ML20067E769
| ML20067E769 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/11/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067E768 | List: |
| References | |
| NUDOCS 9102180151 | |
| Download: ML20067E769 (3) | |
Text
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8[ suok UNITED STATES
,e NUCLEAR REGULATORY COMMISSION i
- I WA$HIN0?ON, D. C. 20bb6 J
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SAFETY CVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 92 AND S2 TO FACILITY OPERATING LICENSE N05. NPF-10 AND NPF-15 S_0UTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVER 51DE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NOS. 2 AND 3 DOCKET NOS.50-36i AND 50-362 1
1.0 INTRODUCTION
By letter dated November 14, 1990 Southern California Edison Company, et al.
(SCE or the licensee) requested changes to the Technical Specifications (TS) for Facility Operating License Nos. NPF-10 and NPF-15 that authorize operation of San Onofre Nucioar Generating Station, Unit Nos. 2 and 3 in San Diego County, California.
This amendment application is a request to modify TS 3/4.7.2 regarding the minimum pressurization temperature for the San Onfore Unit No. 3 steam generators from 70'F to 90'F based on a vendor recommendation to change the reference nil-ductility transition temperature. : iditionally, the San Onofre Unit Nos. 2 and 3 TS 3/4.7.2 would be clarified to indicate that the pressure / temperature limitation pertains only to the steam get:erator secondary
-side.
Both San Onofre Unit Nos. 2 and 3 bases would be revised to include a change to the reference temperature for the nil ductility transition. -
2.0 EVALUATION During.an engineering review, the licensee discovered a discrepancy regarding thereferencetemperaturefornilductil?tytransition(RT Onofre Unit 3 steam generators.
This discrepancy was baseUDdn) for the San an evaluation 1
of; the limiting secondary side material properties used in the fabrication of the' steam generators for each unit. The licensee documented this issue in Licensee Event Report 90-009 and proceeded to administrative 1y control the San Onofre Unit 3 steam generator pressure / temperature limitation, utilizing a more conservative value.
9102100151 910211
'PDR ADOCK 05000361 P
2 This required administratively raising the minimum pressurization temperature when steam generator secondary pressure is greater than or equal to 200 psig from 70'F to 90*F for San Onofre Unit 3.
This is based upon the guidelines specified in the 1974 Edition of the ASME Boiler and Pressure Yessel Code, Sectior.III, Division 1,SubsectionNC2332D(RT 30*F). The ASME Code requires a more restrictive steam generator tempeNIu+re limitation of a 30*F inargin between the RT and the lowest service temperature. The RT for h
San Onofre Unit 3 was Ntermined to be 60'Ft hence the minimum pres 5DNzation temperature should be 90'F. A similar administrative control was not necessary for San Onofre Unit 2.
The licensee proposed to modify the San Onofre Unit 3 TS 3/4.7.2, " Steam Generator pressure / Temperature Limitation
- and modify the appropriate Bases secticntoreflecta90*FvaluefortheIImiting(conditionforoperation(as opposed to a 70'F value) and a 60*F RT value os opposed to a 30*F value) in the Bases section. This is a more $fiservative value than what is currently in the Technical Specifications and is being administratively contro11et tt these values in the interim. While the San Onofre Unit 2 TS limiting condition for operation is not affected the ap3ropriate Bases section should reflect a revised value of RT from30*
to 40*F. This, too, is a more conservative value. The staff agrV M that these changes are more conservative and appropriate for the San Onofre Units 2 and 3 TS 3/4.7.2.
Moreover, the licensee proposed to make editorial changes to both San Onofre Units 2 and 3 TS 3/4.7.2 and the Bases section. Since TS 3/4.4.8 is a)plicable to the primary side of the sti.am generators the licensee requests t1at TS 3/4.7.2 be modified to ref1tet the secondary side of the steam generators. The staff agrees that this change is editorial in nature and is more correct than what is currently stated.
Therefore, t'ased upon the licensee's letter dated November 14, 1990, and the informatico presented herein, the proposed modifications to the San Onofre Nuclear Generating Station, Unit Nos. 2 and 3. Technical Specifications are accept 6ble.
3,0 ENVIRONMENTAL CONSIDERATION The amendcents involve changes with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, or changes a surveillance requirement. The staff has determined that the anendments 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 issued a proposed finding that the ataendments involve no significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendments meet 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 these amendments.
l
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4.0 CONClj$10N We have concluded, based on the considerations discussed above, that (1) there i
is reasonable assurance that the health and safety of the public will not be 4
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 L
these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Lawrence E. Kokajko Dated:
February 11, 1991 b
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