ML20135C831
| ML20135C831 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/14/1997 |
| From: | Dennis Morey SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20135C833 | List: |
| References | |
| NUDOCS 9703040325 | |
| Download: ML20135C831 (15) | |
Text
Dave RAeroy Semiluwa lessleer Vice President Opereeing Compeer b
farley Project PO, Box 1295 B.rmingham, />abama 35201 Te; 295 99L5131 February 14, 1997 SOUTB8 M COMPANY Energy so Serve YearWorld" Docket N3s.
50-348 10 CFR 50.90 50.264
_ U. S. Nuclear Regulatory Coadinion
~
ATIN.: Documet Control Desk
[ Washington,DC 20555 %
Joseph M. Farley Nuclear Plant Facably Operating IJoneses and Tachairal Sg nrw han.
Change Raquest for Power Uprating ladies and c elmann-
[
In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC)
L proposes to amend the Facabey Operatmg 11wwmaan and Tachaw=1 tranAr=hans for Joseph M. Farley Nuclear Plant (FNP) Unit I and Unit 2 to allow operation at an increased reactor core power level of 2775 megawatts thermal (MWt). The proposed change to Facihty Operating Licenses NPF-2 and NPF-8 and the Technical Speci6 cations will redse speci6ed maximum power level and de6aition of rated thermal power. In addition, other Techmcal Speci6 cations changes associated with this reqwt are summarized in Attachmmt I.
2 SNC has completed a comprehensive uprate program to increase the bcensed power from 2652 MWt to 2775 MWt that included a reenalysis or evaluation ofImss Of Coolant Accidect (LOCA), non-LOCA, thermal hydraulic, and aietaar aspects of the Nuclear Steam Supply System (NSSS) and balance of plant structures, systems, and nasapaaaa*=. Magor NSSS compoemts (e.g., reactor vessel, pressurizer, rencear acciant pumps, and semani generators); Balance Of Plant (BOP) companaus (e.g., turbine, generosor, naain saammhse isolseina valves, and aand==aar and feedwase pumps); and asjor systems and sub-systems (e.g., safety imiocanon, auxahary feedwater, reendual heat resnoval, eisotrical distribution, emergency diesel guarators, aanemianient coohng, auxihary cochas water, and ultunate hat sink) have been assessed with respect to boundmg conditions ~W for operation at the uprated power levels. Reactor trip and F=p= M Safety Feature (ESF) actuation setpoints have been assessed.
These sapoets, includag the propcmed setpost modi 6 cations, will provide adequate protection for all design basis events Control systems (e.g., rod control, pressurizer pressure and level, turbine overspeed, steam generator level, and steam dump) have been evaluated for operation at uprated conditions and acceptable results were obtamed The uprate analyses / evaluations were performed in accord.tnce with the current FNP bcensing bases except Large Break LOCA (LBLOCA), indiae spiking, and where appropnate, selected other newfunproved methods. The LBLOCA analyses were perfonned using the approved Westinghouse Best Estunate model E COBRA /IRAC. lodme spiking was ana==beed in the radiological assessments as described in NURFG 0800. For selected other analyses / evaluations, the speci6c analyticat tachairtue used for power uprate is referenced or discussed in the attached NSSS and BOP licensing reports The analyses ba=-h.i that operation at the uprated power level can be actueved without changmg the i W7 0 inippsppppppg
/OG 9703040325 970214 i
PDR ADOCK 05000348 P
U.S. Nuclear Regulatory Commission Page 2 crit er.a that have been previously used as the bases for acceptable operaten All acceptance criteria, including LOCA peak cladding temperature, non-LOCA departure from nucleate boiling ratio, containment pressure and temperature, and dose limits continue to be met.
Attachment I summarizes the basis for the prcposed changes to the Facility Operating Licenses and Technical Specifications. Attachment Il provides proposed markups of the Facility Operatmg Licenses Attachment III contains the revised Techmcal Specifications pages Attachment IV provides the sissficant hazards consideraten in accordance with the requirements of 10 CFR 50.92. 'Ihe technical bases fbr the proposed changes are provided by Attachment V, the NSSS Licensing Report, and Attachment VI, the BOP Licensing Report. A*ehmaat VI also includes an environmental evaluation.
