ML20209D317

Application for Amends to Licenses NPF-11 & NPF-18,revising MCPR Safety Limit & Adding Approved Siemens Power Corp Methodology List of TRs for COLR

ML20209D317
Person / Time
Site:	LaSalle
Issue date:	07/07/1999
From:	Jamie Benjamin COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20209D321	List: ML20209D317 ML20209D323
References
NUDOCS 9907130107
Download: ML20209D317 (9)

Text

Commonwealth I.dmn Comp.m)

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• IMalle Genrrating Nation 2601 North 21st Ro.ed

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Marwilles, 11.61311 9 57 Tcl His WW"61 l

l July 7,1999 l United States Nuclear Regulatory Commission i Attention:' Document Control Desk Washington, D.C. 20555 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 i NRC Docket Nos. 50-373 and 50-374 i

Subject:

Request for Technical Specification Change, to Revise MCPR Safety Limit and add an approved Siemens Topical Report

References:

(1) ANFB Critical Power Correlation, ANF-1125(P)(A) and Supplements 1 and 2, Advanced Nuclear Fuels Corporation, April 1990.

(2) ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties, ANF-1125(P)(A),

Supplement 1, Appendix E, Revision 0, Siemens Power Corporation, September 1998.

(3) Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors / Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors: Methodology for Analysis of Assembly Channel Bowing Effects /NRC Correspondence, XN-NF-524(P)(A), Revision 2, and Supplement 1 Revision 2, Supplement 2, Advanced Nuclear Fuels Corporation, November 1990. If lf (4) RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation '

Model, EMF-85-74(P) Supplement 1 (P)(A) and Supplement 2 (P)(A), Siemens Power Corporation, February 1998.

9907130107 990707 PDR ADOCK 05000373 P PDR A Unicom Company

July 7,1999l .

,f ' -

U.S. Nucl:ar Regulatory Commission 4 Paga 2 In accordance with 10 CFR 50.90, Comed requests a change to Technical

. Specifications (TS) of Facility Operating License NPF-11 for LaSalle County Station Unit 1. The proposed changes are to:

1. TS Section 2.1, Safety Limits, to reflect a change to the LaSalle Unit 1 Minimum Critical Power Ratio (MCPR) Safety Limit.

2. TS Section 6.6.A.6 to add an NRC-approved Siemens Power Corporation (SPC) methodology list of Topical Reports for the Core Operating Limits Report.

Cycle specific calculations have been performed for the LaSalle Unit 1 Cycle 9 MCPR Safety Limit using the NRC-approved SPC methodology (References 1,2, and 3). These calculations show that a 1.11 MCPR Safety Limit for two loop operation and a 1.12 MCPR Safety Limit for single loop operation are required for the Unit 1 Cycle 9 core design. Thus, this amendment request proposes to increase the Unit 1 two loop operation MCPR Safety Limit to 1.11 and the single loop operation MCPR Safety Limit to 1.12.

Additionally, Reference 4, RODEX2A Supplements 1 and 2, has been reviewed and approved by the NRC. This Technical Specification amendment request proposes to add the Reference 3 SPC methodology to Section 6.6.A.6.b of the Unit 1 Technical Specifications. This methodology supports RODEX2A licensing applications to 62 GWd/MTU rod-average bumup and fuel rod / assembly / channel growth models and analytical methods up to 54 GWd/MTU assembly-average burnup. The extended

.bumup limits will support future operation with ATRIUM-9B fuel.

l Comed is requesting that this application for amendment request be i reviewed and approved by the NRC Staff prior to October 23,1999. I

- Approval by October 23,1999, which is the scheduled start of LaSalle Unit 1 Refuel 8, is needed to support LaSalle Unit 1 Cycle 9 operation. LaSalle will i

implement this amendment prior to startup of LaSalle Unit 1 Cycle 9. j This request is subdivided as follows:

1. Attachment A gives a description and safety analysis of the proposed c hanges,

2. Attachment B includes the marked up TS pages for the requested changes indicated,

3. Attachment C p'rovides information supporting no significant hazard finding in accordance with 10 CFR 50.92(C),

4. Attachment D provides information supporting an Environmental Assessment, u - .. .. .

l

- July 7,1999 U.S. Nucl: r R:gulatory Commission Pcg3 3 The proposed changes have been reviewed by the Plant Operations Review Committee and the Nuclear Safety Review Board in accordance with the Quality Assurance Program.

