L-2004-036, Proposed License Amendment, Core Operating Limits Report Methodologies - Supplement. Includes Attachment 1, Attachment a - Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 January 8, 2004 (Nonproprietary)

Proposed License Amendment, Core Operating Limits Report Methodologies - Supplement. Includes Attachment 1, Attachment a - Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 January 8, 2004 (Nonproprietary)

ML040440330
Person / Time
Site:	Saint Lucie
Issue date:	02/11/2004
From:	Jefferson W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EMF-2310(P)(A), EMF-2328(P)(A), L-2004-036
Download: ML040440330 (23)

Text

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 February 11, 2004 FPL L-2004-036 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 - Core Operating Limits Report Methodologies - Supplement By letter L-2002-078 dated May 22, 2002 and supplemented by L-2002-242 on December 5 2002, Florida Power & Light (FPL) submitted a proposed license amendment to update the list of topical reports listed in Technical Specification (TS)

Section 6.9.1.11.b. The proposed change would revise the Core Operating Limits Report (COLR) methodology list to add two NRC approved topical reports, EMF-2310 (P)(A) and EMF-2328 (P)(A), and delete certain topical reports which are superseded by other listed reports. Additionally, consistent with Technical Specification Task Force (TSTF) 363, the referencing of the topical reports would be changed to cite each report only with the report number and title.

L-2002-242 provided the FPL response to the NRC request for additional information (RAI) dated October 31, 2002. The attached information supplements FPL letter L-2002-242 with the Framatone ANP, Inc. sample problem to demonstrate the use of the S-RELAP5 methodology for a specific application to St. Lucie Unit 1.

Attachments 1 and 2 are non proprietary and proprietary versions of the Framatone analysis, respectively, for the loss of forced reactor coolant flow analysis for St. Lucie Unit 1. Framatone ANP, Inc. has determined that the information in Attachment 2 is proprietary in nature. Therefore, it is requested that Attachment 2 be withheld from public disclosure in accordance with the provisions of 10 CFR 2.790(a)(4). The Framatone reasons for the classification of this information as proprietary and the signed affidavit are included as part of Attachment 2.

The original No Significant Hazards Determination bounds the information provided in this supplement. In accordance with 10 CFR 50.91 (b) (1), a copy of the supplement is being forwarded to the State Designee for the State of Florida.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information e( ° an FPL Group company

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Page 2 Please contact George Madden at 772-467-7155 if there are any questions about this submittal.

William Je$Krsi Vice President St. Lucie Plant WJ/GRM Attachments cc: Mr. W. A. Passetti, Florida Department of Health and Rehabilitative Services Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Page 3 STATE OF FLORIDA )

) ss.

COUNTY OF ST. LUCIE )

William Jefferson, Jr. being first duly swom, deposes and says:

That he is Vice President, St. Lucie Plant, for the Nuclear Division of Florida Power &

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 of his knowledge, information, and belief, and that he is authorized to execute the document n behalf aid Li see.

Williff Jef on Jr.

STATE OF FLORIDA COUNTY OF ST LUCIE Sworn to and subscribed before me this I ( day of E-eLAlAt~L1C, 2004 by William Jefferson, Jr., who is rsonally known to me.

Kae oNofia c - tate of Florida 141%

.wq;' Lesfe . Whitwell MYCOMMISSION1 DD020212 EXPIRES May 12A SONOWE11HRUTROY2005 FAININ4SURANCE.IN (Print, type or stamp Commissioned Name of Notary Public)

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 2 Page 1 AFFIDAVIT STATE OF WASHINGTON )

) s.

COUNTY OF BENTON )

1. My name is Jerald S. Holm. I am Manager, Product Licensing, for Framatome ANP, Inc. (FANP"), and as such I am authorized to execute this Affidavit.

2. I am familiar with the criteria applied by FANP to determine whether certain FANP information is proprietary. I am familiar with the policies established by FANP to ensure the proper application of these criteria.

3. I am familiar with the FANP information in the report denoted as Attachment A, Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1, dated January 9, 2004, and referred to herein as Document.' Information contained in this Document has been classified by FANP as proprietary in accordance with the policies established by FANP for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by FANP and not made available to the public.

Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.

5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 2 Page 2

6. The following criteria are customarily applied by FANP to determine whether information should be classified as proprietary:

(a) The information reveals details of FANP's research and development plans and programs or their results.

