ML20215M301
| ML20215M301 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Arkansas Nuclear |
| Issue date: | 10/20/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M243 | List: |
| References | |
| GL-83-28, NUDOCS 8610300151 | |
| Download: ML20215M301 (2) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CONCERNING GENERIC LETTER 83-28, ITEM 4.4 IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B&W PLANTS ARKANSAS NUCLEAR ONE, UNIT 1 DOCKET NO. 50-313 INTRODUCTION AND
SUMMARY
1 Generic Letter 83-28 describes intermediate term actions to be taken by licensees and applicants to address the generic issues raised as a result of the staff's evaluation of the two ATWS events that occurred at Unit 1 of the Salem Nuclear Power Plant.
Item 4.4 of Generic Letter 83-28 required licensees and applicants to confirm that safety-related maintenance and test procedures are applied to the diverse reactor trip feature provided by interrupting power to the control rods through the silicon controlled rectifiers (SCRs).
In addition, the test procedure should verify that the SCRs have degated, thereby removing power from the control rods and the SCRs should be included in the surveillance and test requirements sections of the Technical Specifications.
This report is an evaluation of the response submitted by Arkansas Power and Light Company, the licensee for Arkansas Nuclear One, Unit 1, for Item 4.4 of Generic Letter 83-28. The actual documents reviewed as part of this evaluation are listed in the references at the end of this report.
EVALUATION ThelicenseeforArkansasNuclearOne,UnitIrgspondedtotherequjrementsof Item 4.4 with submittals dated November 5, 1983 and April 24, 1985. The licensee confirmed in these submittals that safety-related procedures are being used to maintain and test the SCRs. The licensee further stated that the pro-cedures used to test the SCRs verify that the SCRs under test have degated and opened the power supply to the control rods. The licensee also stated that Technical Specification changes were being made that would include the SCRs in the maintenance and test requirements section of the Technical Specifications.
The acceptability of these Technical Specification changes will be reported in I
the SER for Generic Letter 85-10 (Item 4.3-T.S.-MPA B-90).
CONCLUSION Based on our review of these responses, we find the licensee's statements confirm that the SCRs are maintained and tested using safety-related procedures. The testing will confirm the opening of the power supply to the control rods, and 8610300151 861020 PDR ADOCK 05000313 P
Technical Specification changes are being made to incl'ude the SCRs in the maintenance and test requirements section of the Technical Specifications.
These actions meet the requirements of Item 4.4 of Generic Letter 83-28 and are acceptable.
REFERENCES 1.
NRC Letter, D. G. Eisenhut to all Licensees of Operating Peactors, Applicants for Operating License, and Holders of Construction Permits,
" Required Actions Based on Generic Implications of Salem ATWS Events (Generic Letter 83-28)," July 8, 1983.
2.
Arkansas Power and Light Company letter to NRC, J. R. Marshall to D. G. Eisenhut. Director, Division of Licensing, NRC, " Arkansas Nuclear One Response to Generic Letter 83-28," November 5, 1983.
3.
Arkansas Power and Light Company letter to NRC, J. Ted Enos to Director of Nuclear Reactor. Regulation, NRC, " Response to RFI - Items 4.4 and 4.5.3," April 24, 1985.
Dated:
October 20, 1986 Principal Contributors:
J. Ramsey D. Lasher
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