ML20137S724

Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability

ML20137S724
Person / Time
Site:	Byron
Issue date:	09/26/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20137S708	List: ML20137S703 ML20137S724
References
GL-83-28, NUDOCS 8509300486
Download: ML20137S724 (3)

Text

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ENCLOSURE 1

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIO 2

RELATED TO LICENSEE RESPONSE TO GENERIC LETTER 83-28

, COMMONWEALTH EDISON COMPANY BYRON NUCLEAR GENERATING STATION

-DOCKET NOS. 50-454: 50-455 1.0. Introduction A. Background Information '

Subsequent to the anticipated transient without scram (ATWS) events at the Salem Nuclear Power Plant, the Commission reviewed intermediate term actions to be taken by the licensees. The actions taken were developed on the basis of information contained in NUREG-1000, " Generic Implications of ATWS Events at the Salem .

Nuclear Power Plant." On July 8, 1983, Generic Letter (GL) 83-28 was issued by NRR.

The letter identified NRC positions developed  ;

from review of the Salem ATWS events. These positions are related to reactor trip system reliability and general management capability.

The specific GL 83-28 items covered by this Safety Evaluation are 4

Sections ~3.1.1 and 3.1.2, " Post-Maintenance Testing (RTS Components)";

3.2.1 and 3.2.2, " Post-Maintenance Testing (All Other Safety-Related Components)"; 4.1, "RTS Reliability (Vendor Related Modifications)"

l and 4.5.1, "RTS Reliability (System Functional Test Description)." ;

i

8. Licensee's Response to Generic Letter (GL) 83-28

& By letters dated February 29,1984 Commonwealth Edison Companyded respon June 1, to specific items 1984,of and GL 83-28. August 6, 1985,

' ' The licensee summarized the results of the requested review and

concluded that all items have been appropriately addressed.

C. Scope of Review The staff's review consisted of an evaluation of the response to determine if the requirements of GL 83-28 have been satisfied. The evaluation for each of the items is given below.

j 2.0 Evaluation l A.

Items 3.1.1 and 3.1.2, " Post-Maintenance Testing (RTS Components)"

The review criteria for these items require that the licensee submit a statement indicating that he has reviewed plant test and maintenance procedures and Technical Specifications to ensure that post-maintenance operability testing of safety related components 8509300486 850926 PDR ADOCK 05000454 p PM

in the reactor trip system is required. Also, the licensee's-statement should contain a verification that vendor recommended test guidance has been reviewed, evaluated, and where appropriate, included in the test and maintenance procedures or the Technical Specifications.

The staff has evaluated the licensee's February 2, 1984 submittal.

in content. for this item and has determined it to be adequate B.

Items 3.2.1 and 3.2.2, " Post-Maintenance Testing (All Other Safety-Related Components)"

The review criteria for these items require that the licensee submit a statement indicating that he has reviewed plant test and maintenance procedures and Technical Specifications to ensure that ~ post maintenance operability testing of all safety-related components is required. Also, a statement is required that contains a verification that vendor recommended test guidance be reviewed, evaluated and where appropriate, included in the test and maintenance procedures or the Technical Specifications.

The staff has evaluated the licensee's February 2, 1984 submittal.'

for this item and has determined it to be adequate in content.

C.

Item 4.1, "RTS Reliability (Vendor Related Modifications)"

The review criteria for this item requires that the licensee submit a statement indicating'that he has reviewed all vendor recommended reactor trip breaker modifications and determined that (1) each modification has been implemented or (2) a written evaluation which specifies the technical reasons for not implementing the modification exists. The staff has evaluated the licensee's August 6,1985 submittal for this item and has determined it to be ade,quate in content.

,1).

Item 4.5.1, "RTS Reliability (System Functional Test Description)"

The review criteria for this item requires that the licensee submit

. a ofstatement committing the diverse to independent, on-line functional testing trip features.

The staff has evaluated the licensee's June 1,1984 submittal for this item, committing to on-line testing of the undervoltage and shunt trip devices, and has determined it to be adequate in content.

3.0 Conclusion The staff concludes that the programs outlined in the licensee's submittals l adequately address the requirements of Generic Letter 83-28 for the areas specified in this Safety Evaluation. -

Dated:

The following NRC' personnel have contributed to this Safety Evaluation: '

1 T. E. Taylor 2

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

Mr. William Kortier Atomic Power Distribution Ms. Diane Chavez 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III Michael Miller U. S. Nuclear Regulatory Corrinission Isham, Lincoln & Beale 799 Roosevelt Road One First National Plaza Glen Ellyn, Illinois 60137 42nd Floor Chicago, Illinois 60603 Joseph Gallo, Esq.

Isham, Lincoln & Beale Mrs. Phillip B. Johnson Suite 840 1907 Stratford Lane 1120 Connecticut Avenue, N.W.

Rockford, Illinois 61107 Washington, D. C. 20036 Dr. Bruce von Zellen Douglass Cassel, Esq.

Department of Biological Sciences 109 N. Dearborn Street Northern Illinois University Suite 1300 DeKalb, Illinois 61107 Chicago, Illinois 60602 Mr. Edward R. Crass Ms. Pat Morrison Nuclear Safeguards & Licensing 5568 Thunderidge Drive Sargent & Lundy Engineers Rockford, Illinois 61107 55 East Monroe Street Chicago, Illinois 60603 Ms. Lorraine Creek Rt. 1, Box 182 Mr. Julian Hinds. Manteno, Illinois 60950 U, S. Nuclear Regulatory Commission Byron / Resident Inspectors Offices ,

4448 German Church Road Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering ,

Illinois Department of '

Nuclear Safety 1035 Outer Park Drive Springfield, Illinois 62704 i

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