L-96-333, Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits
| ML17229A181 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/20/1996 |
| From: | Stall J FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17229A182 | List: |
| References | |
| L-96-333, NUDOCS 9612270073 | |
| Download: ML17229A181 (13) | |
Text
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!'CCFSS.'fON NBR:9612270073 DOC.DATE: 96/12/20 NOTARIZED: NO k'ACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co.
AUTH, NAME AUTHOR AFFILIATION STALL,J.A.
Florida Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000335
SUBJECT:
Application for amend to license DP$-67,requesting deletion of footnote re TS 2.1.1, "Reactor Core Safety Limits."
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December 20, 1996 Florida Power 8t Light Company, P.O. Box 128, Fort Pierce, FL 34954-0128 L-96-333 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re:
St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment.
Reactor Core Safet Limit Pursuant to 10 CFR 50.90, Florida Power &Light Company (FPL) requests to amend Facility Operating License DPR-67 for St. Lucie Unit 1 by incorporating the attached Technical Specifications (TS) revision. The amendment willdelete a footnote associated with TS 2.1.1, "Reactor Core Safety Limits," which requires reactor thermal power to be limited to 90% of2700 Megawatts thermal for Cycle 14 operation beyond 7000 Effective Full Power Hours. It is requested that the proposed amendment, ifapproved, be issued prior to May 15, 1997 to permit continued operation ofSt. Lucie Unit 1 at full power.
Attachment 1 is an evaluation ofthe proposed TS change. is the "Determination of No Significant Hazards Consideration." contains a copy ofthe affected TS page marked-up to show the proposed changes.
Enclosed with this submittal is a copy ofreport EMF-96-176, "St. Lucie Unit 1 Small Break LOCAAnalysis with 30% Steam Generator Tube Plugging," Siemens Power Corporation, Revision 1, December 1996.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 8. Light Company Nuclear Review Board. In accordance with 10 CFR 50.91 (b)(1), a copy ofthe proposed amendment is being forwarded to the State Designee for the State ofFlorida.
Please contact us ifthere are any questions about this submittal.
Very truly yours, J. A. Stall Vice President St. Lucie Plant JAS/RLD Attachments 9hi2270073 9hi220
- PDR, ADQCK 05000335 P
Stewart D. Ebnctcr, Regional Administrator, Region II, USNRC.
Senior Resident Inspector, USNRC, St. Lucic Plant.
Mr. W.A. Passctti, Florida Dcpartmcnt ofHealth and Rchabilitativc Scrviccs.
an FPL Group company
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St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment Reactor Core Safet Limit STATE OF FLORIDA
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COUNTYOF ST. LUCIE )
J. A. Stall being first duly sworn, deposes and says:
That he is Vice President, St. Lucie Plant, for the Nuclear Division ofFlorida Power Ec Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best ofhis knowledge, information and belief, and that he is authorized to execute the document on behalf ofsaid Licensee.
J. A. Stall STATE OF FLORIDA COUNTY OF ST. ~uc <<
Sworn to and subscribed before me this ~~
day of DKCFwR8R 19 +k by J. A. Stall, who is personally known to me.
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'DScA Signature ofNotary Public-State ofFlorida o~pSs ~ sg~~ii~
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St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment Reactor Core Safet Limit ATTACHMENT1 EVALUATIONOF PROPOSED CHANGES
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L-96-333 Attachment 1
P~ae I EVALUATIONOF PROPOSED TS CHANGES Introduction The proposed amendment to Facility Operating License DPR-67 for St. Lucie Unit 1 will delete a footnote associated with Technical Specification (TS) 2.1.1,"Reactor Core Safety Limits,"which requires thermal power to be limited to less than or equal to 90% of2700 Megawatts thermal (MWth)for Cycle 14 operation beyond 7000 Effective Full Power Hours (EFPH). The thermal power constraint was imposed in lieu ofperforming a Small Break Loss of Coolant Accident (SBLOCA) re-analysis for fullpower operation that demonstrates acceptable results using input assumptions corresponding to 30% (average) ofall steam generator tubes plugged (SGTP). That analysis has been completed, and a report ofanalysis results is enclosed with this submittal.
