ML13319B092
| ML13319B092 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/23/1992 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML13319B090 | List: |
| References | |
| NUDOCS 9801080365 | |
| Download: ML13319B092 (13) | |
Text
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a UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 150 TO FACILITY OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-206
1.0 INTRODUCTION
By letter dated April 2, 1992, Southern California Edison Company (SCE or the licensee) proposed to amend Facility Operating License No. DPR-13 to a Possession-Only License (POL) for the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1 or the facility). The POL would permit the licensee to possess but not operate the facility. Although the SONGS-1 reactor has not been shut down, the licensee has proposed that a POL be approved while the facility is still operating, to become effective upon the permanent cessation of operation and certification to the NRC that all fuel has been offloaded from the reactor and stored in the spent fuel pool.
On May 13, 1992, the NRC published in the Federal Register (57 FR 20518), a Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing for the requested amendment. No public comments nor requests for intervention were received.
2.0 BACKGROUND
SONGS-1 received a Provisional Operating License on March 27, 1967 and began commercial operation on January 1, 1968. A Full-Term Operating License (OL) was not issued until September 26, 1991. The OL was to expire on March 2, 2004, 40 years after the issuance of the SONGS-1 Construction Permit. The delay in issuing the OL was due primarily to an NRC staff reevaluation of the plant design to reconfirm its safety in light of operating experience and updated design standards that had developed since the plant was built in the 1960s.
The NRC staff review concluded that numerous modifications were required to SONGS-1 to upgrade the plant to safety standards that were in effect at newer nuclear power stations. SCE made many of the identified upgrades and 9801080365 921023 PDR ADOCK 05000206 P
-2 committed to complete most of the modifications before restarting the reactor from Refueling Outage 12. Refueling Outage 12 was scheduled at the end of 1992. The NRC formalized the licensee's commitment to complete the SONGS-1 modifications by issuing a Confirmatory Order on January 2, 1990. Based on the formalized commitment to upgrade the plant to contemporary safety standards, the NRC issued the OL in 1991.
While reviewing the SCE rate case, the California Public Utilities Commission (CPUC) concluded that the required upgrades for SONGS-1 were not cost effective and refused to permit the licensee to pass on the cost of the plant modifications to the ratepayers. Lacking a means to recoup the cost of the NRC mandated upgrades, SCE decided to stop power operations at SONGS-1 and requested to amend the license to a POL.
3.0 DISCUSSION AND EVALUATION The licensee has requested that the POL become effective upon certification that all reactor fuel has been removed from the reactor and stored in the spent fuel pool.
The SCE letter of April 2, 1992, requested changes to the license that would permit the licensee to possess and maintain the facility but not operate it. The requested changes to the license are consistent with the expected permanent cessation of operation and reactor defueling. The staff's safety evaluation of the requested license changes is provided in the following paragraphs.
The probability of previously analyzed design basis accidents occurring with the plant in a defueled condition will be significantly reduced for the following reasons: (1) no significant safety hazards could result as the facility will be in a nonoperating condition and the entire core will be in the spent fuel pool; the consequences of credible fuel pool accidents, which are analyzed in Chapters 9 and 15 of the Final Safety Analysis Report, would be unchanged by the POL issuance; and (2) there is reasonable assurance that the common defense and security and the health and safety of public will not be endangered by the defueled, nonoperating status of the reactor. Based on the above, the staff concludes that there are no significant hazards considerations that would result from the issuance of a POL that becomes effective upon the complete defueling of the reactor vessel to the spent fuel pool.
The licensee's letter of April 2, 1992, proposed modifications to the Facility Operating License in order to convert it to a Possession Only License. The staff reviewed these proposals and determined that they are acceptable for the future nonoperating and defueled status of the reactor. In summary, the changes permit the licensee to maintain and possess the facility but not to operate it. The staff's evaluation of these changes is presented below:
- 1. Modify license paragraph 2.B.(1) to replace the reference to use and operation with possession but not operation.
Evaluation: This change is acceptable as it removes the facility from an operating status.
-3
- 2. Modify license paragraph 2.B.(2) to remove the authorization to receive and use special nuclear material used as reactor fuel at the facility.
Evaluation: This change is acceptable as it removes the licensee's authority to receive and use special nuclear material as reactor fuel.
