ML20038B923
| ML20038B923 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/02/1981 |
| From: | Morisi A BOSTON EDISON CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| 81-277, NUDOCS 8112090297 | |
| Download: ML20038B923 (2) | |
Text
o.
-- C BOSTON EDISON COMPANY DENERAL DrrscEs 500 novLaTON STREET soaTON. MAssAcMumETTs 02199 A. V. M O RISI 10
/ (Q d
/
MANAGER NUCLEAR O PERATf DNS SUPPORT DEPARTMENT C
f NLA I jl C,CI
' December 2, 1981
-t DEC3
.1981 %
8 rou {Q BECo. Ltr. #81-277 u.h
\\
s Mr. Thomas A. Ippolito, Chief
- 7 \\M' 4r Operating Reactors Branch #2 Division of Licensing Office of Nuclear' Reactor Regulation U.S. Nuclear Regulatory Connission Washington, D. C.
20555 License No. DPR-35 Docket No. 50-293 Additional Information on Reload Application
Dear Sir:
In response to a recent phone call with members of your staff involved in the review of our Reload 5 submittal, we hereby verify that the below listed changes to TABLE 2 of NED0-21696 are applicable:
0 PCT = 2136 F Peak Local 0xidation = 2.3%
Core Wide M-W Reaction = 0.14%
The page reflecting these changes will be sent to you in the near future as well as an additional page to include values covering no-core-spray-heat-trar,sfer as follows:
U PCT = 2200 F Peak Local 0xidation = 2.5%
Core Wide M-W Reaction = 0.17%
In addition, answers to your specific questions are provided as follows:
NRC Question 1.
What is the peak local oxidation (%) for the Design Basis Accident (DBA) using the "no core spray" MAPLHGR multipliers?
0112090297 811202 s
PDR ADOCK 05000293 di P
PDR Sll6
BO"; TON. E35 EON COMPANY
'Mr. Thomas' A. Ippolito, Chief
~
December 2, 1981 Page 2
. Response
- 11. The peak local oxidation is 2.5%.
NRC Question 2.
What is the 'overall hydrogen release for the DBA using ':,o core spray" MAPLHGR multipliers?
Response
'2.
The core-wide metal-water reaction is 0.17%. This is well below the minimum of 1% which is required to be used in the hydrogen release calculation.
Therefore, the overall hydrogen release calculation is. unaffected.
NRC Question 3.
Are Tables 4A-4F in NED0-21296 the results of the standard analysis or the analysis using "no core spray" tiAPLHGR multipliers?
Response
3.
Tables 4A-4F are the results of the standard analysis.
NRC Question 4.
Does the General Electric evaluation of the NRC increased fission gas correction factor as reported in' letters from R.E. Engel (GE) to T. A. Ippolito.(NRC) dated May 6 and May 28, 1981 coply to the Pilgrim ECCS analysis?
Responsa 4.
The evaluation reported in the referenced letters which concludes that adequate margin exists and no fission gas correction factor is required does apply to both the Pilgrim standard ECCS analysis and the "no core spray" analysis.
Therefore, the MAPLHGRs reported in Tables 4A-4F of NED0-21296 need not be reduced for increased fission gas.
Should you have any additional ques tions or concerns on this subject, please do not hesitate to contact ue.
Very truly yours,
0
}{
. k o waa
.-