECAY HEAT REMOVAL SERVICE OPERATING CASES AND SENSITIVITY EVALUATIONS, PRELIMINARY SAFETY ANALYSIS REPORT (PSAR) TABLE 5.6-12
DECAY HEAT REMOVAL SERVICE OPERATING CASES AND SENSITIVITY EVALUATIONS, PRELIMINARY SAFETY ANALYSIS REPORT (PSAR) TABLE 5.6-12


==Reference:==
==Reference:==
Letter HQ:S:82:149, J. R. Longenecker to P. S. Check, " Meeting Summary for the Shutdown Heat Removal Meeting, December 10, 1982," dated December 20, 1982 It has been noted that an error has been made in updating the PSAR (Amendment 76) to incorporate Action No. I from the referenced letter.
Letter HQ:S:82:149, J. R. Longenecker to P. S. Check, " Meeting Summary for the Shutdown Heat Removal Meeting, December 10, 1982," dated December 20, 1982 It has been noted that an error has been made in updating the PSAR (Amendment 76) to incorporate Action No. I from the referenced letter.
Enclosed is the corrected PSAR Table 5.6-12. This corrected table will be included in a future PSAR amendment.
Enclosed is the corrected PSAR Table 5.6-12.
This corrected table will be included in a future PSAR amendment.
Any questions regarding tne subject item can be addressed to Mr. D. Florek (FTS 626-6188) or Mr. A. Meller (FTS 626-6355) of the Project Office Oak Ridge staff.
Any questions regarding tne subject item can be addressed to Mr. D. Florek (FTS 626-6188) or Mr. A. Meller (FTS 626-6355) of the Project Office Oak Ridge staff.
Sincerely, d.
Sincerely, d.
J n R. Longene     r av Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution p
av J n R. Longene r
Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution p
8303090298 830307 PDR ADOCK 05000
8303090298 830307 PDR ADOCK 05000


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DHRS                                           NUm ER     NUMER         NUMER                           EVST                         NA                                 NAK OPERATING                     PEAK               OF PHTS   OF IHTS       OF DHRS         (X)NSERVATIVE HEAT                           FLOW                               FLOW CASE (1)               TEMPERATURE             LOOPS     LOOPS         TRAINS           DECAY HEAT     LOAD                         GPM                                 GPM Design                   - 11200F                 3           0             2               Yes         Yes                         560                                 800 Case                                                                       ,
DHRS NUm ER NUMER NUMER EVST NA NAK OPERATING PEAK OF PHTS OF IHTS OF DHRS (X)NSERVATIVE HEAT FLOW FLOW CASE (1)
(2)
TEMPERATURE LOOPS LOOPS TRAINS DECAY HEAT LOAD GPM GPM Design
Updated                 ~ 10520F                 3           0             2               YesW       Yes                         560                                 800 Design Case Single                    ~10550F                  2(3)       2             1             Naninal       No                           600                                 600 Fail ure                                                                                   Values Evaluation #1                                                                               Used 1137                                                                 (2)
- 11200F 3
SIngie                   2.-11SOM--               2           0             1               Yes'f E - No                             600                                 600
0 2
                                    ?           Failure
Yes Yes 560 800 Case (2)
                                    ?           Evaluation #2 w
Updated
M' Deleyed                 a 1078                   3           0             2               Yes42_ Yes                                560                                800 Start Design Case (V 45 minutes to OHRS operation)
~ 10520F 3
0 2
YesW Yes 560 800 Design Case 2(3)
Single
~10550F 2
1 Naninal No 600 600 Fail ure Values Evaluation #1 Used 1137 (2)
SIngie 2.-11SOM--
2 0
1 Yes'f E - No 600 600
?
Failure
?
Evaluation #2 w
M' Yes42_ Yes 560 800 Deleyed a 1078 3
0 2
Start Design Case (V 45 minutes to OHRS operation)
(1) Conservatisms included in all cases: Shutdown at end of cycle at full powers no consideration of Insulation, no consideration of SGS heat capacity.
(1) Conservatisms included in all cases: Shutdown at end of cycle at full powers no consideration of Insulation, no consideration of SGS heat capacity.
                                                -ff)--Exceeds present-flHRS-hot-teg-temperature-Haft-of-H400Fs---                                 ,
-ff)--Exceeds present-flHRS-hot-teg-temperature-Haft-of-H400Fs---
(2)-0)- Decay heat values he.'s Lwn revised to reflect current conservative design values i
(2)-0)- Decay heat values he.'s Lwn revised to reflect current conservative design values (3)-(4)- The hvo RiTS loops assumption conservatively envelopes the assumption that a MITS pop or pony motor falls to operate.
(3)-(4)- The hvo RiTS loops assumption conservatively envelopes the assumption that a MITS pop or pony motor falls to operate.
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Latest revision as of 06:52, 15 December 2024

Forwards Corrected PSAR Table 5.6-12 Covering DHR Operating Cases & Sensitivity Evaluations to Be Included in Future PSAR Amend
ML20071D251
Person / Time
Site: Clinch River
Issue date: 03/07/1983
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Grace J
Office of Nuclear Reactor Regulation
References
HQ:S:83:223, NUDOCS 8303090298
Download: ML20071D251 (2)


Text

...

Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:233 MAR 0 71983 Dr. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Dr. Grace:

DECAY HEAT REMOVAL SERVICE OPERATING CASES AND SENSITIVITY EVALUATIONS, PRELIMINARY SAFETY ANALYSIS REPORT (PSAR) TABLE 5.6-12

Reference:

Letter HQ:S:82:149, J. R. Longenecker to P. S. Check, " Meeting Summary for the Shutdown Heat Removal Meeting, December 10, 1982," dated December 20, 1982 It has been noted that an error has been made in updating the PSAR (Amendment 76) to incorporate Action No. I from the referenced letter.

Enclosed is the corrected PSAR Table 5.6-12.

This corrected table will be included in a future PSAR amendment.

Any questions regarding tne subject item can be addressed to Mr. D. Florek (FTS 626-6188) or Mr. A. Meller (FTS 626-6355) of the Project Office Oak Ridge staff.

Sincerely, d.

av J n R. Longene r

Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List Standard Distribution Licensing Distribution p

8303090298 830307 PDR ADOCK 05000

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DHRS OPERATING CASES AND SENSITIVITY EVALUATIONS i

l t

DHRS NUm ER NUMER NUMER EVST NA NAK OPERATING PEAK OF PHTS OF IHTS OF DHRS (X)NSERVATIVE HEAT FLOW FLOW CASE (1)

TEMPERATURE LOOPS LOOPS TRAINS DECAY HEAT LOAD GPM GPM Design

- 11200F 3

0 2

Yes Yes 560 800 Case (2)

Updated

~ 10520F 3

0 2

YesW Yes 560 800 Design Case 2(3)

Single

~10550F 2

1 Naninal No 600 600 Fail ure Values Evaluation #1 Used 1137 (2)

SIngie 2.-11SOM--

2 0

1 Yes'f E - No 600 600

?

Failure

?

Evaluation #2 w

M' Yes42_ Yes 560 800 Deleyed a 1078 3

0 2

Start Design Case (V 45 minutes to OHRS operation)

(1) Conservatisms included in all cases: Shutdown at end of cycle at full powers no consideration of Insulation, no consideration of SGS heat capacity.

-ff)--Exceeds present-flHRS-hot-teg-temperature-Haft-of-H400Fs---

(2)-0)- Decay heat values he.'s Lwn revised to reflect current conservative design values (3)-(4)- The hvo RiTS loops assumption conservatively envelopes the assumption that a MITS pop or pony motor falls to operate.

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