SNC has determmed that the proposed changes will not significantly increase the amount of any effluent wiuch may be released offsite and that there is no significant increase in individual or cumulative empar-al r=Amt= exposure. A copy of these proposed changes is being sent to the Alabama State Designee in accordance with 10 CFR 50.91 (b)(1). Southern Nuclear Operatmg Company requests NRC approval of the proposed hoensing changes by January 2,1998. The Unit 2 amendment should become effective prior to catenns Mode 4 for Cycle 13 (Spring 1998), and the Unit I amendment should become effective prior to enterug Mode 4 for Cycle 16 (Fall 1998).
Ifyou have any questmas, please advise.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY b&
Dave Morey Sworn to andsubscribed before me this yof &nh 1997 YYO W
otary Publi8 MyC<
'= Expires:
/. /iW
(.
MGE/ cit:pwrup12. doc Attachments:
I.
Basis For Proposed Changes II. Facility Operating I.: enses Changed Pages III. Techrucal Specificatens Changed Pages IV. Significant Hazards Evaluation V. NSSS Licensing Report VI. BOP Licensing Report cc:
Mr. L. A. Reyes, Region II Adnumstrator Mr. J. I. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health l
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D ve M:r;y Southern Nuclear V e Pesw' Oper:tmg Compny Fane Armer PO Ecs12E E rnm;m A:acama 35201 Ox hl 205 932.5131 J
k February 14, 1997 SOUTHERN L COMPANY Energy o Seml' urWorl?
o Docket Nos.
50-348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission ATfN.: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Facility Operating Licenses and Technical Specifications Chance Recuest for Power Uoratine Ladies and Gentlemen:
In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) proposes to amend the Facility Operating Licenses and Technical Specifications for Joseph M. Farley Nuclear Plant (FNP) Unit I and Unit 2 to allow operation at an increased reactor core power level of G(d 2775 megawatts thermal (MWt). The proposed change to Facility Operating Licenses NPF-2 and NPF-8 and the Technical Specifications will revise specified maximum power level and definition of rated thermal power. In addition, other Technical Specifications changes associated with this request are summarized in Attachment I.
SNC has completed a comprehensive uprate program to increase the licensed power from 2652 MWt to 2775 MWt that included a reanalysis or evaluation of Loss Of Coolant Accident (LOCA), non-LOCA.
thermal hydraulic, and nuclear aspects of the Nuclear Steam Supply System (NSSS) and balance of plant structures, systems, and components. Major NSSS components (c.g., reactor vessel, pressurizer, reactor coolant pumps, and steam generators); Balance Of Plant (BOP) components (e.g., turbine, generator, main steamline isolation valves, and condensate and feedwater pumps); and major systems and sub-systems (e.g., safety injection, auxiliary feedwater, residual heat removal, electrical distribution, emergency diesel generators, containment cooling, auxilia y cooling water, and ultimate heat sink) have been assessed with respect to bounding conditions expected for operation at the uprated power levels. Reactor trip and Engineered Safety Feature (ESP) actuation setpoints have been assessed.
These setpoints, including the proposed setpoint modifications, will provide adequate protection for all design basis events. Control systems (e.g., rod control, pressurizer pressure and level, turbine overspeed, steam generator level, and steam dump) have been evaluated for operation at uprated s
conditions and acceptable results were obtained.
The uprate analyses / evaluations were performed in accordance with the current FNP licensing bases except Large Break LOCA (LBLOCA), iodine spiking, and where appropriate, selected other new/ improved methods. The LBLOCA analyses were performed using the approved Westinghouse p
Best Estimate model _W COBRA / FRAC. Iodine spiking was considered in the radiological assessments b
as described in NUREG-0800. For selected other analyses / evaluations, the specific analytical technique used for power uprate is referenced or discussed in the attached NSSS and BOP licensing reports. 'Ihe analyses demonstrate that operation at the uprated power level can be achieved without changing the
U.S. Nucicar Regulatory Commission Page 2 U
criteria that have been previously used as the bases for acceptable operation. All acceptance criteria, including LOCA peak cladding temperature, non-LOCA departure from nucleate boiling ratio, containment pressure and temperature, and dose limits continue to be met.
