ML20128M909

Safety Evaluation Supporting Util 831104 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1

ML20128M909
Person / Time
Site:	Prairie Island
Issue date:	05/13/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128M880	List: ML20128M876 ML20128M909
References
GL-83-28, NUDOCS 8506030115
Download: ML20128M909 (2)

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION NORTHERN STATE 5 POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT N05. 1 AND 2 GENERIC LtIIER 83-28 REACTOR TRIP BREAKER AUTOMATIC SHUNT TRIP 1.0 Introduction A. Background Information Subsequent to the anticipated transient without scram (ATWS) events at the Salem Nuclear Power Plant, the Consnission 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)"; 4.1, "RTS Reliability (Vendor Related Modifications)"; 4.5.1 "RTS Reliability (System Functional TestDescription)."

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

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By letter dated November 4,1983, Northern States Power Company responded to specific items of GL 83-28. The licensee suninarized the results of the requested review and concluded that all items had 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 sub-mit 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 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 8506030115 DR 850513 ADOCK 05000282 PDR

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staff has evaluated the licensee's November 4,1983, sutimittal for this item and has determined it to be adequate in content.

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 sub-mit 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 verifica-tion 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

. November 4,1983, submittal for this item and has determined it to be adequate in content.

C. Item 4.1,"RTSReliability(VendorRelatedModificationg" The review criteria for this item requires that the licensee submit a statement indicating that he has reviewed all vendor .ecommended reactor trip breaker modifications and determined that (il each modification has been implemented or (2) a written evaluat'on which specifies the technical reasons for not implementing the mot'ification ex{sts. The staff has evaluated the licensee's November 4, 1983 sub-mittal for this item and has determined it to be adequate in content.

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

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The review criteria for this item requires that the licensee submit a statement committing to independent, on-line functional testing of the diverse trip features. The staff has evaluated the licensee's November 4,1983, submittal for this item and has determined it to be adequate in content.

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

Principal Contributor:

T.E. Taylor

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