Comed is notifying the State of Illinois of this application request for changes to the TS by transmitting a copy of this letter and its attachments to the designated state official Should you have any questions conceming this letter, please contact Frank A. Spangenberg, Ill, Regulatory Assurance Manager, at (815) 357-6761, extension 2383.

Respectfully, M

e . enjamin Site Vice President LaSalle County Station cc: Regional Administrator- NRC Region 1ll NRC Senior Resident inspector - LaSalle County Station i

. ,. July 7,1999 U.S. Nucinr R::gulatory Commission P g3 4 STATE OF ILLINOIS )

COUNTY OF LA SALLE )

IN THE MATTER OF )

COMMONWEALTH EDISON COMPANY )

LASALLE COUNTY STATION - UNIT 1 ) Docket No. 50-373

Subject:

Request for Technical Specification Change, to Revise MCPR Safety Limit and add an approved Siemens Topical Report AFFIDAVIT l affirm that the content of this transmittal is true and correct to the best of my knowledge,information and belief.

I i

J$ _

r njamTn O I Site os President LaSalle County Station Subscribed and swom to before me, a N,oJary Public in and l fopth) St above named, this 7W/ day of

/ A' '

. /999 l. My Commission expires on TV / /-24 .c?GO/ .

aw - Esr anzwu OFFICIAL SEAL

/7 N6ft yP'tiblid (

LYNN ELLEN GASSMAN NOTARY PUBLIC, STATE OF ILUNOIS

. MY COMt#SS10N EXPIRES I 24-2001 i

ATTACHMENT A i

. . Propose Change to Technical Specifications I for LaSalle County Station Unit 1 l Description and Safety Analysis for Proposed Changes A.

SUMMARY

OF PROPOSED CHANGES l li) accordance with 10 CFR 50.90, Comed requests a change to Technical Specifications (TS) of Facility Operating License NPF-11 for LaSalle County Station Unit 1. The proposed changes are to:

1. Section 2.1, Safety Limits, to reflect a change to the LaSalle Unit 1 Minimum Critical Power Ratio (MCPR) Safety Limit.

2. Section 6.6.A.6.b to add an NRC-approved Siemens Power Corporation l (SPC) methodology list of Topical Reports for the Core Operating Limits Report.

Cycle specific calculations have been performed for the LaSalle Unit 1 Cycle 9 MCPR Safety Limit using the NRC-approved SPC methodology (References 1, 2, and 3). These calculations show that a 1.11 MCPR Safety Limit for two loop operation and a 1.12 MCPR Safety Limit for single loop operation are required for the Unit 1 Cycle 9 core design. Thus, this amendment request proposes to ,

increase the Unit 1 two loop operation MCPR Safety Limit to 1.11 and the single l loop operation MCPR Safety Limit to 1.12.  !

Additionally, Reference 4, RODEX2A Supplements 1 and 2, has been reviewed and approved by the NRC. This Technical Specification amendment request proposes to add the Reference 3 SPC methodology to Section 6.6.A.6.b of the Unit 1 Technical Specifications. This methodology supports RODEX2A licensing applications to 62 GWd/MTU rod-average burnup and fuel rod / assembly / channel growth models and analytical methods up to 54 GWd/MTU assembly-average burnup. The extended burnup limits will suppoit future operation with ATRIUM-98 fuel.

B. DESCRIPTION OF THE CURRENT REQUIREMENTS Currently the LaSalle Unit 1 Cycle 8 analysis is based only on GE methods because LaSalle 1 Cycle 8 contains only GE fuel.' The LaSalle Unit 1 Cycle 8 MCPR Safety limit is 1.07 for two loop operation and 1.08 for single loop operation. The MCPR Safety Limit for LaSalle Unit 1 had been approved to be increased to 1.08 for two loop operation and 1.09 for single loop operation for Unit 1 Cycle 9 operation based on the Reference 1 SPC correlation (Reference 6).

