ML20207Q645

Safety Evaluation Supporting Util 831104,840116 & 0731 Responses to Generic Ltr 83-28,Item 4.4 Re Maint & Test Procedures for Silicon Controlled Rectifiers

ML20207Q645
Person / Time
Site:	Crystal River
Issue date:	01/09/1987
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207Q644	List: ML20207Q643 ML20207Q645
References
GL-83-28, GL-85-10, NUDOCS 8701280444
Download: ML20207Q645 (2)

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20665

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GENERIC LEITER 83-28, ITEM 4.4 IMPROVEMENTS IN FAINTENANCE AND TEST PROCEDURES FOR B&W PLANTS CRYSTAL RIVER NUCLEAR PLANT, UNIT 3 DOCKET NO. 50-302 INTRODUCTION AND

SUMMARY

, Generic Letter 83-28I 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 shall be included in the surveillance and test requirements sections of the Technical Specifications.

This report is an evaluation of the response submitted by Florida Power Corporation, the licensee for the Crystal River Nuclear Plant, Unit 3, 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

'l The licensee for the Crystal River Nuclear Plant, Unit 3 responded to the rgouire-ments of Item 4.4 4with submittals dated November 4,19832 , January 16, 1984 ,

and July 31, 1984 . The licensee confirmed in these submittals that safety-

related procedures are being used to maintain and test the SCRs. The licensee l

further stated that the procedures used to test the SCRs verify that the SCRs under test have degated and opened the power supply to the control rods. The l 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 the SER for Generic letter 85-10 (Item 4.3 TS -

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 Technical Specification changes are being made to include 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.

Dated: January 9,1987 870128o444 870109 PDR ADOCK 05000302 p PDR

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REFERENCES

1. NRC Letter D. G. Eisenhut to all Licensees of Operating Reactors, 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. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NRC, " Crystal River Unit 3 Response to Generic Letter 83-28," November 4, 1983.

3. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director Division of Licensing, NRC, " Crystal River Unit 3 Technical Specification Change Request No. 111,"

January 16, 1984.

4. Florida Power Corporation letter to NRC, G. R. Westafer to D. G. Eisenhut, Director, Division of Licensing, NPC, " Crystal River Unit 3 Updated Response to Generic Letter 83-28," July 31, 1984.

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