ML20247P959

Safety Evaluation Supporting Amends 116 & 105 to Licenses DPR-39 & DPR-48,respectively

ML20247P959
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	05/30/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247P935	List: ML20247P931 ML20247P959
References
NUDOCS 8906060281
Download: ML20247P959 (2)

Text

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I SAFETY.EVALUATIOLEY THE.0FFICE.0E NUCLEAR REACTOR. REGULATION RELATED.TO.ANENDNENT.NO. 116 TO FACILITY 0PERATING.LICENSEiN0..DPR-39 .

AND AMENDMENT NO. 105.TO. FACILITY.0PERATING. LICENSE.NO..DPR-48 COMMONWEALTH. EDISON. COMPANY ZION. NUCLEAR. POWER. STATION, UNITS.I.AND.2 DOCKET.NOS. 50-295.AND.50-304

1.0 INTRODUCTION

On July 8,1983, the Nuclear Regulatory Commission (NRC) issued Generic Letter 83-28 which described actions to be taken by licensees to resolve concerns raised by the Salem ATWS events. Item 4.3 of this Generic Letter requested licensees and applicants to modify the reactor trip _ system on Westinghouse and Babcock & Wilcox-PWRs to automatically actuate the shunt trip attachment of the reactor trip breakers. Bhsed on their review of the proposed Westinghouse design for automatically actuating the shunt trip device, the staff concluded that revisions to the plant Technical Specifications were needed to provide for surveillance testing of the shunt and undervoltage trip devices during power operation.- On May 23, 1985, the staff issued Generic Letter 85-09 to all Westinghouse PWR licensees which clarified the original requirements for testing the trip devices by requiring that the shunt and undervoltage trip devices be tested independently during power operation. In accition, independent testing of the control room manual trip switch and wiring to both trip devices and testing of the reactor trip bypass breakers were required.

These changes are cor.sidered necessary by the staff to ensure reliable operation of the reactor trip breakers.

2.0 EVALUATION By letter dated March 25, 1985, Commonwealth Edison Company (the licensee) proposed revisions to the Zion Technical Specifications to add clarifications in surveillance testing requirements for automatic reactor trip logic in accordance with Generic Letter 83-28. Subsequent to the licensee's submittal, Generic Letter 85-09 was issued on May 23, 1985. This Generic Letter provided extensive guidance for establishing the Technical Specifications required by Generic Letter 83-28. The staff's review of the licensee's submittal dated March 25, 1985, revealed that the licensee did not address the surveillance

. requirements for the reactor trip bypass breakers, and the independent operability testing requirement for the undervoltage and shunt trip attachments for manual. reactor trip function. These deficiencies were communicated to the licensee in a conference call held between the staff and the licensee on March 31, 1989. The licensees's April 17, 1989 submittal addressed the surveillance requirements for the reactor trip bypass breakers, undervoltage and shunt trip ,

attachrent. The staff issued no significant hazard consideration notice on April 28, 1989 (54 FR 18367). )

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The review of April 17, 1989 submittal, revealed that some additional clarifications were desirable for line Item 21 covering the reactor trip breakers in Table 3.1-1. The licensee submitted required changes by a submittal dated May 10, 1989. In addition, some minor editorial changes were proposed by the licensee.

The staff determined that May 10, 1989 submittal did not significantly change licensee's previous submittal dated April 17, 1989, and it did not change the conclusion of no significant hazard consideration evaluation previously performed by the licensee and the staff.

On the basis of its review of the above submittals, the staff concludes that the licensee has provided an acceptable response to the items addressed in the NRC guidance requiring independent testing of the undervoltage and shunt trip attachments during power operation and independent testing of the control room manual switch contacts and wiring to the trip breakers during each refueling outage. .The limiting conditions for operation and the surveillance testing requirements proposed by the licensee are consistent with the guidance provided in Generic Letter 85-09. Therefore, the staff finds that these changes are consistent with the recommendations in Generic Letter 85-09 and are acceptable.

In addition, minor editorial changes proposed by the licensee are found to be acceptable.

2.0 ENVIRONMENTAL. CONSIDERATION These amendments involve a change in the installation or use of the facilities components located within the restricted areas as defined in 10 CFR Part 20.

The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously.

l issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such Tinding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forthin10CFRSection51.22(c)(9). Pursuantto10CFR51.22(b)noenvironmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

3.0 CONCLUSION

We have concluded, based on the considerations discussed above, that: (1)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amenduents will not be inimical to the common defuse ano security or to the health and safety of the public.

Principal Contributor: D. Lasher and C. Patel Dated: May 30, 1989

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