ML20117G144

Forwards Response to 850512 Request for Addl Info Re Items 2.1,2.2.2 & 4.5.2 of Generic Ltr 83-28, Required Actions Based on Implications of Salem ATWS Events. Item 4.5.3 Will Be Responded to at Later Date

ML20117G144
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	05/07/1985
From:	George Alexander COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20117G150	List: ML20117G144 ML20117G187 ML20117G195 ML20117G206 ML20117G218
References
0089K, 89K, GL-83-28, NUDOCS 8505130431
Download: ML20117G144 (3)

Text

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. .o Commonwealth Edison O One First National Pitze. Chicago. Ilhnois Address Reply to. Post Othee Box 767 Chicago, Illinois 60690 May 7, 1985 f Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Braidwood and Byron Stations Supplement Response to Generic Letter No. 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events" NRC Docket Nos. 50-454/455 and 456/457 References (a): Generic Letter No. 83-28 D. G. Eisenhut i 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

Dear Denton:

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. Attached are the responses for Byron and Braidwood Stations for items 2.1, 2.2.2, and 4.5.2. Item 4.5.3 will be responded to at a later date.

Please address any questions that you or your staff may have concerning our response to Generic Letter No. 83-28 to this  ;

office.

Respectfully, 8505130431 850507 l

DR ADOCK 05000t>54 p

PDR G.L. Alexander Nuclear Licensing Administrator Attachment cc: US NRC, Document Control Desk Washington, DC 20555 f

L.N. Olshan - LB1 J. Stevens - NRR I{ d \

1 J. G. Keppler - RIII RIII Inspectors - BY/BW 0089K

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PART I BRYON STATION Item 2.1 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

Byron Station has implemented Nuclear Stations Division Directive MO-2, Control of Vendor Equipment Technical Information. The directive is reflected in Station Administrative Procedures BAP 1340-14 and BAP 1340-T17. The referenced procedures describe the methodology for vendor manual receipt, control, and use which includes processing manual revisions and documenting the engineering review of technical manuals.

Vendor revision and new materials are initially reviewed by the Technical Staff Engineer responsible for the system affected.

Following this review, maintenance and operating personnel review the information for impact on approved station procedures. Finally, all controlled copies of the af fected manual are updated to reflect the-revision. Controlled copies of vendor manuals may be compared to the master copy of'the manual to verify accuracy and completeness. The master copy of the manual is filed in plant records vault-and is not available for general checkout.

In the case of the reactor trip system components, Westinghouse

' requires ~ signed receipt acknowledgements for documentation sent to Commonwealth Edison. Assuming a change to the technical information is required as a result of the modification, concurrence from Westinghouse shall be requested.

Copies of the station procedure and the Nuclear Stations Directive are attached to the end of this section.

0089K-

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, Item 2.2.2 Applicant needs to present its evaluation of the NUTAC program and describe how it will be implemented at Byron /Braidwood. The staff found the NUTAC program fails to address the concern about establishing and maintaining an interface between all vendors of safety-related equipment and the utility. Accordingly the applicant will need to supplement its response to address this concern. This additional information should describe how current procedures will be modified and new ones initiated to meet each element of the item 2.2.2 concern.

I Response CECO's representative in the NUTAC program was from Nuclear Stations j Division, a Corporate level organization. To implement the Vendor

' Equipment Technical Information Program at each nuclear station, NSD issued a directive, NSDD-M02, based on the NUTAC program and INPO Good Practice MA 304. The directive defines the minimum requirements for implementation of the program and serves as our corporate statement on the control of vendor information. A copy is attached at the end of Part I for your review.

Item 4.5.2 Applicant needs to describe design modifications that will permit on-line test of the RTS and provide an implementation schedule.

Response

The station was designed with on-line testing capabilities. Byron Station currently conducts on-line testing of the Reactor Trip Breakers on a bimonthly, staggered basis in Operating Surveillances 180S 3.1.1-10 and 1 BOS 3.1.1-11. The testing verifies proper operation of the shunt and undervoltage trip actuations on both trains of the reactor trip system. Copies of the procedures are attached to the end of this section.

The shunt trip modification will be installed per a Westinghouse Field Change Notice (CAEM 10807). Upon completion of the modification installation (1st refueling), surveillance procedures will be updated to include testing from the auto shunt trip panel.