ML17325B736
| ML17325B736 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/27/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325B734 | List: |
| References | |
| GL-83-28, NUDOCS 8507110143 | |
| Download: ML17325B736 (3) | |
Text
ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO LICENSEE RESPONSE TO GENERIC LE'ITER 83-28 INDIANA AND MICHIGAN ELECTRIC COMPANY D.
C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 DOCKET NOS. 50-315'0-316 1.0 introduction A.
Back round 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 info'rmation contained in NUREG-1000, "Generic Implications of ASS 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 A'NS 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 Compo-nents)"; 4.1.,
"RTS Reliability (Vendor Related Modifications)";
and 4.5.1, "RTS Reliability (System Functional Test Description)".
Sections 3.2.1 and 3.2.2 will be evaluated upon receipt of licensee's completed response.
B.
Licensee's Res onse to Generic Letter (GL 83-28 By letters dated November 4, 1983 and March 30,
The licensee summarized the results of the requested review and concluded that all items have been appropriately addressed.
C.
Sco e 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 Testin RTS Com onents "
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 8507110143 850h27 PDR ADOCK 0500Q315 P
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recommended test guidance has been reviewed, evaluated, and where appropriate, included in the test and maintenance procedures or the Technical Specificati'ons.
The staff has evaluated the licensee's November 4, 1983 submittal for this item and has determined it to be adequate in content.
B.
Item 4.1 "RTS Reliabilit (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 November 4, 1983 submittal for this item and has determined it to be adequate in content.
C.
Item 4.5.1 "RTS Reliabilit S stem Functional Test Descri tion "
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 March 30, 1984 submittal for this item (committing to on-line testing of the undervoltage trip device, also the shunt trip upon completion of required modification), and has determined it to be adequate in content.
3.
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.
Dated:
The following NRC personnel have contributed to this Safety Evaluation:
T. E. Taylor