ML19269B784
| ML19269B784 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 11/30/1978 |
| From: | Reed C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19269B785 | List: |
| References | |
| NUDOCS 7812040201 | |
| Download: ML19269B784 (2) | |
Text
.. _ _ _ _.
@ One First National Plaza, Chicago, Illinois Commonwealth Edison Address Reply to: Post Office Box 767 Chicago, Illinois 60690 t
November 30, 1978 Mr. Harold R. Denton, Director- [
Nuclear Reactor Regulation U.S. Nuclear Regulatory Consnission '
washington, DC 20555
Subject:
Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2 Amendment No. 17, Final Safety Analysis Report, to tho Application for Construction Permits and j
Operating Licenses FRC Docket Nos. 50-454, 50-455, 50-456
~
and 50-457 Reference (a):
October 20, 1978 letter from Rogsr S.
Boyd to Cordell Reed titled "Results of Byron and 2raidwood Acceptance l
Review."
Dear Mr. Denton:
The applicati.on for construction permits and operating j
licenses for Byron Station Units 1 and 2 and Braidwood Station Units 1 and 2, docketed September 20, 1973 in NRC Docket Nos.
50-454, 50-455, 50-456 and 50-457, are hereby amended by sub-mittal of Amendment No. 17 pursuant to Section 50.34 of 10 CFR 50.
Said amendment consists of the Byron and Braidwood Stations Final Safety Analysis Report including the proposed technical specifications.
The Final Safety Analysis Report (FSAR) analyzes the design of each unit for operation at the ultimate power level j
currently contemplated, 3425 s t, or the equivalent not electrical output of 1120 MWe.
Accordingly, it is requested that the design of Byron i
Units 1 and 2 and Braidwood Unita 1 and 2 be reviewed for operation at power levels up to 3425 at and that the facility licenses bo issued authorizing operation of each unit at this power level subject to the conduct of auch tests and demonstr&tions and the
.subsmission of such future reports as the NRC may deem appropriate.
L6
?81204oco(
k f
i ERC Docket nos. 50-454 50-455 50-456 50-457 Mr. Barcid'R. Denton: Novcaber 30, 1978 Every effort han boon made to format the PSAR in accordanco with Regulatory Guide 1.70, Rovision 2, in ordor to facilitate your review.
However, at thin timo, tho FSAR doon not contain the additional informt. tion roquanted in Enclosuro 2 of Reference- (a).
This information will be provided in a subsequent. amendment by January 31, 1979.
Also, includod under separate cover are the overnize drawings indicated in Section 1.7 of the FSAR.
The Operating License Stage Byron and Braidwood Environmental Report required by 10 CFR 51 in being suhaitted under separato cover.
In accordance whh the NRC letter of October 20, 1973, Reference (a), and 10 CFR 50.30, Conanonwealth Edison han included.
three (3) signed originals transmitting fifteen (15) copies of tLhe general inform
- 4cm of 10 cPn 50.33 and 50.37 cua IwLy (40)-
copi.. uI the rirel Safety Arel,ysia nog % In addition, ten (10) copies of the general information and thirty (30) copies ~of the Final Safety Analysis Report will be retained and distributed in accordance with the instructiona contained in Roferenco (a).
An affidavit confirming distribution in accordance with Enclosure 1 of Reference (a) will be provided within ten (10) days after receipt of an acknowledgement that the enclosed f
information has been docketed.
-)&kFS At Gooreouen + very truir vere, sS Yl2I8 0 W h Q,
(
5ePRR &re LY Cordoll Reed Annistant Vico-Pronident attachments SUBSCRIBED and SITER to before no thfajl/ % day s
of llA h l % flf n _), 1978.
N l I. ll -
(? Of 04140 No$ary Pub'lic
()
.