ML20040A433
| ML20040A433 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 04/30/1976 |
| From: | Bunch D Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201210077 | |
| Download: ML20040A433 (3) | |
Text
-.
a 4
l
.m-
\\
g 30 1976 Docket No.: STM 50-5641 nichard C. DeYotsag, Assistant Director for Light Water Reactors, DPM ~ ~
Q1 IMPUT FLANT MAME: B-SAR-205 ~
LICENSING STAGE: CP (PDA)
DOCKET NUMBER: STd 50-566 MTLESTONE NUMBER: 03-31 RESPONSIBLE BRANCH: LWR #1, T. Cox, LPH REQUF.STED COi!PLETION DATE: April 26, 1976 REVIEW STATUS: AAB Input Complete Attached is the AAB's Q1 input. As B-SAR-205 is a nuelaar steam s,vpply system the AAB review is limited to the accident analysis areas in Section.
r 15.
(
. E. Murphy conducted the review.
4/
D. F. Bunch, Chief Accident Analysis Branch Division of Site Safety and Envirr== ental Analysis
~
Distribution S. Hanauer W. MGonald, w/o encl.
Q1 In or B-SAR-205 H. Denton J. Panzarella, w/o encl.
D. Crutchfield P. Shuttleworth, w/o encl.
R. Vollmer Docket File J. Miller NRR Reading
,.S. Varga AAB Reading R. Boyd AAB File J. Stolz DSE Reading j
L T. Cox D. Bunch K. Murphy 8201210077 810403 PDR FOIA MADDEN 80-515 PDR ADh/SE AAB:DSE SD_
Y
~
. del
-EV. Qae, evanau mars >
/ I7b 4QQ.2A 4 -M 6 4
/76 roem ABC.)tt (Rev. 9 5)) AECM 0240 1lt u. s.sovsanusuf paintine orrecas tota.ese. sos
/
/
+
4
.--e.
A t
i APR 3 0 m
..r
~
Docket No. :. STN 50-566 l
l r
[
Richard C. DeYotsag, Assistant Director for Light Water Reactors, DPH ' ~
Q1 INPUT l
PLANT MAME: B-SAR-205 LICENSING STAGE: CP (PDA)
DOCKET NUMBER: STd 50-566
[
MILESTONE NUMBER: 03-31 RESPONSIBLE BRANCH: LWR #1, T. Cox, LPM REQUESTED C011PLETION DATE: April 26, 1976 REVIEW STATUS: AAB Input Complete t
Attached is the AAE's Q1 input. As B-SAR-205 is a nuclear steam s,upply l
system the AAB review is limited to the accident analysis areas in Section.
E. Murphy conducted the review.
l 4f
- ~
i D. F. Bunch, Chief I
l Accident Analysis Branch Division of Site Safety and Enviran= ental Analysia Distribution Enclosure
- S. Hanauer W. Mcdonald, w/o encl.
l Q1 Input for B-SAR-205 t
H. Denton J. Panzarella, w/o encl.
D. Crutchfield P. Shuttleworth, w/o enc 1.
R. Vollmer Docket File l
J. Miller NRR Reading
,.S. Varga AAB Reading R. Boyd AAB File
[J.Stolz DSE Reading T. Cox D. Bunch K. Murphy i
i j
l s
?
AAB:DSE AD
/SE Spf
, y errice >
..../ krihy/b/ W-RIRtQ
~
-EHV meg AM/76 ~
_4.1e7/76 422926 c
/.y,
_ve.
perus ABC.)t3 (Rev. 9 93) ARCM 0240 W u. s. eovsnmasewf pnewfine orrects seta.ooe.see
.,.~.7 f
-33.1_1 s
(~.
- K...J. 0 ACCIDENT. ANALYSIS BRANCH SECTION A l
311.6 Appendix 15A, Radiation Sources, should provide a discussion and data on iodine spf. king as a result of reactor pressuri and temperature changes.
Iodine spiking should be considered in the. environmental consequence analyses of the ste na line break and steam generator tube
,/
rupture accidents (see SRP 15.1.5 and 15.6.3).
Provide the requqpted data for the appendix and update the appropriate accident sections.
311.7 It is stated that Table 15.1.16-3 summarizes the assumptions'used in (15.1.16) determining the radiological assumptions of a waste gas decay tank rupture. The table is missing and should be supplied.
i 311.8 The last paragraph on page 15.1.18-6 appears to conclude that no fuel (15.1.18) melting occurs as a result of the worst rod ejection accident. Verify that this is true. If fuel melting is calculated to occur, modify the outline of the radiological consequence analysis to ' conform with the guidelines of Regulatory Guide 1.77 regarding fuel melt.
h e
8 4
e e
e N
i k
.s e
=* m W e +,
- - - _ - - _ - _ _ _ - _ _ _ _