ML20134A482
| ML20134A482 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/24/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134A479 | List: |
| References | |
| GL-83-28, TAC-54096, TAC-54097, NUDOCS 8511070100 | |
| Download: ML20134A482 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION WISCONSIY ELECTRIC POWER COMPANY POINT BEACH huCLEAR PLANT, UNIT N05. 1 AND 2 DOCKET NOS. 50-266 AND 50-301 i
GENERIC LETTER 83-28, ITEMS 3.1.1, 3.1.2, 4.1 and 4.5.1 1.0 Introduction A.
Background Information Subsequent to the anticipated transient without scram (ATWS) events at the Salem Nuclear Power Plant, the Comission reviewed intemediate 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 (Reactor Trip System Components); 4.1, Reactor Trip System Reliability (Vendor-Related Modifications); and 4.5.1, Reactor Trip System Reliability (System Functional Testing).
B.
Licensee's Response to Generic Letter (GL) 83-28 By letter dated November 7,1983 Wisconsin Electric Power Company responded to specific items of GL 83-28. The licensee sumarized
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the results of the requested review and concluded that all items have been appropriately addressed.
C.
Scope of RevieE 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 items 3.1.1, 3.1.2, 4.1 and 4.5.1 is given below.
E B f 2.0 Evaluation 3
A.
Items 3.1.1 and 3.1.2, Post Maintenance Testing (Reactor Trip System so Components) 8,g" The review criteria for these items require that the licensee submit C
a statement indicating that he has reviewed plant test and maintenance i
procedures and Technical Specifications to ensure that post-maintenance O
operability testing of safety-related components in the reactor trip mE system is required. Also, the licensee's statement should contain a verification that vendor recomended 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 November 7,1983 submittal for this item and has determined it to be adequate in content.
4.
B.
Item 4.1, Reactor Trip System Reliability (Vendor-Related Modifications)
The review criteria for this item requires that the licensee submit a statement indicating that he has reviewed all vendor recomended 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 November 7,1983 submittal for this item and has determined it to be adequate in content.
C.
Item 4.5.1, Reactor Trip System Reliability (System Functional Testing)
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 7,1985 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 submittal of November 7,1983 adequately address the requirements of Generic Letter 83-28 for the areas specified in this Safety Evaluation.
Principal Contributor:
T. E. Taylor Date: October 24, 1985
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