This change is consistent with the eventual nonoperating status of the facility.
- 3. Modify license paragraph 2.B.(3) to remove the reference to reactor startup.
Evaluation: This change is acceptable as it removes an unnecessary use of special nuclear material as sealed neutron sources used only for startup.
In addition, the remainder of this paragraph would properly allow the licensee to receive, possess, and use radioactive devices needed for radiation monitoring and instrument calibration as this use enables monitoring plant and environmental conditions which remain a condition of the POL and the Technical Specifications.
- 4. Modify license paragraph 2.C.(1) to remove the wording which authorizes the facility to operate at core power levels not in excess of 1346 megawatts thermal.
Evaluation: This change is acceptable as it removes the licensed authority to operate the facility. The new paragraph 2.C.(1) will read:
"The licensee is not authorized to operate the facility as a nuclear reactor."
- 5. Modify license paragraph 2.F to reflect that this amendment is effective when the licensee provides certification in writing that all reactor fuel has been permanently offloaded from the reactor and stored in the spent fuel pool.
Evaluation: This change is acceptable in that it reflects the conditions of the reactor vessel that provide the basis for the staff's finding of no significant hazards considerations that would result from the issuance of this POL.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the 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 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
-4 occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards considera tion, and there has been no public comment on such finding (57 FR 20518).
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 the amendment.
6.0 CONCLUSION
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 activities 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: John P. Moulton Date: October 23, 1992
o UNITED STATES R,"
0 NUCLEAR REGULATORY COMMISSION
/g1 WASHINGTON, D. C. 20555 October 23, 1992 MEMORANDUM:
Sholly Coordinator FROM:
John 0. Bradfute, Acting Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactors Regulation
SUBJECT:
REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE (TAC NO. M83123)
Southern California Edison Company, et al., Docket No. 50-206, San Onofre Nuclear Generating Station, Unit No. 1. San Diego County, California Date of application for amendment: April 2, 1992 Brief description of amendment: The amendment modifies Facility Operating License No. DPR-13 to a Possession Only License (POL) upon the permanent cessation of operations and the removal of all fuel from the core.
Date of issuance:
October 23, 1992 Effective date:
Upon certification to the NRC that all reactor fuel has been permanently offloaded from the reactor and stored in the spent fuel pool.
Amendment No.:
150 Facility Operating License No. DPR-13: The amendment modifies the operating license to a POL.
Date of initial notice in FEDERAL REGISTER: May 13, 1992 (57 FR 20518)
The Commission's related evaluation of the amendment is contained in a Safety Evaluation dated October 23, 1992.
No significant hazards consideration comments received: No.
Sholly Coordinator October 23, 1992 Local Public Document Room location: Main Library, University of California, P. 0. Box 19557, Irvine, California 92713 John 0. Bradfute, Acting Project Manager Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation DISTRIBUTION:
Docket File 50-206 ONDD Reading File PDV Reading File JBradfute SWeiss EHyl ton ly'oordinator (Orig+1)
OGC (MS15B18)
JMoulton TQuay RDudley
- See Previous concurrence PDV/LA PDNP/PE*
PDV/PM PDNP/D*
DFoster JMoulton/vsb JBradfuteA" SWeiss 10g.3/92 09/03/92 10/2z/92 09/08/92 DOCUMENT NAME: M83123.JM
53792.
Federal -Register /6
. 57. No. 219 1 Thursday.. November
- 992 / Notices Big Rock Point Inservice Inspection Pennsylvania Power and Lght Date of initial notice in Federal Program be performed in accordance Company. Docket No. 58,3K Register. September Z,1992(57 FR with the Big Rock Point Intergranular Susquehanna Steam Eectric Station, 40218JThe Commission's rated Stress Corrosion Cracking (IGSCC)
Unit 2, Luzerne County, Pennsylvania evaluation of the amendment is Program.
Date contained in a Safety Evaluation dated Date of issuance: October 19, 1992 June of ap po rmendmel October 29,1992.No significant hazards Effective date: October 19,1992 1992, and October 19, 1992 Amendment No.: 108 Brief description of amendment: This Local Public DocumentRoom Facility Operating License No. DPR-6.
amendment changes the Technical location: Osterhout Free Library, The amendment revises the Technical Specifications in support of the Unit 2, Reference Department 71 South Specifications.
