ML20114D501

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Safety Evaluation Supporting Amends 44 & 33 to Licenses NPF-76 & NPF-80,respectively
ML20114D501
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 08/27/1992
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114D494 List:
References
NUDOCS 9209090051
Download: ML20114D501 (3)


Text

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%,.... + p SAFETY EVALVATIOR BY THE OFFICE OF NUCLEAR REACTOR REGEATION 7 ELATED TO AMENDMENT N05. 44 AND 33 TO FACillTY OPEF.ATING LICENSE N05. NPF-76 AND NPF-80

. HOUSTON LIGHTING ' POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTR,AL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET N05, 50-498 AND 50-499 SOUTH TEXAS PROJECT. UNITS 1 AND J

1.0 INTRODUCTION

By application dated June 19, 1992, Houston Lighting & Power Company, et.al.,

(the lh ensee) requested changes to the Technical Specifications (Appendix A to facility Operating License Nos. NPF-76 and NPF-89) for the South Texas Project, Units 1 and 2.

The proposed changes would revise the schedule for snubber visual inspections in accordance with the guidance provided in Generic Letter 90-09, " Alternate Requirements for Snubt'er Visual Inspection Intervals and Corrective Actions."

2.0 EVALUATION The snubber visual examination schedule in the existing iechnical Specifi-cation, is based on the permissible number of inos erable snubbers found during the visual examination.

Because the existing snubber visual examination schedule is based only on the absolute number of inoperable snubbers found during the visual examinations irrespective of the total population of l

snubbers, licensee with a large snubber population find the visual exam

  • nation scheduh excessively restrictive.

The purpose of the alternative visual-l exami.atio. schedule is to allow the licenses to perform visual examinations and corret.tive actions during plant outagas without reduction of the

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confidence level provided by the existing visual xamination schedule. The new visual examination schedule specifies the permissible number of inoperable snubbers for various snubber populations.

The basic examination interval is the normal fuel cycle up to 24 months.

This interval may be extended to as long as twice the fuel cycle or reduced to as small as two-thirds of the fuel cycle depending on the numter of unacceptable snubbers found during the visual l

- examination.

The examination interval may vary by 25 percent to coincide l

with the actual outage.

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6 In the event one or more snubbers are found inoperable during a visual examination, the limiting Conditions for Operation (LCO) in the present IS require the licensee to restere or replace the inoperable snubber (s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the attached system inoperable and follow the appropriate action statement for that system.

This LCO will remain in the TS however, the permissible number of inoperable snubber (s) and the subsequent visual examination interval will now be determined in accordance with the new visual examination schedule (Table 1 of Generic letter 90-09, dated December 11, 1990). As noted in the guidance for this line item TS improvement, certain corrective actions may hhve to be performed depending on the number of inoperable snubbers found.

All requirements, for corrective actions and evaluations associated with the use of visual examination schedule and stated in the footnotes 1 through 6, (Table 1 of Generic Letter 90-09) shall be included in the TS.

The licensee has proposed changes to Specification 3/4.7.9 that are consistent with the guidance provided in Generic Letter 90-09 for the replacement of the snubber visual examination schedule with Table 1 (including footnotes )

through 6) of Generic letter 90-09.

On the basis of its review of this matter, the staff finds that the proposed changes to the TS are acceptable.

3.0 RATE COELJATIM in accordance with the Commission's regulations, the Texas State official was notified of the propcsed issuance of the amendment.

The State official had no comments.

4.0 DiVIRONMENTAL CONSJDERATION 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 that the amendment involves no significant increase !n 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 issued a proposeo finding that the amendment invol.*es no significant hazards consider-ation, and there has been no public comment on such finding (57 FR 32573).

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 nr environmental assessment need be prepared in connection with the issuance of the amendment.

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, 5.0 CONCLUkLWi 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 actis, ties 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:

J. Rajan (.-AR/EMEB)

W. Reckley (NRR/PDIV-2)

Date:

August 27, 1992 4

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