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for FANP.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for FANP in product optimization or marketability.

(e) The information is vital to a competitive advantage held by FANP, would be helpful to competitors to FANP, and would likely cause substantial harm to the competitive position of FANP.

7. In accordance with FANP's policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside FANP only as required and under suitable agreement providing for nondisclosure and limited use of the information.

8. FANP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 2 Page 3

9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

SUBSCRIBED before me this T day of January, 2004.

Susan K. McCoy l NOTARY PUBLIC, STATE OF WAS1D MY COMMISSION EXPIRES: 1/10/04 Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 1 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 1 ATTACHMENT A Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 January 8, 2004 Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 2 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 2 Contents 1.0 Introduction ..................................... 3 2.0 Identification of Causes and Event Description ................................... 3 3.0 Acceptance Criteria ..................................... 3 4.0 Methodology ...................................... 4 4.1 Nodalization ...................................... 4 4.2 Chosen Parameters and Conservative Input ..................................... 4 4.3 Sensitivity Studies ..................................... 4 5.0 Definition of Events Analyzed and Bounding Input .................................... 5 6.0 Results ...................................... 5 7.0 Conclusions ...................................... 5 8.0 References ...................................... 5 Tables Table 1 Key Assumptions ........................... 6 Table 2 Key Input Parameter Biasing .7 Table 3 Sequence of Events .8 Figures Figure 1 S-RELAP5 Reactor Vessel Nodalization .9 Figure 2 S-RELAP5 Reactor Coolant System Piping Nodalization .10 Figure 3 S-RELAP5 Steam Generator Secondary and Steam Line Nodalization .11 Figure 4 Reactor Power .12 Figure 5 Pressurizer Pressure .13 Figure 6 Reactor Coolant Temperatures .14 Figure 7 RCS Flow Rates .15 Figure 8 Total Reactivity .16 Figure 9 Pressurizer Level .17 Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 3 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 3 1.0 Introduction The analysis documented herein describes a Loss of Forced Reactor Coolant Flow (LOF) analysis for the St. Lucie Unit 1 (SLA) nuclear power plant. This analysis is performed as a sample problem to demonstrate the use of the Reference I methodology to the SLA plant. The deterministic minimum departure from nucleate boiling ratio (DNBR) is not calculated herein since the evaluation of the DNBR margin Is performed statistically each cycle as part of the DNB limiting condition of operation (LCO) verification.

2.0 Identification of Causes and Event Description The LOF event is characterized by a reduction In forced reactor coolant system (RCS) flow while the plant Isoperating. A loss in RCS flow is either partial or total. Partial loss of flow may be due to a failure of a pump motor (i.e. mechanical failure, loss of power supply, or unintentional trip). Total loss of flow may be due to the concurrent loss of electrical power to all pump motors. A total loss of flow Is a more severe event and is the event analyzed here.

The LOF event results In a degradation of core heat transfer, reduction in departure from nucleate boiling (DNB) margin, and a challenge to the DNB specified acceptable fuel design limit (SAFDL).

DNBR margin is also reduced due to the decrease In primary system flow and resulting increase in core coolant temperatures. This increase in core coolant temperatures will also cause the primary volume to increase, resulting in an increase in the primary system pressure.

The LOF event is generally not sensitive to neutronics parameters because it occurs so rapidly. The event is assumed to occur at beginning of cycle (BOC) with a maximum positive Technical Specification moderator temperature coefficient (MTC) at full power.

3.0 Acceptance Criteria This event Is classified as a Condition 11event. Consistent with the plant licensing basis, the acceptance criterion for this analysis is protection of the DNB limit. No single failure will affect the analysis for this event.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335.

L-2004-036 Attachment 1 Page 4 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 4 4.0 Methodology The analysis was performed using the S-RELAP5 methodology (Reference 1). The S-RELAP5 code was used to model the [

4.1 Nodalization The S-RELAP5 primary and secondary side models were nodalized [

The Reference I sample problem, based on a Combustion Engineering reactor, uses the same nodalization as that for SLA. There are therefore no differences between the two models.

4.2 Chosen Parameters and Conservative Input The parameters and equipment states were chosen to provide a conservative estimate of the challenge to DNB. The biasing and assumptions for key Input parameters are consistent with the approved Reference 1 methodology. The key assumptions are given In Table I and the biasing of key parameters Is provided In Table 2. The process of defining the biasing and assumptions for key input parameters Is consistent with the Reference 1 sample problem.

