ML17195A800
| ML17195A800 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/16/1985 |
| From: | Thomas Taylor NRC |
| To: | |
| Shared Package | |
| ML17195A799 | List: |
| References | |
| GL-83-28, NUDOCS 8505220075 | |
| Download: ML17195A800 (2) | |
Text
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO LICENSEE RESPONSE TO GENERIC LETTER 83-28 COMMONWEALTH EDISON COMPANY DRESDEN NUCLEAR POWER STATION DOCKET NOS~ 50-237, 50-249
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 licensee. 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);" and 4.5.. 1, "RTS Reliability {System Functional Test Description)."
B.
Licensee's Response to Generic Letter (GL) 83-28 By 1 etters dated November 5, 1983, February 29, and June 1, 1984, Commonwealth Edison 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 responses to determine if the requirements of GL 83-28 have been satisfied. The evaluation for each of the specific items listed 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 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 850S220075 850. 516 Jj',,
~DR ADOCK 05000237.
--. -P Dij -
,..~..... staff has evaluated the licensee's November 5, 1983,. submittal 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 bther 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 November 5, 1983, submittal for this item and has determined it to be adequate in content.
C.
Item 4.5.1, "RTS Reliability (System Functional Test Description)"
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 June 1, 1984, submittal for this item describing the on-line testing of the scram pilot valves (including initiating circuitry) and has determined it to be adequate in content.
3.0 CONCLUSION
The staff concludes that the programs outlined in the licensee's suhmittals adequately address the requirements of Generic Letter 83-28 for the areas specified in this Safety Evaluation.
4.0 ACKNOWLEDGEMENT This Safety Evaluation was prepared by:
T. E. Taylor Dated :
May 16, l 985