ML20039A192
| ML20039A192 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/14/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TASK-15-07, TASK-15-7, TASK-RR LSO5-81-12-038, LSO5-81-12-38, NUDOCS 8112160343 | |
| Download: ML20039A192 (3) | |
Text
_-
4 December 14, 1981 Docket No.50-029 LS05-81 12-038 7
Mr. James A. Kay Senior Engineer - Licensing Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Kay:
SUBJECT:
YANKEE ROWE - SEP TOPIC XV REQUEST FOR ADDITIONAL INFORMATION We have reviewed the topic assessment on the above topic that you submitted on June 30, 1981 and we find that additional infonnation is needed to com-i plate our safety evaluation.
Please provide the requested information within 30 days of receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, 05 clearance is not required under P.L.96-511.
Sincerely.
Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing I
Enclosure:
- 1. Request for Additional Infonnation[~ I f ry,.
/
i t-cc w/ enclosure:
DR w 6 V'g
/>
See next page 8
/
b 400; OfCN
~
/
9 W.g 9.- %kgg'?.7 4.-Q
'O
~2 h o /Ty Of I
c gilg,16 0 y
\\
bnGh/
3?fM4/ n ORE OkBi5C k$dSA:0L SE SENb
'"]} Sb i@i~(5PM......... f.. 6".". ".".,.... ({.666f
'dlidnas
.....SEf.D.d2.{
omer)
................1.."...
"C""" "Nii"iiill" ~
..E.M..cKenna :d p' SURNAME >
....../.3 '../.81.........')...........
..1. 2. f..... 8.1....
..1. 2.././.a[./. 8.1.......
..12../.10../. 81 12 12/^ /8
...1. 2../..o. 3..../. 8.1...
o,re >
, eme ronu sis co-soi sncu o24o OFF1CIAL RECORD COPY use m ini-ass *a
4 A
Mr. James A. Kay YANKEE R0WE Docket No. 50-29 CC Mr. James E. Tribble, President Yankee Atomic Electric Coapany 25 Research Drive Westborough, Massachusetts 01581 Greenfield Coccunity College 1 College Drive Greenfield, Massachusetts 01301 Chai rman Board of Selectmen Tcwn of Rowe Re.se, Massachusetts 01367
' Energy Facilities' Siting Council-lath Floor One Ashburten Place Bcston, Massachusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN: EIS COORDINATOR JFK Federal Buiicing Boston, Massachusetts 02203 Resident Inspector Yankee Rcwe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 m
-~
wy -
h
~-
l.Q 6
ENCLOSURE a
' YANKEE R0WE SEP TOPIC XV-7, REQUEST FOR ADDITIONAL INFORMATION '
. - 1.
For the complete loss of forced reactor coolant flow (trip of all four pumps) event, 'please provide the calculated minimum DNB ratio.
Also please provide the amount of fuel failure (assuming any fuel rod which has a DNBR less than the minimum allowable DNBR value for Yankee Rowe plant fails) and the estimated radioactive release-
.during the transient. Also, provide. a transient curve of the re-actor coolant system pressure for the limiting event to demonstrate 4
'that,the pea,k. pressure, does not.,ex,ceed,ll.0% of. the system design.,,f,,,
.. pressure,; 1
.,.; ;,. g..,
y
.s
...,. )..
.,.g 2.
A. qualitative analysis comparing the RCP rotor seizure accident with the RCP shaft break is requested to identify the limiting case-with respect to maximum RCS pressure and limiting fuel performance.
The analysis should assume a loss'of offsite power as a result of turbine trip, the Technical Specification limit of. steam generator tube leak-age and a single active failure in safety systems.
Appropriate delay.
time for loss of offsite power may be assumed if suitably justified.
The evaluation should include tabulations of the sequence of events,-
disposition of normally operating systems, utilization ~ of safety systems and transient curves including RCS pressure and DNBR and.re-actcr coolant flow for the limiting accident.
Confirm that the results of the analysis meet the acceptance criteria for these events per SRP 15.3.3.
Assume any fuel rod which has a DNBR less.than the minimum allowable value for Yankee Rowe fails.
State the amount of failed fuel in the results of the analysis.
Radiological consequences.should be calculated accordingly.
.m hem
,