ML20199K380

From kanterella
Revision as of 04:30, 19 November 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Safety Evaluation of Applicant 831105 & 840601 Responses to Generic Ltr 83-28,Item 2.1 (Part 1),requiring Confirmation of Identification of All Components Needed to Institute Reactor Trip as safety-related.Program Approved
ML20199K380
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 06/25/1986
From: Noonan V
Office of Nuclear Reactor Regulation
To: Farrar D
COMMONWEALTH EDISON CO.
Shared Package
ML20199K385 List:
References
GL-83-28, NUDOCS 8607090143
Download: ML20199K380 (3)


Text

-

Docket Nos.: STN 50-456 and STN 50-457 Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690

Dear Mr. Farrar:

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2 - SAFETY EVALUATION REPORT FOR GENERIC LETTER 83-28, ITEM 2.1 (PART 1)

The applicant was required by Generic Letter 83-28, Item 2.1 (Part 1) to confirm that all components whose functioning is required to trip the reactor are identified as safety-related on all plant documentation and in information handling systems that are used to control ~all activities performed on this safety-related equipment.

By letters dated November 5, 1983, and June 1, 1984, the applicant responded to Item 2.1 (Part 1) (Equipment Classification - RTS Components). The responses were found to be acceptable, as documented in the enclosed Safety Evaluation prepared with the assistance of EG&G Idaho, Inc. The applicant's responses confirm that a proaram exists for identifying, classifying and treating components as safety-related which are reouired for performance of the reactor trip function. This program meets the requirements of Item 2.1 (Part 1) of Generic Letter 83-28, and is therefore acceptable.

Generic Letter 83-28, Item 2.1 remains open since the vendor interface portion (Part 2) has not been resolved.

. Sincerel y, R

Vincent S. Noonan, Director PWR Pro,iect Directorate #5 Division of PWR Licensing-A

~

Enclosure:

Safety Evaluation cc: See next page Distribution:

SDocket Files- T. Novak E. Jordan D. Lasher, EICSB, DPA NRC PDR OELD M. Rushbrook Local PDR B. Grimes J. Stevens PD#5 R/F ACRS (10)

J.P9etlow PD#5 f DIR:PD#5 JSteve s VSN nay ,

6/gf/8 6 /86(/ i e607090143 860625 PDR ADOCK 050004 6

UNITED STATES p t, NUCLEAR REGULATORY COMMISSION

= j WASHINGTON, D. C. 20555

, ,E

+ R e., - /

..... 8, a ses Docket Nos.: STN 50-456 and STN 50-457

=%

Mr. Dennis L. Farrar Director of Nuclear Licensing ,

Commonwealth Edison Company 1

Post Office Box 767 g Chicago, Illinois 60690 a

ll

Dear Mr. Farrar:

SUBJECT:

BRAIDWOOD STATION, UNITS 1 AND 2 - SAFETY EVALUATION REPORT FOR GENERIC LETTER 83-28 ITEM 2.1 (PART 1)

The applicant was required by Generic Letter 83-28. Item 2.1 (Part 1) to confirm that all components whose functioning is required to trip the reactor are identified as safety-related on all plant documentation and in information i handling systems that are used to control all activities performed on this safety-related equipment.

By letters dated November 5,1983, and June 1,1984, the applicant responded to Item 2.1 (Part 1) (Equipment Classification - RTS Components). The i

responses were found to be acceptable, as documented in the enclosed Safety Evaluation prepared with the assistance of EG8G Idaho, Inc. The applicant's responses confinn that a program exists for identifying, classifying and treating components as safety-related which are required for perfonnance of the reactor trip function. This program meets the requirements of Item 2.1 (Part 1) of Generic Letter 83-28, and is therefore acceptable.

Generic Letter 83-28. Item 2.1 remains open since the vendor interface portion (Part 2) has not been resolved.

Sincerely, f f -

l

4. Director W

j#l 5rojec Direc rate #5 i Division o PWR Licensing-A I

Enclosure:

Safety Evaluation i cc: See next page -

.~+--.-.-,3 ,--s,-.,-_,,.,w_,,- .,---e-,-. , , - _ - - - - _---_,r,

~

Mr. Dennis L. Farrar Braidwood Station Commonwealth Edison Company Units 1 and 2 cc:

Mr. William Kortier Ms. Lorraine Creek Atomic Power Distribution Route 1, Box 182 Westinghouse Electric Corporation Manteno. Illinois 60950 Post Office Box 355 * * -

Pittsburgh, Pennsylvania 15230 Douglass Cassel, Esq.

109 N. Dearborn Street Joseph Gallo, Esq. Chicago, Illinois 60602

. Isham, Lincoln & Beale 1150 Connecticut Ave., N. W. Elena 7. Kezelis, Esq.

Suite 1100 Isham, Lincoln & Beale Washington, D. C. 20036 . -

Three First National Plaza Suite 5200 C. Allen Bock, Esq. Chicago, Illinois 60602

Post Offices Box 342 l Urbana, Illinois 61801 Mr. Charles D. Jones, Director i Illinois Emergency Services Thomas J. Gordon, Esq. and Disaster Agency Waaler, Evans & Gordon 110 East Adams Street

! 2503 S. Neil Springfield, Illinois 62706 Champaign, Illinois 61820 George L. Edgar Ms. Bridget little Rorem Newman & Poltzinger, P.C.

i Appleseed Coordinator 1615 l Street, N.W.

i 117 North linden Street -

Washington, D.C. 20036 Essex, Illinois 60935 Michael Miller, Esq.

Mr. Edward R. Crass Isham, Lincoln & Beale

! Nuclear Safeguards and One First National Plaza licensing Division 42nd Floor Sargent & Lundy Engineers Chicago, Illinois 60603 i 55 East Monroe Street j Chicago, Illinois 60603 l

, U. S. Nuclear Regulatory Commission '

Resident Inspectors Office RRil, Box 79 Braceville, Illinois 60407 Regional Administrator, Region III U. S. Nuclear Regulatory Commission

! 799 Roosevelt Road Glen Ellyn, Illinois 60137 4

l l

, ,,--.,---..-,..,-,.---,,..--n,_. __ ---n,., n -

. . . - - . - - - , , , , , , , - , - - - . - . -