ML20211H948
| ML20211H948 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/06/1987 |
| From: | Hunsader H COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-1.C.1, TASK-1.D.1, TASK-1.D.2, TASK-2.D.1, TASK-2.K.3.05, TASK-TM 2690K, NUDOCS 8702260337 | |
| Download: ML20211H948 (2) | |
Text
-
e f%
/
Cofninonwealth Edloon
- Z One First Nabonal Plaza, Chicago, Illinois Address Reply to
- Post Omce Fsox 767 Chicago, Illinois 60690 0767 February 6, 1987 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Braidwood Station Units 1 and 2 Generic Issues (Sa:em ATWS and TMI-2)
NRC Docket Nos. 50 -456 and 50-457
Dear Mr. Denton:
It has been requested that Commonwealth Edison provide the status of implementation of certain generic issues for Braidwood. Per this request, enclosed is a listing of the generic issues indicating the completion date or projected completion date for implementation of our actions to resolve the issues.
Please direct any questions regarding this matter to this office.
Very truly yours, "k
. C. Hunsader Nuclear Licensing Administrator klj Enclosure cc:
J. A. Stevens - NRR Braidwood Resident Inspector 8702260337 870206 PDR ADOCK 05000456 PDR 2690K p
t
Regulatory Inftnnation Tr cking System Facility Implementation FACILITY: Braidwood I and 2 PLANT LOCATION: Braidwood, IL.
LICENSED POWER: 3411 mlT PROJECT MANAGER:
J. Stevens DOCKET NUMBER: 50-456/50-457 DESIGN POWER: 1120 mfE BRANCH CHIEF:
S. Varga ARCH./ ENGR: S&L NSSS VENDOR: Westinghouse LIC. ASSISTANT:
LICENSEE TAC NO.
MPA #
TITLE STATUS DATE (Units 1 & 2)
M57198 A-17 Instrumentation to follow the course of an accident Projected 1988 M59077 A-20 10 CFR 50.62 operating reactor reviews Projected 1988 M59942 A-21 10 CFR 50.61, pressurized thermal shock rule Completed 01/17/86 M56274 B-76 Item 1.1 - post trip review; program description Completed 09/12/85 M56276 B-77 Item 2.1 - equipnent classification Completed 06/25/86 (Part 1)
M56278 B-78 Items 3.1.1 & 3.1.2 - post maintenance test procedure Completed 09/17/85 (except for VETIP)
M56279 B-79 Item 3.1.3 - post maintenance testing Projected 8/87 M56282 B-80 Item 4.1 - reactor trip system reliability Conpleted 09/17/85 M56283 B-81 Items 4.2.1 & 4.2.2 - preventative maint prog.
Conpleted 04/21/86 M56285 B-82 Item 4.3 - automatic actuation of shunt trip Projected 1987 M56275 B-85 Salem ATWS 1.2 data capability Completed 05/05/86 M56277 B-86 Salem ATWS 2.2 S-R components (Awaiting NRC review)
M56280 B-87 Salem ATWS 3.2.1 & 3.2.2 5-R components Completed 06/25/86 (except for VETIP)
M56281 B-88 Salem ATWS 3.2.3 T.S. S-R components Completed 11/05/85 M56284 B-89 Salem ATWS 4.2.3 & 4.2.4 life components (Awaiting NRC review)
M56286 B-90 Salem ATWS 4.3 W and B&W T.S.
Projected 1987 M56287 B-92 Salem ATWS 4.5.1 diverse trip features completed 10/01/85 M56288 B-93 Salem ATWS 4.5.2 & 4.5.3 test alternatives (Awaiting NRC review)
M58046 C-16 Utility responses to staff reconnendations concern Congleted 2/85 (w/ Byron)
M57199 F-05 I.C.1.2/3.B procedures generation packages Completed 01/31/87 57197 F-09 I.D.2 safety parameter display system Projected 1st refuel outage F-14 II.D.1 relief and safety valve test requirements Completed 10/26/82 571 %
F-71 I.D.1.2 detailed control room review Projected 1987 50889 G-01 II.K.3.5 reactor coolant pump trip Projected 1987 2690K J