Descri tion ofPro osed Chan e
TS 2 1 1 Pa e 2-1: Delete the asterisk following "THERMALPOWER," and delete footnote "*"
shown at the bottom ofpage 2-1.
A copy ofTS Page 2-1, marked-up to show the proposed changes, is contained in Attachment 3.
Back round Amendment No. 145 to Facility Operating License No. DPR-67 (L.A. Wiens (NRC) to T.F.
Plunkett (FPL): ST. LUCIEUNIT 1 - ISSUANCE OF AMENDMENTRE: THERIVfAL MARGINANDREACTOR COOLANT SYSTEM FLOWLIMITS(TACNO. M95472), July 9, 1996) was issued to permit plant operation with up to 30% (average) SGTP and 345,000 gpm minimum Reactor Coolant System (RCS) flow. In support ofthis amendment, FPL had determined that conservatism in the existing SBLOCA analysis, which had previously been performed for conditions corresponding to 25% SGTP and 355,000 gpm RCS flow, would offset any adverse effects due to the increased SGTP and decreased reactor coolant system flowfor full power operation up to 7000 EFPH. To offset any adverse effects for operation beyond 7000 EFPH, it was determined that limitingcore thermal power to 90% ofrated thermal power would provide sufficient margin to ensure 10 CFR 50.46 conformity for the remainder ofoperating Cycle 14.
Subsequent to issuance ofAmendment No. 145, a re-analysis ofthe SBLOCA has been completed using input assumptions corresponding to 30% (average) SGTP and 345,000 gpm RCS flow. The results ofthat analysis are briefly discussed in this evaluation, and data is provided in greater detail in the enclosed Siemens Power Corporation-Nuclear Division Report EMF-96-176, "St. Lucie Unit 1 Small Break LOCAAnalysis with 30% Steam Generator Tube Plugging," Revision 1, December 1996.
L-96-333 Attachment 1
P~ee 2 Bases for TS Chan e
By Amendment No. 145, the NRC approved a license amendment to reduce the RCS flowfrom 355,000 gpm to 345,000 gpm and the low flowtrip setpoint from 95% to 93% ofdesign RCS flow. This amendment supported a SGTP level of30%+ 7%, with a requirement to derate to 90% of2700 MWthprior to exceeding 7000 EFPH ofCycle 14 operation.
The requirement to derate was based on the SBLOCA analysis, which supported a full power operation up to 7000 EFPH and 90% power level beyond 7000 EFPH.
Except for the SBLOCA, acceptable results were shown within the applicable safety limits for all the safety and setpoint analyses at 100% power operation at the amended conditions and a SGTP level of30% + 7%. The SBLOCAwas evaluated at 100% ofrated power up to 7000 EFPH and at 90% power level beyond 7000 EFPH. To support Cycle 14 operation at 2700 MWthto end-of-cycle required a reanalysis ofSBLOCA with the limitingend-of-cycle conditions.
The SBLOCA has been reanalyzed to support Cycle 14 operation at 100% power for the entire operating cycle. The analysis, included as the enclosure to this proposed license amendment, demonstrates acceptable results in compliance with 10 CFR 50.46 criteria. The peak cladding temperature (PCT) was calculated to be 1804'F, well below the acceptance criteria of2200'F.
This analysis was performed by Siemens Power Corporation (SPC), using an NRC-approved SBLOCA evaluation model. The reanalysis was done with changes to input assumptions with respect to the loop seal clearing and the location ofcold leg injection point. The loop seals in the broken loop and one ofthe intact loops were biased to remain plugged. In the current analysis of record, the loop seal in the broken loop did not stay plugged.
Also the safety injection point was moved a node away from the reactor coolant pump to represent a more realistic configuration.
Overall these changes remove some ofthe conservatism as compared to the analysis ofrecord for 25% tube plugging level (EMF-92-148, "St. Lucie Unit 1 Small Break LOCAAnalysis," Siemens Power Corporation, May 1994).
Conclusion The SBLOCA reanalysis, along with the analyses addressed in Amendment No. 145, support operation ofSt. Lucie Unit 1 at 100% ofRATED THERMALPOWER for the entire Cycle 14.
