ML20217Q953
| ML20217Q953 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/28/1997 |
| From: | Lynch M NRC (Affiliation Not Assigned) |
| To: | Capra R NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9709040017 | |
| Download: ML20217Q953 (3) | |
Text
-
r August 28, 1997 4
MEMORANDUM T0:
Robert A. Capra. Director Project Directorate III-2 Division of Reactor Projects III/IV. NRR FROM:
M. David Lynch Senior Project Manager OdginalSigf*lBT' Project Directorate III-2 Division of Reactor Projects III/IV. NRR
SUBJECT:
FORTHCOMING MEETING WITH COMMONWEALTH EDISON COMPANY (COME0)
DATE & TIME:
Wednesday. September 4. 1997 1:00 pm to 4:00 pm LOCATION:
One White Flint North 11555 Rockville Pike Room 0-03 B4 Rockville MD PURPOSE:
To discuss Comed's methodology, including assumptions, for calculating radiation ex)osure doses resulting from predicted steam generator tube leacage in the event of a main steamline break. This discussion is in support of a pending license amendment to revise the Byron. Unit 1. Technical Specifications to reduce the maximum permissible dose equivalent iodine-131 concentration in the primary coolant.
PARTICIPANTS *: EC UTILITY J.. Roe D. Saccomando C. Miller J. Blomgren R. Emch J. Hosmer, et, al R. Capra C. Hinson L. Brown G. Dick S. Bailey M. D. Lynch Docket No STN 50-454 cc: See next page CONTACT:
M. David Lynch Yb /
(301) 415-3023
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers )ursuant to " Commission Policy Statement on Staff Meetings Open to the Pu)1ic" 59 Federal Reaister 48340, 9/20/94 DOCUMENT NAME: G:\\CHNTJR\\ BYRON \\BYO903.MTG OFC'
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- August 28, 1997 HEMDRANDUM T0: Robert A. Capra Director Project Directorate 111 2 DivisionofReactorProjects111/IV.NRR Q]
FROM:
H.DavidLynch,SeniorProjectManage ProjectDirectorate1112 Division of Reactor Projects III/IV. NRR
SUBJECT:
FORTHCOMING HEETING WITH COMMONWEALTH ErilSON COMPANY (COMED)
DATE & TlHE:
Wednesday. September 4, 1997 1:00 pm to 4:00 pm LOCATION:
One White Flint North 11555 Rockville Pike Room 0 03 B4 Rockville. HD PURPOSE:
To discuss Comed's methodology, doses resuPing from predict including assumptions, for calculating radiation ex)osure steam generator tube leacage in the event of 4 main steamline bceak. This discussion is in support of a pending license amendment to revise the Byron, Unit 1. Technical Specifications to reduce the maximum permissible dose equivalent iodine 131 concentration in the primary coolant, PARTICIPANTS *:
(RC JTILITY Roe J. Saccomando s.C. Hiller J. Blomgren R. Emch J. Hosmer, et. al R. Capra C. Hinson L. Brown G, Dick S. Bailey H. D. Lynch Docket No. STN 50-454 cc:
See next page CONTACT:
H. David Lynch (301) 415-3023
- Meetings between NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers oursuant to " Commission Policy Statement on Staff Heetings Open to the Pu)1ic" 59 Federal Reaister 48340, 9/20/94.
i
.f NOTICE OF AbGUST 26. 1997 MEETING WITH COMED E. Mail
.e S. Collins 1(SJC1)/F. Miraglia (FJM)
R. Zimerman (RPZ)
J. Roe (JWR)
E. Adensam (EGA1)
R. Capra (RAC1) i t
M. D. Lynch (MDL)
C. Moore (ACM)
D. Ross-(SLM3)
t C. Miller-(CLM1)
R. Emch (RLE)
C. Hinson (CSH)-
L. Brown (LAB 2)-
G. Dick (GFD)
S. Bailey (SNB)
J. Caldwell (JRC1)
G. Tracy (GMT)-
J. Strasma-(RJS2)
PMNS (Meeting announcement Coordinator)
Hard Conv
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Docket (STN 50 454)
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