ML20207S547

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Safety Evaluation Supporting Licensee Response Satisfying Requirements for Matl Resistance to chloride-induced Corrosion in Critical CRD Mechanisms & Helium Circulator Components
ML20207S547
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/11/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207Q712 List:
References
NUDOCS 8703200015
Download: ML20207S547 (1)


Text

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UNITED STATES

,- NUCLEAR REGULATORY COMMISSION

, , wasmNcToN. o. c. 20s55 y m.....f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE EVALUATION OF CHLORINE RELEASE INTO THE PPIMARY COOLANT SYSTEM PUBLIC SERVICE COMPANv 0F COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO 50-267

1.0 INTRODUCTION

By letters dated January 31, March 13 and 26,1985, and July 9, 1986, Public Service Company of Colorado, the licensee, subnitted for our review their evaluation of the role played by chlorine in the Fort St. Vrain primary coolant system with respect to corrosion of various safety-related components. Part I of the evaluation concerned the different sources of chlorine and amounts of chlorine ingressed into the primary system. Part II concerned the corrosion effects of the chlorine. Staff review of Part I was provided to the licensee by letter dated November 13, 1986.

2.0 DISCUSSION This Safety Evaluation concerns Part !!,and was perfomed by Idaho National Engineering Laboratory (INEL) under technical assistance contract to the staff. The results of their review are contained in the attached report EGG-NTA-7502, dated January 1987, entitled " Technical Evaluation Report, Evaluation of Chloride Corrosion in the Primary Coolant System in the Fort St.

Vrain Plant." This report is considered a part of this Safety Evaluation.

3.0 CONCLUSION

The staff has reviewed the INEL report and concurs with its findings and conclusions. Based on this review, the staff concludes that the licensee has satisfied the reouirements for material resistance to chloride-induced corrosion in critical control rod drive mechanitms and helium circulator components where problems due to chloride-induced corrosion had developed.

In addition, the staff concludes that the metallurgical and failure consequence evaluations of the remaining safety-related components fabricated from materials susceptible to chloride-induced corrosion are acceptable, and indicate that adverse effects on plant safety will not occur as a result of postulated failures. The staff considers the issue of chlorine release into the Fort St. Vrain primary coolant system to be resolved.

Principal Contributor: K. Parczewski Dated: March 11, 1987

Attachment:

Technical Evaluation Report B703200015 B70311 PDR ADOCK 05000267 P PDR