.Cycle reload, which will consist of Franklin Street, Wilkes-Barre, Date of initial notice in Federal fresh !NP 9x9(SQB-5) fuel assemblies Pennsylvania 18701.
Register April 29, 1992 (57 FR 18172) and irradiated SNP 9x9(XN-3), (XN-2)
Southern California Edison Company,et The Commission's related evaluation of and (XN.1) assemblies. Changes have al, Docket No. 50-06 San Onofre theamedmet i cotaied n aSafty been made to the following TS and
' Nuclear Generating Station, Unit No. 1, the amendment is contained in a Safety Evaluation dated October 19, 1992.No ases:a. B 2.1 Safety Llmitsb. 3/4.2.1 San Diego County. California significant hazards consideration Average Planar Linear Heat Generation commeicnt consideratNon Ratec. 3/4Z22 APRM Se 'tpoin tad. 3/4.2.3 Ar of aplcainfa92nde comments received: No.Minimum Critical Power Ratioe. 3/44 Local Public Document Room Linear Heat Generation Ratef. 3/4..1 Brief description of amendment: The lucotion: North Central Michigan Recirculation System& B 3/4.1 amendment modifies C4iege, 1515 Howard Street, Petoskey..
Reactivity Control Systemsh. B 3/4.2 Facility Operating License No. DPR Michigan 49770.
Power Distribution Limitsi. B 3/4.4.1 13 to a Possession Only License (POL)
Indiana Michigan Power Company, Recirculation Systex.
53.1 Fuel upon the permanent cessation of Docket No. 50-315, Donald C. Cook Assemblies operations and the removal of all fuel Nuclear Plant, Unit No.1, Berrien Date of Issuance: October 28,1992 from the core.
County,Effective date: October 28,1992 Date of issuanceM.iAc0n 2
CoutyMitanAmendment No.: 91 Effective date: Upon certification to Date of application for amendment.
Facility Operating License No. NPF-the NRC that all reactor fuel has been October 29, 1990 as supplemented June
- 22. This amendment revised the permanently ofoaded from the reactor 13, 1991 and April 13,1992.
Technical Specifications.
and stored in the spent fuel pool Brief description of amendments: This Date of initial notc in Federal Amendment No.: 150 amendment changes Technical Register. September 18,1992(57 FR Specifications (TS) concerning.
4277)The Commission's related 13: The amendment modifies the "Pressure-Temperature Limits," to limit evaluation of the amendment is the maximum heat-up rate to 60 F/hr contained in a Safety Evaluation dated oatintlicene to a edrL and to provide revised heat-up and October 28,1992.No significant hazards Date o al notice in FRal cooldown pressure-temperature (P-T) consideration comments receiveck No Regis n'
M ay 13, 19 the limit curves. In addition, the amendment Local Public Document Room amendment is contained in a Safety changes the TS to reflect revisions to the location: Osterhout Free library, Evaluation dated October 23,1992. No pressure set point and enable Reference Department 71 South significant hazards consideration temperature for the low-temperature Franklin Street. Wilkes-Bare, comments received: No.
overpressure protection system. The Pennsylvania 18701.
Local Public Document Room revisions are based on a reanalysis of Pennsylvania Power and light location: Main library University of reactor vessel sample material in Company, Docket No. 50-38, California, P. 0. Box 19557, rvine, accordance with Regulatory Guide 1.9 Susquehanna Steam Electric Station, California 92713 Revision 2. Through this licensing action Unit 2, Luzerne County, Pennsylvania the guidance of Generic Letter 88-11 has been followed for D. C. Cook, Unit No. 1.
Date of application for amendment Nos. 50-259, 50-260 and 5-296, Browns Date of issuance: October 26,1992 August 7,1992 Ferry Nuclear Plant, Units 1,2 and 3.
Efective date: October 26, 1992
- Brief descrition of amendent This Limestone County, Alabama Ae et
.:171ailt amendment would make a change to the DaeoaplctnIframdets AmendmentsSusquehanna Steam Electric Station Operating Licenses Nos. DPR-58 and (SSES Unit 2 Technical Spefications April 1,1992 (TS 311)
DPR-74. Amendment revised that changes the isolation signal for Brief description of amendments:
theTechnical Specifications.
suppression pool cleanup line valves These license amendments revise the Date of initial notice in Federal HV-25766 and HV-25768 from reactor Browns Ferry Nuclear Plant Technical Register November 28, 1990 (55 FR vessel low water level 3 (+13") or high Specifications by removing provisions 49452).The Commission's related drywell pressure to reactor vessel low that limit the combined interval of evaluation of the amendments is water level 2 (-3W') or high dywjj consecutive surveillances to less than contained in a Safety Evaluation dated pressue.