Page1of5

r j

.- 1 ATTACHMENT A J

, , Propose Change to Technical Specifications i for LaSalle County Station Unit 1 Description and Safety Analysis for Proposed Changes

The previously approved burnup limits for ATRIUM-9B fuel are 60 GWd/MTU l I

peak pellet and 48 GWd/MTU assembly average burnup. These limits were I approved in Reference 4, which has been approved for inclusion in the LaSalle Unit 1 Technical Specifications (Reference 7).  ;

i O l

C. BASES FOR THE CURRENT REQUIREMENTS The most recent NRC approved MCPR Safety Limit for LaSalle Unit 1 is 1.08, i which was expected to be utilized for LaSalle Unit 1 Cycle 9 operation. This l

MCPR Safety Limit was approved in Referer. e 6 for LaSalle Unit 1 Cycle 9 and j was based on SPC's NRC-approved MCPR Safety Limit correlation and j methodology (References 1 and 5). LaSalle Unit 2 Cycle 8 MCPR Safety Limit l calculations resulted in a 1.08 (two-loop operation) and a 1.09 (single loop )

operation) MCPR Safety Limit. Therefore these values were consistently applied j to Unit 1.

The burnup limits for ATRIUM-9B fuel are 60 GWd/MTU for peak pellet exposure j and 48 GWd/MTU for assembly-average exposure. The current licensing burnup I limite for SPC BWR fuel are based on the NRC-approved burnup limits j established in Reference 4. The most recent approved burnup limits (Reference

3) are 62 GWd/MTU rod average and 54 GWd/MTU assembly-average exposures. i i

l D. NEED FOR THE REVISION OF THE REQUIREMENTS

]

This Technical Specification amendment request proposes to change the  ;

Minimum Critical Power Ratio (MCPR) Safety Limit of LaSalle Unit 1 in order to j support Unit 1 Cycle 9 operation. LaSalle Unit 1 Cycle 9 was approved for i operation with a MCPR Safety Limit of 1.08 for two loop operation and 1.09 for single recircuiation loop operation, with less than 0.1% of the rods predicted to experience boiling transition (Reference 6). Since the approval of Reference 6, LaSalle Unit 1 Cycle 9 cycle-specific MCPR Safety Limit calculations have been i completed. Siemens Power Corporation (SPC) has evaluated the MCPR Safety l Limit for LaSalle Unit 1 Cycle 9 using the Reference 1 NRC-approved correlation  :

with the approved ATRIUM-9B additive constant uncertainty (Reference 2). The  !

evaluation determined that the most recently approved MCPR Safety Limit of 1.08 for two loop operation /1.09 for single loop operation (Reference 6) needs to be changed for L1C9 operation. To ensure LaSalle 1 Cycle 9 operation with less than 0.1% of the rods predicted to experience boiling transition, a 1.11 two loop

. Page 2 of 5 i

- l ATTACHMENT A '

, , Propose Change to Technical Specifications l for LaSalle County Station Unit 1 l Description and Safety Analysis for Proposed Changes 1

and a 1.12 single loop MCPR Safety Limit are required. This increase in MCPR Safety Limit is being driven by the fact that L1C9 is Unit 1's first cycle with ATRIUM-9B fuel and Siemens methodology, has a larger batch fraction, and is a 24-month operating cycle. Therefore, this Technical Specification amendment request proposes to increase the MCPR Safety Limit for LaSalle Unit 1 from 1.08 to 1.11 for two loop operation and from 1.09 to 1.12 for single loop operation. l I

Should future cycle's MCPR Safety Limit calculations prove that a Unit 1 two loop operation MCPR Safety Limit of 1.11 or a single loop operation MCPR Safety Limit of 1.12 are no longer appropriate, a Technical Specification change l would be initiated by Comed to support operation of that cycle. j This amendment request also proposes to add Reference 3 to Section 6.6.A.6.b of the Technical Specifications. This methodology is needed to support the design and operation of future reloads containing ATRIUM-9B fuel. The l Reference 3 NRC-approved methodology permits the use of extended burnup I limits for ATRIUM 9 and 10 designs. Therefore, adding Reference 3 to Section 6.6.A.6.b is needed to support design and operation of future reloads containing ATRIUM-9B fuel.