Attachment I summarizes the basis for the proposed changes to the Facility Operating Licenses and Technical Specifications. Attachment 11 provides proposed markups of the Facility Operating Licenses.
i Attachment Ill contains the revised Technical Specifications pages. Attachment IV prosides the significant hazards consideration in accordance with the requirements of 10 CFR 50.92. De technical bases for the proposed changes are provided by Attachment V, the NSSS Licensing Report, and Attachment VI, the BOP Licensing Repon. Attachment VI also includes an environmental evaluation.
SNC has determined that the proposed changes will not significantly increase the amount of any effluent 1
which may be released offsite and that there is no significant increase in individual or cumulative aupation.;I radiation exposure. A copy of these proposed changes is being sent to the Alabama State Designee in ac:ordance with 10 CFR 50.91 (b)(1). Southern Nuclear Operating Company requests NRC approval of the proposed licensing changes by January 2,1998. The Unit 2 amendment should become effective prior to entering Mode 4 for Cycle 13 (Spring 1998), and the Unit I amendment should become effective prior to entering Mode 4 for Cycle 16 (Fall 1998).
If you have any questions, please advise.
Respectfully submitted, Ob SOUTliERN NUCLEAR OPERATING COMPANY G3 Rew Dave Morey Sworn to and subscribed before me this y of 0.ch l997 Yk/dstAcvbest$
otary Publi8 My Commission Expires:
/. /k 7
L MGE/ cit:pwrup12. doc Attachments:
1.
Basis For Proposed Changes II. Facility Operating Licenses Changed Pages III. Technical Specifications Changed Pages IV. Significant Hazards Evaluation V. NSSS Licensing Report VI. BOP Licensing Report C_D
" ' ' ^ " " ' ' ' " " * ' " " " ^ ' ~ ' " ' ' ' ' " ' '
Mr. J.1. Zimmerman, NRR Project Manager Mr. T. M. Ross, Plant Sr. Resident Inspector Dr. D. E. Williamson, State Department of Public Health
4 f,
be:
Dr. A. Alapour
' OV Mr. M. G. Eidson l
Mr'. D. E. Grissette Mr. R. D. Hill l
Mr. J. E. Love Mr. K. W. McCracken 4
i Mr. J. W. McGowan Mr. R. J. Morrison Mr. J. A. Posenecker i
Mr. D. J. Shelton i
Mr. R. W. Stewart Mr. J. J. 'Ihomas l
i Mr. R. C. Surman Mr. W. H. Warren i
Mr. L. S. Williams Mr. J. D. Woodard l
NEL Reading File
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NEL CATLIPS i
FNP Document Control RTYPE: A4.54 j
NS File: TS 1.0 I
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I ATTACHMENTI i.
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FARLEY NUCLEAR PLANT 1
1 TECHNICAL SPECIFICATIONS CHANGE REQUEST
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i POWER UPRATE i
l BASIS FOR PROPOSED CHANGES 4
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Joseph M. Farley Nuclear Plant Units I and 2 Facility Operating Licenses & Technical Specifications Change Request for Power Uprating BASIS FOR PROPOSED CHANGES The proposed Technical Specifications changes are summarized in the attached table. The proposed changes are based on performance of new analyses and detailed evaluations to support an increase in Rated Thermal Power (RTP) from 2652 MWt to 2775 MWt. The RTP change will also be incorporated in Section 2.C (1) ofFacility Operating License Nos. NPF-2 (Unit 1) and NPF-8 (Unit 2), where the maximum reactor core power level is stipulated.