The proposed change supports the reduced RCS flowof345,000 gpm corresponding to a SGTP level of30% + 7% approved in Amendment No. 145.
ATTACHMENT2 DETERMINATIONOF NO SIGNIFICANTHAZARDS CONSIDERATION
L-96-333 P~ae I DETERMINATIONOF NO SIGNIFICANTHAZARDS CONSIDERATION Description ofamendment request:
The proposed amendment willdelete a footnote associated with Technical Specification 2.1.1,"Reactor Core Safety Limits," which requires thermal power to be limited to 90% of2700 Megawatts thermal (MWth) for Cycle 14 operation beyond 7000 Effective Full Power Hours.
Pursuant to 10 CFR 50.92, a determination may be made that a proposed license amendment involves no significant hazards consideration ifoperation ofthe facilityin accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences ofan accident previously evaluated; or (2) create the possibility ofa new or different kind ofaccident from any accident previously evaluated; or (3) involve a significant reduction in a margin ofsafety. Each standard is discussed as follows:
(1)
Operation ofthe facility in accordance with the proposed amendment would not involve a signiTicant increase in the probability or consequences of an accident previously evaluated.
The proposed change willallow full Cycle 14 operation at 100% ofrated power (2700 MWth), by deleting the requirement to derate to 90% ofrated power prior to exceeding 7000 EFPH. This restriction was imposed in the NRC transmittal letter forLicense Amendment 145 for SBLOCA considerations when considering the increased SGTP level of30% + 7%. AllFinal Safety Analysis Report (FSAR) events, other than SBLOCA were evaluated at 100% ofrated thermal power and showed no significant increases in the probability or consequences ofaccidents previously evaluated.
The SBLOCA was reanalyzed to demonstrate continued compliance with 10 CFR 50.46 criteria. There is no impact ofthe proposed change on any FSAR accident initiator. The plant configuration and systems remain unchanged.
Therefore, operation ofthe facilityin accordance with the proposed amendment would not involve a significant increase in the probability or consequences ofan accident previously evaluated.
(2)
Operation ofthe facilityin accordance with the proposed amendment would not create the possibility of a new or different kind ofaccident from any accident previously evaluated.
This proposed amendment removes the requirement in the Technical Specifications to derate to 90% of2700 MWthfor Cycle 14 operation beyond 7000 EFPH. There willbe
L-96-333 P~ae 2 no change to the modes ofoperation ofthe plant. The plant configuration and the design functions ofall the safety systems remain unchanged.
The proposed amendment willnot change the physical plant or the modes ofoperation defined in the facilitylicense.
The changes do not involve the addition ofnew equipment or the modification ofexisting equipment, nor do they alter the design ofSt. Lucie plant systems. Therefore, operation ofthe facilityin accordance with the proposed amendment would not create the possibility ofa new or difFerent kind ofaccident from any accident previously evaluated.
(3)
Operation ofthe facilityin accordance with the proposed amendment would not involve a significant reduction in a margin ofsafety.
The impact ofthe proposed change on'available margin to the acceptance criteria for Specified Acceptable Fuel Design Limits (SAFDL), primary and secondary over-pressurization, peak containment pressure, potential radioactive releases, 10 CFR 50.46 requirements for the large break LOCA, and existing limitingconditions for operation has been evaluated and addressed in the reduced RCS flowoperating license Amendment No.
145. A requirement to derate to 90% of2700 MWthwas imposed based on the SBLOCA analysis.
The small break LOCAanalysis with 30% + 7% SGTP supported operation up to 7000 EFPH at 100% of-rated thermal power. A reanalysis ofSBLOCA with the limitingend-of-cycle conditions at 100% ofrated power, demonstrates continued compliance with 10 CFR 50.46 criteria.
Therefore, operation ofthe facilityin accordance with the proposed amendment would not involve a significant reduction in a margin ofsafety.
Based on the discussion presented above and on the supporting Evaluation ofProposed TS
~ Changes, FPL has concluded that this proposed license amendment involves no significant hazards consideration.