3.25 times the specified interval in October 2, 1992. No significant hazards Dote o October 29.192 accordance with the guidance of consideration comments received: No.
Effective date: October 29, 192 Generic Letter 89-14.
Local Public Document Room Amendment No. 92 Dote of issumeOctober19, 199 location: Maude Preston Palenske Facility Operting License No. NPF-Effective dotr October19.1992 Memorial Library, 500 Market Street. St.
22This ameei revise4 the Amendment Nos. 188 Unit 1; 203 Unit JosephS Michigan 408tm Te E etr160 Unit
F UNITED STATES DISTRIBUTION VV.
NUCLEARREGULATORY COMMISSION Docket File (50-206)
WASHINGTON, D.C. 20555 PDV Rea ing F le Aradfute December 14, 1992 vDFoster D*C***O EHylton, 11820 DOCKET NO.
5020 Regulatory Publications Branch MEMORANDUM FOR:
Division of Freedom of Information and Publications Services Office of Administration and Resources Management FROM:
Office of Nuclear Reactor Regulation
SUBJECT:
SAN OOFRE NUCLEAR 56NERATING STATION UNIT 1 One signed original of the Federal Register Notice identified below is enclosed for your transmittal to the Office of the Federal Register for publication. Additional conformed copies (
5
) of the Notice are enclosed for your use.
L] Notice of Receipt of Application for Construction Permit(s) and Operating License(s).
Notice of Receipt of Partial Application for Construction Permit(s) and Facility License(s): Time for Submission of Views on Antitrust Matters.
O Notice of Consideration of Issuance of Amendment to Facility Operating License. (Call with -day insert date).
L Notice of Receipt of Application for Facility License(s); Notice of Availability of Applicant's Environmental Report; and Notice of Consideration of Issuance of Facility License(s) and Notice of Opportunity for Hearing.
Notice of Availability of NRC DraftlFinal Environmental Statement.
Notice of Limited Work Authorization.
Notice of Availability of Safety Evaluation Report.
O Notice of Issuance of Construction Permit(s).
O Notice of Issuance of Facility Operating License(s) or Amendment(s).
O Order.
O Exemption.
O Notice of Granting Exemption.
O Environmental Assessment.
O] Notice of Preparation of Environmental Assessment.
Receipt of Petition for Director's Decision Under 10 CFR 2.206.
O Issuance of Final Director's Decision Under 10 CFR 2.206.
I Other:
Correction to Biweekly Notci Division of Reactor Project Ill/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated
Contact:
- j.
Sradfute Phone:
t 5n4-r3&1
7590-01 NUCLEAR REGULATORY CO MISSION CORRECTION TO BIWEEKLY NOTICE APPLICATIONS AND AMENDMENTS TO OPERATING LICENSES INVOLVING NO SIGNIFICANT HAZARDS CONSIDERATIONS In the Biweekly Notice beginning on page 53792 in the issue of Thursday, November 12, 1992, make the following correction:
On page 53792, "Date of issuance: April 2, 1992" should read "Date of issuance: October 23, 1992."
FOR THE NUCLEAR REGULATORY COMMISSION Jes W. Clifford, Director roject Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
7590-01 NUCLEAR REGULATORY COMMISSION CORRECTION TO BIWEEKLY NOTICE APPLICATIONS AND AMENDMENTS TO OPERATING LICENSES INVOLVING NO SIGNIFICANT HAZARDS CONSIDERATIONS In the Biweekly Notice beginning on page 53792 in the issue of Thursday, November 12, 1992, make the following correction:
On page 53792, "Date of issuance: April 2, 1992" should read "Date of issuance: October 23, 1992."