Southern Nudear Operating Company (SNC) has completed a comprehensive uprate program to increase the Farley Nuclear Plant (FNP) licensed power from 2652 MWt to 2775 MWt that included a reanalysis or evaluation of LOCA, non-LOCA, thermal hydraulic, and nuclear aspects of the NSSS and Balance Of Plant (BOP) structures, systems, and components.
Major NSSS components (e.g., reactor vessel, pressurizer, RCPs, steam generators) and BOP components (e.g., turbine, generator, MSIVs, condensate and feedwater pumps), and major j
systems and sub-systems (e.g., safety injection, auxiliary feedwater, RHR, electrical Os distribution system, emergency diesel generators, containment cooling, auxiliary cooling water, ultimate heat sink) have been assessed with respect to bounding conditions expected for operation at the uprated power levels. Reactor trip and ESF actuation setpoints and allowable values have been assessed, and the proposed changes will provide adequate protection for all design basis events. Control systems (e.g., rod control, pressurizer pressure and level, turbine overspeed, steam generator level, steam dumps) have been evaluated for operation at uprated conditions. This program was structured consistent with the methodology established in WCAP-10263, "A Review Plan for Uprating the Licensed Power of a PWR Power Plant."
The uprating analytical techniques (methodology and tools) and engineering efforts were performed in accordance with the licensing bases that currently exist for FNP, except for Large Break LOCA (LBLOCA), iodine spiking, and where appropriate, selected other new/ improved methods. The LBLOCA analyses were performed using the approved Westinghouse Best Estimate model F COBRAffRAC to demonstrate Farley meets the criteria of 10 CFR 50.46 for LBLOCA. Where applicable, iodine spiking was considered in radiological assessments as described in NUREG-0800. For selected other analyses / evaluations, the specific analytical technique used for power uprate is referenced or discussed in the NSSS and BOP licensing reports.
r Page1
O The proposed changes to the RTP definition and RCS fluid volume are supported by overall uprate program results. The analyses demonstrate that operation at the uprated power level can be achieved without changing the acceptance criteria and safety limits that have previously been used as the basis for acceptable operation. All acceptance criteria, including LOCA PCT, non-LOCA DNBR, containment pressure and temperature, and dose limits continue to be met.
The Technical Specifications DNB parameters are calculated based on the most limiting analytical values plus indication uncertainties. All values reflect Farley specific analytical values used to verify the adequacy of safe operation at the proposed power level.
Instrumentation uncertainties associated with FNP calibration practices and equipment have been included in the calculation of the final indicated values.
The results of the comprehensive uprate program have afforded the opportunity for FNP to improve operational margins. Revisions to the containment systems bases and test program reflect the results of the maximum peak calculated containment internal pressure fre LOCA and main steam line break analyses. Degraded ECCS pumn flowrates were verifica acceptable for all analyses that are sensitive to these parameters. The modified full power steam flows for MSSVs are consistent with the analyses prepared to support uprate. Results of analyses, such as main steam line break and mass and energy releases, have verified that the increase in O
MSIV stroke time is acceptable. Major NSSS components were reviewed for the increase in the number of secondary side hydrotest transients and found acceptable. The FNP Unit 2 steam generator tube F* distance has been updated for bounding plant conditions associated with uprating and steam generator tube plugging of 20%. These bounding inputs were applied using the NRC approved F' methodology for FNP Unit 2 to develop the revised value of 1.60 inches.
The changes in trip setpoints have resulted from the analyses performed to support operation at the proposed uprated power. The results of the analyses conclude that since all acceptance criteria continue to be met, the proposed values are acceptable. The allowable values were modified based on FNP specific instrument uncertainties, calibration practices, calibration equipment, and installed hardware.
The proposed revisions to the FNP Operating Licenses and Technical Specifications will allow an increase in RTP from 2652 MWt to 2775 MWt with no significant increase in risk or environmental impact.
