ML20235N741

Forwards Updated Response for Items 2.1 & 4.5.2 of Generic Ltr 83-28, Required Actions Based on Generic Implementation of Salem ATWS Events

ML20235N741
Person / Time
Site:	Braidwood
Issue date:	09/23/1987
From:	Hunsader S COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
3612K, GL-83-28, NUDOCS 8710070051
Download: ML20235N741 (3)

Text

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C:mm:nw2alth Edison 3

V One First National Plaza. Chicago, Illirnis Address Reply to: Post Office Box 767 4

Chicago, Illinois 60690 0767 September 23, 1987 Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTN: Document Control Desk

Subject:

Braidwood Station Units 1 and 2 Supplement Response to Generic Letter No. 83-28, " Required Actions Based on Generic Implications of Salem ATWS Rvents" NRC Docket Nos. 50-456 and 50-457 References (a) Generic Letter No. 83-28 D.G. Eisenhut letter to all OLS and CPS dated July 8, 1983 (NL-83-0003)

(b): B.J. Youngblood to D.L. Farrar letter dated March 12, 1985 (c): May 7, 1985 G.L. Alexander letter <

to H.R. Denton

Dear Mr. Murley:

Reference (b) contained a request for additional information pertaining to Items 2.1, 2.2.2, 4.5.2 and 4.5.3 of Generic Letter 83-28 (Reference (a)). Reference (c) provided the responses for Byron and Braidwood Stations for Items 2.1, 2.2.2, and 4.5.2. This letter provides an updated response (See Attachment A) for Items 2.1 and 4.5.2 in response to a I-request by members of your staff. All actions required for Items 2.1 (second part) and 4.5.2 have been completed. No further action is required.

Please address any questions that you may have concerning this matter to this office.

Very truly yours, e710070051 870923 PDR ADOCK 05000456 PDR

• fd" C- j+- I j

P S. C. Hunsader Nuclear Licensing Administr; tor -l l

Attachment l l

Cs cc: S. Sands NRC - RIII O Braidwood Resident Inspector i 3612K

.A, ATTACHMENT A Item'2.1 (second part)

Applicant needs to submit detailed-information describing its vendor interface program for reactor trip system components. Information supplied should state how'the program assures that vendor technical

- information is kept complete, current, and controlled throughout the life of the plant and-should also indicate how the program will be implemented at Byron /Braidwood..

Response (May 7, 1985)

Braidwood's Vendor Equipment Technical Information program (VETIP) is currently under development. An administrative procedure, BwAp 1340-5 has been written, and is currently undergoing the station's review process.

This procedure has been written'to. implement the Nuclear Stations Division-

' Directive M02, control of Vendor Equipment Technical Information. This procedure applies'to both safety related and non-safety related equipment.

BwAP 1340-5 prescribes that all vendor manuals, safety-related and non-safety related, be controlled by the Central Files Supervisor. All satellite files are-likewise controlled. It defines the review criteria, including effects on station procedures, for vendor initiated revisions to  ;

equipment manuals. Also addressed in this' procedure is the vendor manual 1 update process, which is initiated when a plant modification is undertaken.

i Updated Response _

Braidwood Station administrative procedure BwAp 1340-5 " Vendor 1 Manual control" has been approved for site use and is currently in Revision j

2. i l

Item 4.5.2 )

l Applicant needs to describe design modifications that will permit l on-line test of the RTS and provide an implementation schedule.

Response (May 7, 1985) {

l The Braidwood Reactor Trip System employs two diverse trip features j

- an undervoltage trip and a shunt trip. Any time a reactor trip signal is j generated, power is removed from the undervoltage trip attachment which in j turn will trip the reactor trip breaker. In addition, the shunt trip relay  !

will be energized to supply the breaker with a redundant trip. l The system is designed such that on-line testing is accomplished through the use of a bypass breaker in parallel with the main trip breaker. l When testing is performed, the bypass breaker is placed in the connect i position and the main breaker is placed in the disconnect position. With I l

the. main trip bre3ker out-of-service, both utadervoltage and shunt-trip devices can be tested. During this testing, the bypass breaker can be tripped by similar undervoltage and shunt-tiip devices, 3612K l

j

L f-p; x. ..

As these modifications have been incorporated into the .-

I system / equipment construction phase-of the Braidwood Startup program, the implementation schedule corresponds to the respective. unit's fuel loa'd date.

As.can be:seen by the above description,. modifications have been msde to enable Braidwood to accomplish on-line testing of reactor trip

'. breakers. The only design modification is the addition of the' shunt trip i

! coil, but it should be noted that replacement undervoltage trip attachments l 1 are being supplied by Westinghouse for installation at Braidwood.

. Updated Response' The shunt trip devices'for the Unit 1 and 2 Reactor Trip System have been installed and are tested per operating surveillance BwoS 3.1.1-10 and 3.1.1-11 "Birponthly, Staggered Basis, Reactor Trip Breaker Shunt and Undervoltage Trip Independence Test - Train A" and " Train B".

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