4.3 Sensitivity Studies This event Is controlled primarily by the primary system flow coast down. The S-RELAP5 code assessments in Reference I validate the model relative to this controlling parameter. Thus, no additional model sensitivity studies are needed for this application.

The biasing of input parameters was chosen to produce a conservative estimate of the challenge to DNB. Review of the Input parameter biasing determined that It is conservative for this application.

Thus, no additional Input parameter sensitivity studies are needed.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 5 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 5 5.0 Definition of Events Analyzed and Bounding Input The event Is analyzed at full power conditions since that provides the minimum margin to the DNB limit at the beginning of the event. The event Is also analyzed at BOC conditions. This provides positive moderator reactivity feedback which results in an Increase in power during the event. The input parameter biasing and assumptions for the analysis of this event, shown in Table I and Table 2, are consistent with the approved methodology.

6.0 Results The transient system responses are shown In Figure 4 to Figure 9. The sequence of events is given In Table 3. The results show that the RCS flow rate decreases rapidly to the point where the RCS flow trip Is reached. Reactor power slightly Increases until the reactor trip is reached, then decreases rapidly.

The margin to DNB is statistically calculated as part of the cycle specific DNB LCO verification analysis using the Reference 2 methodology.

7.0 ConclusIons This analysis shows the application of the approved Reference 1 S-RELAP5 methodology to the SLA plant. The protection of the DNB SAFDL Is demonstrated on a cycle specific basis.

8.0 References

1. EMF-2310(P)(A) Revision 0, SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, Framatome ANP, May 2001.

2. EMF-1961(P)(A) Revision 0, Statistical SetpointfTransient Methodology for Combustion Engineering Type Reactors, Siemens Power Corporation, July 2000.

Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 6 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 6 Table I Key Assumptions I

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Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 7 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 7 Table 2 Key Input Parameter Biasing I

I Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 8 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 8 Table 3 Sequence of Events Event Time (sec) l Value Under-Frequency or Initiate Event 0 Under-Voltage on Bus Peak Heat Flux Occurs 0.0 1.8754E+5 Btulhr-ft2 Flow Reaches Low Flow Trip Setpoint 0.85 91% of Initial Low Flow Trip Occurs 1.86 + 1.02 sec. for Trip Delay Banks Release Cont 2.6 + 0.75 sec. for Holding Control Banks Release 2.6 Coils Peak Power Occurs 2.6 2798.7 MW Turbine Isolates 2.7 Pressurizer Spray Actuates 2.7 Peak Pressurizer Pressure Occurs 6.1 2440.7 psia End of calculation 10 Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 9 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 9 I

I Figure 1 S-RELAP5 Reactor Vessel Nodalizatlon Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 10 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 10

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Figure 2 S-RELAPS Reactor Coolant System Piping Nodalization Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment I Page 11 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit I ATTACHMENT A January 8, 2004 Page 11 I

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Figure 3 SRELAP5 Steam Generator Secondary and Steam Line Nodalization Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 12 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 12 3000 2500 F 2000 i 1500 Ca cM1000 500 So 0

0 10 Time s)

Figure 4 Reactor Power Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 13 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit I ATTACHMENT A January 8, 2004 Page 13 2450 qdnn T-,-

2 I 2350

'4 12 a.2300 2250 10 Time (s)

Figure 5 Pressurizer Pressure Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 14 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8, 2004 Page 14 551 C 550 No E

0 549 E

C, C

(O548 547 0 2 4 6 8 10 Time (s)

Figure 6 Reactor Coolant Temperatures Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 15 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit 1 ATTACHMENT A January 8. 2004 Page 15 10000 9000 8000 0

7000 Z.,

co 6000 5000 4000 o

Time (s)

Figure 7 RCS Flow Rates Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 16 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit I ATTACHMENT A January 8, 2004 Page 16 2

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-6 10 Time (s)

Figure 8 Total Reactivity Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information

St. Lucie Unit 1 Docket No. 50-335 L-2004-036 Attachment 1 Page 17 Framatome ANP, Inc.

Results of Loss of Forced Reactor Coolant Flow Analysis for St. Lucie Unit I ATTACHMENT A January 8, 2004 Page 17 70 69

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66 65 0 2 4 6 8 10 Time s)

Figure 9 Pressurizer Level Attachment 2 contains 10 CFR 2.790(a)(4) Proprietary Information