ML20133E689

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Safety Evaluation Supporting Amends 86 & 73 to Licenses NPF-76 & NPF-80,respectively
ML20133E689
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 01/08/1997
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20133E143 List:
References
NUDOCS 9701130112
Download: ML20133E689 (3)


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UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001

+4.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 86 AND 73 TC 4

FACILITY OPEPATING LICENSE NOS. NPF-76 AND NPF-80 HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET N05. 50-498 AND 50-499 a

SOUTH TEXAS PROJECT. UNITS 1 AND J 1.0,lhTRODUCTION By application dated October 23, 1996, as supplemented by letter dated November 6, 1996, Houston Lighting & Power Company, et al., (the licensee) i requested changes to the Technical Specifications (TSs) (Appendix A to Facility Operating License Nos. NPF-76 and NPF-80) for the South Texas Project, Units 1 and 2 (STP).

The proposed changes would revise TS 3.4.6.1, regarding reactor coolant system (RCS) leakage detection instrumentation, to adopt the requirements found in NUREG-1431, " Standard Technical Specifications Westinghouse Plants," for the RCS leakage detection instrumentation.

2.0 DISCUSSION The leakage detection systems at STP consist of two atmospheric radioactivity monitors, one gaseous and one particulate, and a containment normal sump level and flow monitoring system. The proposed change (1) reduces the number of containment atmospheric radioactivity channels which must be operable from two to one, (2) increases the allowed outage time (A0T) with both containment atmospheric radiation monitors inoperable from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days, and (3) increases the A0T for an inoperable containment normal sump level and flow monitoring system, from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 30 days.

The licensee is requesting the above changes to allow calibration of the containment normal sump level transmitter during power operations. Due to a misunderstanding about the system configuration, the containment normal sump level transmitter loop was not calibrated during the previous outage. As a i

result, the calibration will exceed its frequency on February 1, 1996. While the calibration can physically be done during power operations, the actual time to perform the calibration will take about 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to complete. During this time, the containment normal sump level and flow monitoring system will 9701130112 970108 PDR ADOCK 05000498 p

PDR

, be inoperable, forcing a unit shutdown. This license amendment will permit the calibration to be completed without forcing a unit shutdown.

3.0 EVALUATION 3.1 Reducina the nn=her of operable containment atmosoheric radioactivity channels from two to one.

With this proposed change, the plant will continue to have diverse and independent means of detecting significant changes in the amount of leakage i

from the RCS, including the containment normal sump level and flow monitoring system and at least one of the two containment atmospheric radiation monitors.

Based on the above, the staff finds this change acceptable.

3.2 Increasina the A0T with both containment atmosoberic radiation monitors inocerable from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 30 days.

l This proposed change is based upon the continued availability of an operable l

containment normal sump level and flow monitoring system and the compensatory requirements in the action statements. The proposed action required as a result of this change is an analysis of a containment atmospheric grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or performance of a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (the proposed RCS water inventory balance of at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is an increase in the frequency required by TS 4.4.6.2.1.c, which is once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). The current TSs action is an analysis of a containment atmospheric grab sample at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and performance of a RCS water inventory balance at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

The staff finds that either the grab sample or the water inventory balance is sufficient alternative action since either action will identify changes in RCS l

leakage. The staff finds that the 24-hour interval is appropriate since this interval provides periodic information that is adequate to detect RCS leakage.

The staff finds the 30-day A0T appropriate since it recognizes that at least one other form of continuous leakage detection monitoring is available (the containment normal sump level and flow monitoring system). Based on the above, the staff finds these changes acceptable.

3.3 Increasina the A0T for an inoperable containment normal sumo level and flow monitorina system from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 30 days.

This proposed change is based upon the continued availability of an operable containment atmospheric radiation monitor and the compensatory requirements in the action statements. The proposed action required as a result of this change is performance of a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The current TSs action offers no alternative action except to go to hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to cold shutdown with the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The staff finds that the water inventory balance is sufficient alternative action since this will identify changes in RCS leakage.

The staff finds that i.

the 24-hour interval is appropriate since this interval provides periodic l

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L information that is ade.quate to detect RCS leakage. The staff finds the 30-day A0T appropriate since it recognizes that at least one other form of continous leakage detection monitoring is available (an operable containment i;

atmospheric radiation monitor).

Based on the above, the staff finds these changes acceptable.

4.0

SUMMARY

Based on the above evaluation, the staff finds that the proposed changes to TS 3.4.6.1, regarding RCS leakage detection instrumentation, are acceptable. The staff also notes that the proposed changes are consistent with the requirements found in NUREG-1431, " Standard Technical Specifications Westinghouse Plants," for the RCS leakage detection instrumentation.

5.0 STATE CONSULTATION

4 In accordance with the Comission's regulations, the Texas State official was notified of the proposed issuance of the amendments. The State official had

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no coments.

6.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no 4

significant increase in the amounts, and no signlficant 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 Comission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public coment on such finding (61 FR 64387). 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 l

the amendments.

7.0 CONCLUSION

The Comission 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 Comission's regulations, and (3) the issuance of the amendments will not be inimical to the comon defense and security or to the health and safety of the ptblic.

Principal Contributor:

T. Alexion Date: January 8, 1997 3