FOR THE NUCLEAR REGULATORY COMMISSION Original signed by James W. Clifford, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation DISTRIBUTION:
Docket File (50-206)
PDV Reading File J. Bradfute D. Foster B. Golden (Orig. + 5 cys)
T. Quay J. Clifford OFC LA/PDV/DRPW PM/PDV/qRPW AD/PDV DRPW NAME DFoster t F
JBrl~f*
Lrmc JCK4brd DATE d/
//92 7*/ 1
/92 ov/I /92 OFFICIAL RECORD COPY DOCUMENT NAME:
BWEEKLY.COR
d~o.50 2
dm 60544.
Federal Regiter I VoL S7, No. 245 Monday,. December 21. 1992 1 Noticeg Endowmfft fir the Arts. Washington.
issuanw.: Apral 2, 1992" should read moDet "0. 50-44 DC 20506, or call (202) 862-5429.
"Date of Unkoe: October 23, 1902."
Dated December 15, 1992.
For the Nuclear faory Commisslan.
TU Eactroc Co. Consideration of Yvonne M. Sabine, James W. Clifford.
Issuance of Amendment to Facilt Director, Panel Operations, National Operating License, Proposed No EndowmentfortheAsts.
Director, Pr*ct Direcieame V, Lywon of Significant Hazards Consideration Reactor ProDects V2-390 F 1 8 :ar ou Determination, and Opportunity for FR Doc. 92-30906 Filed 12-2R2; 8:45 am R
2 5orRe U5ild 1-9 Hearing eCUM CODE 750--
The U.S. Nuclear Regulatory NAINAICINEFONATO Commission (the Commission) is NATIONAL SCIENCE FOUNDATION
.considering issuance of an amendment to Facility Operating License No. NPF Special Emphasis Panel In Docket oOf-0424-LA-3
-87 issued to TU Electric Company (the Atmospheric Sciences; Notice of 3
licensee) for operation of the Comanche Meeting GogPoe a.ata.(Vue Peak Steam Electric Station, Unit I In accordance with the Federal Elcti PoermW C@.,
Unk 1
andtl (CPSES) located in Soalervell County, Advisory Committee Act (Pub. L nUnit and ToXA cU 463, as amended), the National Science The proposed amendment would Foundation announces the following Atomic Safety and Licusing Board revise the Unit 1 Technical ng.
Before Administrative judges:
Specifications.to include revised heatup Date and Time: Wednesday, January 6, Peter B. Bloch. Chair and cooldown curves for the reactor 1993; 8 a.m. to 5 p.m.
Dr. James H. Carpenter coolant system, revised limits for the Place: Room 523. National Science Thomas.
power-operated relief valve (PORV) oundation,.1o G Street, Nw., wangton Re: License A Muanfe setpoints, and the addition of a Type of MeetingtCosed Re mead specification for feedwater isolation DContact Pro:
rSL Ne-valve pressure/temperature limits.
Contacd PerAson tms R.eserh December 14.1992.
These changes are required to support Section Head. Lwe Atwasplire R Decmbr 1, 192 the licensing of Comanche Peak Steam Division of Atmospheric Sciences, National (Limited Appeaances; Preheaing Electric Station Unit 2.
Science Foundation, 1800 G St. NW.,
Conference)
Before issuance of the proposed Washington. DC 20550. Telephone:Psuat to 10 CFR 2.15 and 2.752 license amendment, the Commission Purpose of Meeting: To provide advice and we will hol aPublic linted' will have made findings required by the recommendations concerning proposal appeamae sessiaon from 7 pi to up to Atomic Energy Act of 1954. as amended submitted toNS for financial support.
10 pm (as required), January 11. 1993, (the Act) and the Commission's Agenda: To review and evalate the CAR and a public prehearing conference from TelCois Research Aircraft Flet Resecturing 9 am until 11 am on January 12, at the C
has mae proposal as part of the selection process for Law Enforcement Center, room 240, 401 proposed determination oat te Reason for Cosing:The proposal being Walton Way, Augusta, Georgia 30911.
significant hazards consideration. Under revietd includes information of a Limi appearances may be writtn the Commission's regulations in 10 CFR technica nformaion nacial aa, scd h a or oral. People wishing to speak at the 50.92, this means that operation of the tesals anmperon.
incal ata suchops salaries; and personal information limited appearance session may obtain facility in accordance with the p concerning individuals associated with the priority by mailing a letter on or before amendment would not (1) involve a proposal. These matters are.
une January 5 to: Licensing Board (Georgia significant increase in the probability or U.SA7. 552b(c), (4) and (6) of the Governiment Poe) Uas Nuclear Regulatory consequences of an accident previously in the Snshine Act Commissi4
- 1on, DC 20555.
evaiated, or (2) create the possibility of Dated-December 14.1992, Written appearances may be mailed to a new or different kind of accident from ci Reoecc Winkler, the same address or submitted at the any accident previously evaluated, or Comme Anagwent Officer.
