ML20093H732

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Safety Evaluation Supporting Amend 169 to License NPF-6
ML20093H732
Person / Time
Site: Arkansas Nuclear 
Issue date: 10/12/1995
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20093H722 List:
References
NUDOCS 9510200322
Download: ML20093H732 (2)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.1 Ao TO l

FACILITY OPERATING LICENSE NO. NPF-6 J

ENTERGY OPERATIONS. INC.

l ARKANSAS NUCLEAR ONE. UNIT N0.2 DOCKET NO. 50-368 l.0 INTRODUCTION By application dated April 4, 1995, Entergy Operations, Inc. (the licensee),

submitted a request for changes to the Arkansas Nuclear One, Unit 2 (ANO-2),

Technical Specifications (TSs). The proposed changes would delete the requirements associated with the part length control element assemblies (PLCEAs). The PLCEAs are being replaced with full length, full strength control element assemblies (CEAs) during outage number 11 in September / October i

1995. The technical acceptability and the safety aspects of the modification were evaluated by the licensee under the 10 CFR Part 50.59 process.

The proposed TS change merely updates the TSs to reflect the hardware configuration in the plant.

i 2.0 EVALUATION i

In addition to the 73 full length CEAs, the ANO-2 reactor currently contains eight PLCEAs. The PLCEAs contain full strength neutron absorber sections in only the upper 10% of their length and are intended to provide control of axial power distribution.

By the end of the current fuel cycle, Cycle 11, the CEAs will have operated to the end of their evaluated design life and will be replaced during the refueling outage. During this outage, the licensee will also replace the eight PLCEAs with full length CEAs and will designate this as Group P CEAs.

The licensee's operating experience has shown that the CEAs alone are capable of controlling axial power during plant operation and, therefore, PLCEAs are not necessary.

In addition, replacement of the PLCEAs with full length CEAs will allow the Group P CEAs to be used as an additional control group and will provide additional shutdown reactivity worth. The addition of the full length rods is an enhancement to safety in that additional rods will be available to shut down the reactor. New power dependent insertion limits (PDILs) will be developed ta allow this application and will be located in the ANO-2 Core Operating Limits Report (COLR). Based on these facts, the proposed TS changes which eliminate reference to PLCEAs are acceptable.

9510200322 951012 Enclosure PDR ADOCK 05000368 P

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3.0 TECHNICAL CONCLUSION The staff has reviewed the proposed TS changes to ANO-2 which eliminate reference to PLCEAs and finds them acceptable since all PLCEAs will be 4

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replaced by full length CEAs during the next refueling outage.

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4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Arkansas State official was notified of the proposed issuance of the amendment. The State official I

had no comments.

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5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined l

that the amendment involves no significant increase in the amounts, and no i

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 issued a pro-posed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (60 FR 37090).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

L. Kopp Date: October 12, 1995 4

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