E. DESCRIPTION OF THE PROPOSED CHANGES This amendment proposes to increase the LaSalle Unit 1 MCPR Safety Limit I from 1.08 to 1.11 for two loop operation and from 1.09 to 1.12 for single loop operation. All MCPR surveillance requirements remain unchanged. This request for amendment proposes the following wording for Technical Specification Section 2.1.2.

l The MINIMUM CRITICAL POWER RATIO (MCPR) shall not be less than 1.11 with two recirculation loop operation and shall not be less than 1.12 with single recirculation loop operation with the mactor vessel steam dome pressure greater than 785 psig and core flow greater than 10% of rated flow.

Page 3 of 5

ATTACHMENT A

, Propose Change to Technical Specifications for LaSalle County Station Unit 1 Description and Safety Analysis for Proposed Changes Similarly, the Section 2.1.2 Action statement and the Section 2.0 Bases are proposed to be revised to reflect the increased MCPR Safety Limit.

This request for amendment proposes the following reference to be included in Technical Specification Section 6.6.A.6.b.

26. RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, EMF-85-74(P), Supplement 1 (P)(A) and Supplement 2 (P)(A), Siemens Power Corporation, February 1998.

F. SAFETY ANALYSIS OF THE PROPOSED CHANGES The basis for revising the MCPR Safety Limit for LaSalle Unit 1 is that LaSalle l Unit 1 Cycle 9 MCPR Safety Limit calculations show that a Safety Limit of 1.08 (two loop operation) and 1.09 (single loop operation) cannot be supported with less than 0.1% of the rods predicted to experience transition boiling.

Conservatively increasing the MCPR Safety Limit to 1.11 for two loop operation and 1.12 for single loop operation ensures LaSalle Unit 1 Cycle 9 operation with fewer than 0.1% of the rods predicted to experience transition boiling.

The basis for adding Reference 3 to Section 6 of the Technical Specifications is to allow use of the NRC-approved extended burnup limits. The extended burnup limits will support future operation with ATRIUM-9B fuel.

G. IMPACT ON PREVIOUS SUBMITALS The Reference 6 Technical Specification Amendment (Number 131 for Unit 1) increased the LaSalle Unit 1 MCPR Safety Limit to 1.08 for two loop operation and 1.09 for single loop operation. The Reference 6 changes to the Unit 1 Technical Specifications will be incorporated for use of ATRIUM-9B fuel and SPC methodologies in LaSalle Unit 1 Cycle 9. This amendment request changes the MCPR Safety Limit approved in Reference 6 from 1.08 to 1.11 for two loop operation and from 1.09 to 1.12 for single loop operation. No other changes made in Reference 6 are impacted by this amendment request.

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4 ATTACHMENT A Propose Change to Technical Specifications for LaSalle County Station Unit 1 Description and Safety Analysis for Proposed Changes ri. SCHEDULE REQUIREMENTS Comed requects approval of this Technical Specification amendment by October 23,1999. The requested approval date was selected to support the LaSalle Unit 1 Refuel 8 schedule. LaSalle Unit 1 willimplement the increased Safety Limit prior to startup of LaSalle Unit 1 Cycle 9.

I. REFERENCES

1. ANFB Critical Power Correlation, ANF-1125(P)(A) and Supplements 1 and 2, Advanced Nuclear Fuels Corporation, April 1990.

2. ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties, ANF-1125(P)(A), Supplement 1, Appendix E, Revision 0, Siemens Power Corporation, September 1998.

3. RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, EMF-85-74(P) Supplement 1 (P)(A) and Supplement 2 (P)(A), Siemens Power Corporation, February 1998.

4. Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9x9-IX and 9x9-9X BWR Reload Fuel, ANF-89-014(P)(A), Revision 1, and Supplements 1 and 2, Advanced Nuclear Fuels Corporation, October 1991.

5. Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Watar Peactors/ Advanced Nuclear Fuels Corporation Critical Power Mnhodology for Boiling Water Reactors:

Methodology for Analysis of Assembly Channel Bowing Effects /NRC Co respondence, XN-NF-524(P)(A), Revision 2, and Supplement 1 Revision 2, Supplement 2, Advanced Nuclear Fuels Corporation, November 1990.

6. NRC SER dated March 16,1999, Issuance of Amendments (TAC Nos. M99548 and M99549), Donna M. Skay to Oliver D. Kingsley.

7. NRC SER dated October 29,1996, issuance of Amendments (TAC Nos. M95156 and M95157), Donna M. Skay to Irene M. Mhnson.

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