Limited Appearance session. Limited (3) involve a significant reduction in a
[FR Doc. 92-30902 Filed 12-18-92Z 8:45 a Appearances will be listened to or read margin of safety. As required by 10 CFR BUM CODE 7554M-4 carefully but are not part of the 50.91(a). the licensee has provided its decisional record and may not, analysis of the issue of no significant therefore, form a basis for the opinion of hazards consideration, which is NUCLEAR REGULATORY the Board. Each appearance will be presented below.
COMMISSION limited to from five to ten minutes, (1) The proposed changes do not depending on the numberof speakers; involve a significant increase in the Correction ta nweeldy Notice the time limit will be announced at the pr bility orconsequences ofan Applicatio Liens enovng No inningof the session.
a e
viously evaluated.
oprtn Ucenses Involving 140f h SW The following changes affect the Significant Hazards Consideradons For the Atomic Safety and Licensing Board, pressuretemperature limits which In tBel ace n o Bet.6NS define the acceptable regions of In the Biweekly Not"c begining on p
- a.
OPOSSUMo page 53781 ia the issue of Thrsday,
- The 5a psi decrease In heatup/
November 12, 1992, make the followhg Chai cohdown carvec cOn Pal 3r Dco a
- The 39 psi decrease in a portion of Onp p 53792 i the third ratle w
the PORV setpoint curve Comn y,
the Southern Calita.ia Eseeaso s
- The addition of the 2MF/hour Company, a aL hding o c(
seelsoheatup curve; and
605e4 Fed e a.
IL 5.N
.24 o d y j1,j1" ol e Entmnt 16,o the Arts, Washat SUD pi,ig hudra DC 2050., or Call (2012) MZ-54a0.
"Dot ofApM,,.Oco 2
3,9" solgead Date& Decemb~er IS, 1992.
UEetiCc.Cosdaon1 Yvonne hi Sabine, For the Nuclear It" O4y ComElcri oiCnndbdoio Directo. Panel oper +/-
ationl
'1a e W. Cliffor,ZIZ Issuance f A an t F c lt Directo, Poea, Dureerate V~ ai Signaft icns HazrCn~
OA Of tin Fcn.
PO po No
[FRN DE ?-" o fieam-8..g.B4SzJ ctor jw.
I, ? V/ v y
Dete n*"110, and Opportunity for
____Dar-__________Fied_1_-_4-22r SAS am Hearing
____BUM_ CF N
7""Z-3o s hd 1-*.o 4
The U.S. Nuclear Regulatory NAIiONAL ME5 FOUNATIO Commission (the Commissf on) Is SpalJJjI Empha is ( Panel A.O Inconsidering issuance Of an amendment Asperic Scp~iene;Ntc f
[oktnesZ-L_ 045O to Facility Operating License No. NpF..
Meeting 387 issued to TUj Electric Company (the In acordnce iththe ederl G~s Pwer *. at f.; V lcensee) froperation of the Comanche In~~ ~ ~
~
~ ~ ~ ~ ~ ~ ~P a accodanc wihteEdri*cr ~ ~ ~ ~~lctedic S oaine'h Unt Advso ComitteAc (Pub. L 2 )
amendmentru"6919an T 463, as amended), the
-2)ona Foundtio anno w
e fo owj At a isden evs he U i mT eie meeing s he loing Atoic afey nd icasin BordThe Proposed aedntwould 1993; 8n rie to Wdeday, January 6, Beoer Adiitrtv judgeh. Cpcfiainstancuereierha Date; and t Tim Ptere9 6-Chali r~i.Jug and cooldown curves for the reactor Place: Room 523 National SineDr.
