ML20140D731

Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing

ML20140D731
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/20/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20140D728	List: ML20140D722 ML20140D731
References
GL-83-28, NUDOCS 8603260452
Download: ML20140D731 (2)

Text

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ENCLOSURE o

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO LICENSEE RESPONSE TO GENERIC LETTER 83-28 DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR Docket No. 50-409 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 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)."

B. Licensee's Response'to Generic Letter (GL) 83-28 By letter dated October 25, 1983, Dairyland Power Cooperative responded to specific items of GL 83-28. 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.

2.0 Evaluation 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 jn 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 October 25, 1983, submittal for this , item and has determined it to be adequate in content.

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b 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 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 October 25, 1983, submittal for this item and has determined it to be adequate in content.

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

O Principal Contributor: T. E. Taylor.

Dated: MAR 2 01988 a