ML20198R712
| ML20198R712 | |
| Person / Time | |
|---|---|
| Site: | Byron |
| Issue date: | 06/04/1986 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 1745K, NUDOCS 8606100179 | |
| Download: ML20198R712 (3) | |
Text
-...
N Commonwrith Edison O ) One First National Plaza. Chicago, Ilknois C'
Address Reply to-Post Office Box 767 Chicago. Illinois 60690 June 4, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Station Unit 1 Generic Issues NRC Docket No. 50-454 Reference (a): April 29, 1986 letter from L. N. Olshan to D. L. Farrar I
Dear Mr. Denton:
Reference (a) requested Commonwealth Edison to provide the status of implementation of certain generic issues for Byron Unit 1.
Per this request, enclosed is a marked-up listing of the generic issues indicating the completion date or projected completion date for implementation of our actions to resolve the issues.
i Please direct any questions regarding this matter to this office.
Very truly yours, K. A. Ainger Nuclear Licensing Administrator la i
Enclosure 4
1 i
1745K B606100179 860604 E,
PDR ADOCK 05000454 P
PDR g
i
~-,
- =1208731 -001 REGULAT0RY INF0RMATION TRACKING SYSTEM PA;E NO.
6 FACILITY IMPLEMENTATION 03/31/86
'OCILITY: BYRON 1
'LANT LOCATION: 17 MI SH OF ROCKFORD, ILL LICENSED POWER: 3411 MHT PROJECT MANAGER: L. OLSHAN 10CKET NUMBER:
050-00454 DESIGN P0HER:
1120 MHE BRANCH CHIEF:
V.
NOONAN
,RCH/ ENGINEER:
S&L NSSS VENDOR:
HEST LIC. ASSISTANT:
M. RUSHBROOK E INSPECTOR:
LIC ACT LICENSEE AC NO.
MPA 4 TITLE COMPLETE STATUS AAlg A
157198 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 06/01/87 Pro 3eefed MII 159077 A-20 to CFR 50.62 OPERATING REACTOR REVIEHS N//S /
'*3bd I
9942 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE Co"PUC
'b Oca f 8 E8-
'*!84 i55274 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION &
07/11/85C (om p ife.
81[d l
6276 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION & VENDOR INTER 01/02/86
'6278 B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/26/85C Complef t-80/fi 55279 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 11/05/85C Comp kfe, to[N 6282 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/26/85C Comp ltft-11[f3' Comp ele.
Shf l
$6283 P-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 08/30/85 6285 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 03/13/85C Co*Pltf8-U/II
>6275 B-85 SALEM ATHS 1.2 DATA CAPABILITY 04/01/86 Projeded 3%7 -
56277 B-86 SALEM ATHS 2.2 S-R COMPONENTS 01/02/86 Co **Pkle.
D[99 OoMfkYL
'!I 6280 B-87 SALEM ATHS 3.2.1 & 3.2.2 S-R COMPONENTS 09/26/85C 56281 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 11/05/85C Co"P * '
I 6284 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 12/31/86 CMP l ele, 4/rb 56286 B-90 SALEM ATHS 4.3 H AND B8H T.S.
01/02/86 Projecled 7[Ila O*f eft-Dhi~
l 6287 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/26/85C Co*fkft if'ff 56288 B-95 SALEM ATHS 4.5.2 & 4.5.3 TEST ALTERNATIVES 58046 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN ComplCfd 2Nf CompleIC.
<!ds' 57199 F-05 I.C.1.2/3.B PROCEDURES GENERATION PACKAGES (NUREG 03/27/86
s t-1208731-001 REOULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.
- 671 6
FACILITY IMPLEMENTATION 03/31/86:
lYRON 1 (CONTINUATION)
LIC ACT LICENSEE
'AC NO.
MPA 9 TITLE COMPLETE STATUS R&lg 157197 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM CoMglede-3/IS~
157194 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLONUP TO 03/01/87 fujeelt/
I'N1 E"i"**
IT 160889 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5)