ML20199L717
| ML20199L717 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/25/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199L713 | List: |
| References | |
| GL-85-19, TAC-60724, TAC-60725, NUDOCS 8607090578 | |
| Download: ML20199L717 (5) | |
Text
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 50 TO NPF-10 AND AMENDMENT N0.'39 TO NPF-15 SOUTHERN CALIFORNIA EDIS0N COMPANY, ET AL DOCKET N05. 50-361 AND 50-362
1.0 INTRODUCTION
Southern California Edison Company (SCE), on behalf of itself and the other licenses, San Diego Gas and Electric Company, The City of Riverside California, and The City of Anaheim, California, has submitted several applications for license amendments for San Onofre Nuclear Generating Station, Units 2 and 3.
One such request, Proposed Change PCN-214, is evaluated herein. This change would revise Technical Specification (TS) 3/4.4.7, "RCS Specific Activity," in accordance with Generic Letter 85-19,
" Reporting Requirements on Primary Coolant Iodine Spikes." The proposed change would:
(1) delete the short-term reporting re to primary coolant specific activity levels; and (2) quirements related no longer require plant shutdown if the primary coolant iodine activity limits are exceeded for accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />. Our evaluation of the proposed change is given below.
2.0 SAFETY EVALUATION Technical Specifications 3/4.4.7 for San Onofre Units 2 and 3 currently require, among other things, that:
(1) the plant be in a least HCT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if the specific activity of the primary coolant is greater than 1.0 microcurie / gram dose-equivalent I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval; (2) the plant must be shut down if the primary coolant specific activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 month period; and (3) the licensee must submit a special report to the NRC if the total cumulative operating time at a primary coolant specific activity greater than 1.0 tocroct.ric/ gram dose-equivalent I-131 exceeds 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> in any consecutive 6 month period.
On September 27, 1985 the NRC staff issued Generic Letter 85-19, " Reporting Requirements on Primary Coolant Iodine Spikes," to all licensees and applicants for operating power reactors and holders of construction permits for power reactors.
In Generic Letter 85-19, the staff determine that:
(1) reporting requirements related to primary coolant specific activity levels, specifically iodine spikes, could be reduced from a short-term report (special report or licensee event report) to an item to be included in the annual report; and (E) existing shutdown requirements based on exceeding 8637090578 860625 ADOCK 050 g 1 PDR p
the primary coolant specific activity limits for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> were no longer necessary. The change in these requirements is based on an improvement in the quality of nuclear fuel over the past 10 years and the fact that appropriate actions would be initiated long before approaching the limit as currently specified. Generic Letter 85-19 also presented model TS which reflect these findings.
Southern California Edison Company has proposed amending the San Onofre Units 2 and 3 TS to match the model TS and to remove some redundancy between the current actions and surveillance requirements. Although San Onofre Unit 3 has experienced some relatively high specific activity levels in the primary coolant during the first cycle of operation, the specific activity levels at San Onofre Units 2 and 3 have been within the TS limits.
In accordance with Generic Letter 85-19, the portion of the TS regarding plant shutdown if the primary coolant specific activity limits are exceeded for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval would not be affected by the proposed TS change. Since this proposed change is consistent with the Model TS enclosed in Generic Letter 85-19, the NRC staff finds the proposed amendments acceptable.
In summary, the staff has reviewed the proposed changes to TS 3/4.4.7 for San Onofre Units 2 and 3.
The proposed changes would delete the short-term reporting requirements related to primary coolant specific activity levels and no longer require plant shutdown if the primary coolant specific activity limits are exceeded for an accumulated period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />.
As discussed above, the staff finds that the proposed changes meet the applicable regulatory guidance and requirements and are, therefore, acceptable.
3.0 CONTACT WITH STATE OFFICIAL The NRC staff has advised the Chief of the Radiological Health Branch, State Department of Health Services, State of California, of the proposed determination of no significant hazards consideration. No comments were received.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in the installation or use of facility components located within the restricted area. The staff has determined that the amendments involve no significant increase in the amounts of any effluents that may be released offsite and that there is no significant increase in individual or cummulative occupation radiation exposure. The Commission has previously issued proposed findings,that the amendments involve no significant hazards consideration, and there has been no public comment on such findings. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR Sec. 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environ-mental assessment need to be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
The Staff 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, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public. We, therefore, conclude that the proposed changes are acceptable, and are hereby incorporated into the San Onofre 2 and 3 Technical Specifications.
Dated:
June 25, 1986
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TABLE 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES E
o E
Primary Device Backup Device 7
Number Number Service Description E
3B0106 3BLP0101 Containment Normal Cooling Fan E-397 H
3B0107 3BLP0102 CEDM Cooling Supply Fan E-403B w
380109 3BLP0103 CEDM Cooling Supply Fan E-403A 3B0111 3BLP0104 Standby Containment Normal Cooling Fan E-393 3B0209 3BLP0201 Containment Normal Cooling Fan E-394 3B0406 3BLP0301 Hydrogen Recombiner E-145 Power Panel L-180 3B0409 3BLP0302 Upper Dome Air Circulator A-071 3B0410 3BLP0303 Containment Emergency Fan E-399 380411 3BLP0304 Containment Emergency Fan E-401 3B0419 3BLP0305 Standby Upper Dome Air Circulator A-074
,s#
3B0606 3BLP0401 Hydrogen Recombiner E-146 Power Panel L-181 T
3B0609 3BLP0402 Upper Dome Air Circulator A-072 5
3B0610 3BLPO403 Containment Emergency Fan E-400 3B0611 3BLP0404 Containment Emergency Fan E-402 3B0619 3BLP0405 Standby Upper Dome Air Circulator A-073 3B0809 3BLP0501 Containment Normal Cooling Fan E-396 380811 3BLP0601 Containment Normal Cooling Fan E-398 3B0903 3BLP0701 Containment Recirculation Unit A-353 l
380906 3BLP0702 Polar Crane (Containment) R001 (C) 3B0907 3BLP0703 Standby Control Element Drive Mechanisic Cooling Supply Fan E-404A 380909 3BLP0704 Standby CEDM Cooling Supply Fan E-404B 380911 3BLP0705 Containment Recirculating Unit Heater E-568 3E 3BA02 3BLP0812 CCW from RCP P-001 Seal Heat Exchanger TV-9144 E
3BA03 3BLP0813 CCW from RCP P-003 Seal Heat Exchanger TV-9154 E
3BA04 3BLP0801 CEDM Cooling Supply Fan E-403A (3BA04-A)
(Enclosure Heater) 5
June 25, 1096 ISSUANCE OF AMENDMENT h0.50 TO FACILITY OPERATING LICENSE NPF-10 AND AMENDMENT NO. 39 TO FACILITY OPERATING LICENSE NPF-15 SAN ON0FRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DISTRIBUTION
.eDocket-File 50-361/362
""NRC PDR ~~~
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Local POR PRC System i
NSIC PBD7 Reading JLee (8)
HRood OELD LHarmon EJordan BGrimes JPartlow WJones LChandler, OELD CMiles HRDenton DGEisenhut JRutberg AToalston RDiggs, LFMB MVirigilo TBarnhart (8)
FMiraglia/FSchroeder EButcher NThompson
.