ML20235L172
| ML20235L172 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/16/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235L173 | List: |
| References | |
| NUDOCS 8902270411 | |
| Download: ML20235L172 (7) | |
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.1 UNITED STATES NUCLEAR REGULATORY COMMISSION SOUTHERN CALIFORNIA EDISON COMPANY. ET AL DOCKET NOS. 50-361 AND 50-362-NOTICE OF CONSIDERATION OF' ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES AND OPPORTUNITY FOR HEARING
. The U. S. Nuclear. Regulatory Commission (the Commission) is considering.
issuance of amendments to Facility. Operating License Nos. NPF-10 and NPF-15 issued to Southern California Edison Company (SCE), San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (the licensees), for~ operation of San Onofre Nuclear Generating Station, Units 2 and 3 located in~ San Diego County, California.
The request for amendments was submitted by letter dated November 7, 1988 as revised by letter dated December 29, 1988, and identified as Proposed Change Number PCN-278.
The proposed change _would revise Technical Specifications 3/4.4.8.1,
" Reactor Coolant System, Pressure / Temperature Limits;" 3.4.1.4.1, " Cold Shut-down - Loops Filled;" 3.4.1.3, " Hot Shutdown;" 3.4.8.3.1, " Overpressure Protection System, RCS Temperature s 235'F;" and 3.4.8.3.2, " Overpressure l-A Protection System, RCS Temperature > 235'F." The change would revise the Reactor Coolant System Pressure / Temperature limit curves, LTOP temperatures,
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and associated bases to be effective up to B EFPY of operation.
The maximum allowable Reactor Coolant System pressure at any temperature is based upon the stress limitations for brittle fracture considerations.
Technical Specification 3/4.4.8.1, " Reactor Coolant System, Pressure / Temperature Limits," provides operational constraints in all modes of reactor operation to ensure that the most stress limiting location in the reactor pressure vessel is not susceptible to brittle failure as a consequence of reactor operations.
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embrittlement.of the reactor vessel wall also affects the temperature below
. which low temperature overpressure protection (LTOP) is required.
LTOP is provided by the Shutdown Cooling System (SDCS) relief valves (SDCSRVs) which must be aligned below the specified temperature to provide assurance that the reactor vessel will be operated in the ductile region in accordance with 10 CFR Part 50, Appendix G, during both normal. operation and overpressurization events due to equipment malfunction or operator error.
Technical Specifications' require alignment of the SDCS relief. valves at. temperatures below the temperature corresponding to the PT curve pressurizer relief valve set point of 2500 psia.
The current Unit 2 RCS PT limit curves in the Technical Specification 3/4.4.8,-
Figures 3.4-2 and 3.4-3, are valid for 4 effective full power years (EFPY) and are based on the adjusted RT f 63.3'F.
The current LTOP temperature is NDT 235'F and provides' RCS pressure relief at temperatures below the intersection of the pressurizer relief valve setpoint, 2500 psia, and the 100*F/hr cooldown Curve.
The proposed change would revise the pressure / temperature limits for heatup and cooldown shown in Figures 3.4-2 and 3.4-3, respectively, and the LTOP temperature., based on the fluence at 8 EFPY.
The minimum boltup
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temperature would increase to 86*F as stated in the proposed Technical Speci-l fication 3.4.8.1.d.
An analysis was conducted by the licensees in accordance-with 10 CFR 50, Appendix G; Standard Review Plan Sections 5.2.2 and 5.3.2, ASME B&PV Code,Section III, Division 1; Appendix G; and Regulatory Guide 1.99, Revision 2, May 1988.
Using values listed in the FSAR Table 5.2-5, " San Onofre 2 Beltline Material," an adjusted RT of 120*F was calculated by the licensees NDT
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based on the fluence at 8 EFPY.
Separate heatup and cooldown LTOP temperatures, 312'F and 287*F, respectively, were calculated.
The LTOP heatup and cooldown
. temperatures were determined from the intersections of the pressurizer relief valve setpoint and the 60'F/hr heatup curve and 100*F/hr cooldown curve, respect-ively, at which the LTOP functions must be transferred between the SDCSRVs and the pressurizer relief valve during heatup and cooldown.
The licensees state that the pressure / temperature limits for the closure flange is independent of fluence, and the effect on the heatup and cooldown curves due to the flange has largely disappeared for this operating period. The material correlations were based on the copper and nickel content of the reactor vessel in accordance with the new Regulatory Guide 1.99, Revision 2.
The proposed LTOP controlling pressure of 446 psia corresponds to the calculated maximum RCS pressure which could be reached during a postulated over-pressurization event in the temperature region where the LTOP system is aligned.
Morever, the licensees state that LTOP controlling pressure is more limiting than the PT limit curves, providing added margin that the PT limit is not exceeded.
The licensees believe that the intersections of the LTOP controlling pressure and 60 F/hr heatup curve and 100*F/hr cooldown curve provide the temperature at which the heatup rate can be increased and the cooldown rate must be reduced, and have proposed temperatures of 163'F and 145'F for heatup and cooldown, respectively.
Further reduction in heatup and cooldown rates to 10'F/hr would occur due to more limiting controlling LTOP pressure, at 112*F and 103*F, respectively.
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1 Before issuance of the proposed license amendments, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the J
Act) and the Commission's regulations.
By March 27, 1989 the licensees may file a request for a hearing with respect to' issuance of the amendments to the subject facility operating licenses, and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for hearing and petition for leave to intervene.
Requests for a hearing and petitions for. leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board Panel designated by the Commission or by the Chairman of the Atomic Safety and Licensing Board Panel will rule on the request and/or petition,' and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature l
of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) t.!d possible effect of any order which may i
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7 be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petitionwithoutrequestingleaveoftheBoarduptofifteen(15)daysprior to the first pre-hearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (15) days prior to the first pre-hearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention-set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendments under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Service Branch, or'may be delivered to the Comission's Public Document Room, 2120 L Street, NW, Washington, DC, by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner or representative for the petitioner promptly inform the Comission by a toll-free
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telephone call to Western Union at 1-(800)325-6000(inMissouri 1-(800)342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to George W. Knighton: petitioner's name and telephone number; date petition was mailed; plant name; and publication date 1
and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washington, DC 20555, and to Mr. Charles R. Kocher, Esq., Southern California Edison Company, 2244 Walnut Grove Avenue, P.O. Box 800, Rosemead, California 91770 and Orrick, Herrington and Sutcliffe, Attention: David R. Pigott, Esq., 600 Montgomery Street, San Francisco, California 94111, attorneys for the licensees.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board, that the petition and/or request should be granted based upon a balancing of the factors specified in the 10 l
CFR2.714(a)(1)(1)-(v)and2.714(d).
If a request for hearing is received, the Comission's staff may issue the amendment after it completes its technical review and prior to the completion of any required hearing if it publishes a further notice for public comment of its proposed finding of no significant hazards consideration in i
accordance with 10 CFR 50.91 and 50.92.
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- . For further details with respect to this action, see the application for amendments which is available for public inspection at the Commission's public Document Room, 2120 L Street NW, Washington, DC, and at the General Library, University of California at Irvine, Irvine, California 92713.
Dated at Rockville, Maryland, this16th day of February,1989.
FOR THE NUCLEAR REGULATORY COMMISSION af 4'
George
. Knighton irector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects 9
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