ML20128Q837
| ML20128Q837 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/03/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20128Q814 | List: |
| References | |
| NUDOCS 8507150094 | |
| Download: ML20128Q837 (1) | |
Text
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ENCLOSURE SAFETY EVALUATION REPORT FOR DELETION OF PSEUD 0 R0D DROP
{
WOLF CREEK GENERATING STATION DOCKET N0. STN 50-482 7
4 In a letter dated May 17, 1985, Kansas Gas and Electric Company (KG&E) requested an exemption for performance of the pseudo RCCA drop test at 50% power. The safety evaluation for this test at Wolf Creek included a potential for a violation of the F-Delta-H Technical Specification (Specification 3.2.3).
Previously KG&E had requested a one time only g
exemption from Technical Specification 3.2.3.
The primary reason for performing the pseudo RCCA drop rod test is the verification of the Nuclear Instrumentation System (NIS) capability to detect a significantly misaligned rod. This test has been performed on many Westinghouse plants including Union Electric's Callaway Plant.
The test results have always shown that the system has the capability of detecting a misaligned rod.
For the Wolf Creek and Callaway plants, the core / vessel / detector relationship is the same 4
the NIS is the same and the same model detectors are used.
Since the core ar.d NIS are the same for the two plants, the Callaway capability to detect a significantly misaligned rod indicates that Wolf Creek would also detect the rod. The licensee has also agreed that the Wolf Creek test results prior to the pseudo rod drop test will be compared with the corresponding results for Callaway. This will fur'ther verify that the plant response is the same. We agree with the licensee that no useful infonnation would be gained from per-formance of this test at Wolf Creek and thus find it acceptable to delete the pseudo rod drop test from the test program.
3507150094 850703 PDR ADOCK 05000482 P
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