O Page 2
O In addition to the Technical Specificatiens changes summarized on the attached Table, certain technical specification limits contained in the Core Operating Limits Report (COLR) will be changed for uprate as discussed below. Current Unit 2 operations are based on a nuclear enthalpy hot channel factor of 1.65. An assessment of all pertinent accident analyses resu!!s has verified that the 1.70 value for FJIis acceptable for both Unit I and Unit 2. This change will be incorporated in the COLR to provide consistency between both units and afford flexibility in core design and plant operation. An increase in Fo for VANTAGE 5 fuel from 2.45 to 2.50 has been verified to be acceptable by the results of pertinent analyses including LBLOCA. All analyses acceptance criteria continue to be met. In addition, a " flat" K(Z) curve has been developed which will provide flexibility in core reload design and subsequent operation of FNP. These changes will be incorporated in the COLR for uprate. Unit I and Unit 2 are presently scheduled to implement the uprated reactor core thermal power level for Cycle 16 (Fall 1998) and Cycle 13 (Spring 1998), respectively.
It should be noted that the proposed Technical Specifications changes (marked-up and typed pages) are based on SNC to NRC letters dated September 30,1996 (FNP Technical Specifications Change Request COLR) and January 10,1997 (FNP Technical Specifications Change Request Generic Laser Welded Sleeves for SG Tubes).
O V
uprbas2. doc Page 3
FNP UNITS 1 AND 2
SUMMARY
OF TECHNICAL SPECIFICATIONS CHANGES FOR POWER UPRATE (q/
Section Description Justification v
1.25 Change rated thermal power from Detailed evaluations and analyses 2652 MWt to 2775 MWt.
support the increase in core power.
l Revise RCS fluid volume from 9723 This reflects the best available calculated 5.4 to 9829 ft' and T., from 525 to 567.2'F.
water and steam volume for the RCS.
l 6.9.1.11 For COLR administrative requirements, The Westinghouse Best Estimate LOCA revise reference to LOCA model.
model was used for the uprate analyses.
Table 3.2-1 Change DNB parameters:
These values reflect the input values for B3/4.2.5 Indicated RCS T., to 580.3 *F, uprate accident analyses. All accident Indicated przr. pressure to 2209 psig, analyses acceptance criteria (including Indicated RCS total flow to 264,200 DNBR, LOCA PCT, containment gpm.
response and dose consequences) are met. The DNB parameters reflect FNP i
Bases revisions reflect Farley specific specific uncertainties, procedures and calculation assumptions /results.
calibration practices.
1 4.5.2 g Change CCP pressure from 2458 psig to The flow rates provide margin and were 2323 psid and RHR pressure from 136 verified acceptable from pump, system, pdf to 145 psid.
and analyses perspectives.
O B3/4 6.1.4 Rnise peak calculated containment The rnised Bases and test program i
B3/4.6.1.6 internal pressure for LOCA, i.e., P., from reflect the results of new containment 6.16 48 psig to 43 psig. Indicate that peak analyses performed for uprate.
calculated pressure for MSLB is 53 psig.
B3/4.7.1.1 Revise MSSV steam flow at 100% RTP The rnised Bases will reflect the new from i1,613,849 to 12,270,000 lbs/hr and plant conditions resulting from the percentage of flow from i12 to 105.8%
uprating changes.
4.7.1.5 Revise MSIV closure time from 5 to 7 sec.
This provides margin, and analyses verified ti;c increased stroke time is acceptable.
Table 5.7-1 Increase limit for number of secondary Results of design transients and system hydrotests from 5 to 10.
component evaluations confirm the acceptability of this change.
3/4.4.6 For Unit 2 only, change SG tube F*
Bounding inputs based on uprate B3/4.4.6 dir;ance from 1.54 to 1.60 inches.
conditions were used to establish new value.
Table 2.2-1 Rnise applicable RTS setpoints and The changes in setpoints resulted from allowable values.
analytical values needed to support the increase in RTP. The allowable value Table 3.3-4 Revise applicable ESFAS setpoints and changes resulted from recalculation of allowable values.
these values based on FNP specific w/
instrumentation uncertainty allowances.
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