James H. &;L-coolant system revised limits for the Foundatin.~ 1800 C Street, NW., Washington Thom D'Mrh POwar-O~eretd relief valve (PORV)
DaldCgi Re: License Amnmn aransfei, a setPoints. and the addition of a TypeOf Aeetj-cose Souher Nuceadspecification for feedwater Isolation Contact Person. EDr Richmrd S.- Creea~ei
'S p%-%
1-01-CLA-.3 vlepesr/eprtr mL h.~
pN These chane r eurdt upr Dvso f tm opheicSc ee Naioa Deembter 14,aans, prggn th iesing of Comanche Peak Steam S c i e n c e F o u n d a t i o n 1 8 0 o G S t. N.
o f r n e h
i e n e r
e u r d t u p r W aehigton DC~.o~ 2Lim'ted Te' Coreheanc Electric Station Unit 2.
357-64&puma 1010 CR 2715Befo~re issuance of the proposed Purpose Of Meeting: To prvd ad ie
[
we w dhl la and w.5 1 icens havem e ndn gsr b the C m iso sPbmlice toie ilhvemd idn subcmted t N"n~ fomiaclspotsssi on
?m7put to up to Atomic aryAtO194samne Agena.Trevie and evaluate the 10CA m (as requied) January 11, 1993.
(the Act) and the Commissisn' ReserchAircft leetResWARand a public prehearing conlerec fio)= reguio)L, rops alart Aicrfth F le wo Res ces fo am until 11 am on Ja u r 2 tt eThe Co nmm ission has ~ade.
an award.
Law E33fOrcement Center, room 240, 401, Proposed determiatin that the Reasocn for Closing: Il propoa being Walton Way, Augusta, Georgia 30911.
amendment request involves no reviewed includes information of a Lmtdsg'i thzrscnieain ne propria ry,. or Li m iteia na ur, p ea race m ay be w ritten h o m s w.
eg ~ t o n 1 F
technical~~ inaoratidn orooral.rationthe rides.
person al Infor atio li i e at th thiseseaon th a op r ton of the concerning indiiduals associae with the Priority by mailin g le ay o obtain facility inac o lda c noth thDe P ro p o sal. T ese m
~
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tte r o r ( e o r e a m e n d m e n t w o u ldea m int h ei P ro b a il ty o U...552b(c), (4) and (6) of the G, eM po W, us. N oar (G ori s' cnseqt ofs an acche pr evaiuly o i eecc Sunl r. Wg, rte n
, as
()5e a u.or 2)c a the possibility of D a t } e i~ 4, 1 9 9~aWi t e r i a m a y b e m a i l e d t o a n e w o r d i f f e r e n t k i n d o f a c c i d e n t f r o m t PA. Rebecca Winklerthe same addr~ess or submitted at tf any accident previous l v ua~ J.o CommffeeP~n~ et fi e Limited Ap ernesession. Liifted (3) involate, aorgiic
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Southern California Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 HAROLD B. RAY TELEPHONE SENIORVICEPRESIDENT April 2, 1992 7144.84oo U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Amendment Application No. 203, San Onofre Nuclear Generating Station, Unit 1 Enclosed is Amendment Application No. 203 to the Facility Operating License No. DPR-13 for San Onofre Nuclear Generating Station, Unit 1. Amendment Application No. 203 consists of Proposed Change No. 254.
The proposed change will modify the Facility License to a "Possession Only License" to allow San Onofre Nuclear Generating Station Unit 1 (SONGS 1) to possess special nuclear material but not operate the nuclear reactor at the completion of Fuel Cycle 11.
SCE has reached an agreement with the California Public Utilities Commission staff to permanently close the plant at the end of fuel Cycle 11, including the possibility of a fuel shuffle and extended fuel cycle operation.
The purpose of the Possession Only License is to provide the licensing basis for the Nuclear Regulatory Commission (NRC) to grant Southern California Edison (SCE) regulatory relief from certain operating requirements that are inappropriate for a permanently shutdown and defueled reactor.
If you have any comments or questions regarding this amendment application, please contact me.
Very truly yours, cc:
J. B. Martin, Regional Administrator, NRC Region V George Kalman, NRC Senior Project Manager, San Onofre Unit 1 J. 0. Bradfute, NRC Project Manager, San Onofre Unit 1 C. W. Caldwell, NRC Senior Resident Inspector, San Onofre Units 1, 2&3 J. H. Hickman, California Department of Health Services r-9O707T6-- 920402 PDR ADOCK 05000206 P