TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl

Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl

ML20211M273
Person / Time
Site:	Comanche Peak
Issue date:	09/03/1999
From:	Tarrey C TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211M279	List: ML20211M298 TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl
References
TAC-MA4841, TAC-MA4842, TXX-99158, NUDOCS 9909090074
Download: ML20211M273 (8)

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L TXU TXU Electrk 2 C. Lance Terry Comanche Peak 5enior Vice President & Principal Nuclear Officer Steam Electrk station

- P.O. Box 1002 .

Glen Rose.TX 76043 '>

Tel:254 8978920 Fax:254 897 6652 "

. fttrry1@txu.com Log # TXX-99158 File # 10010 916 (5.6)

Ref. # 10CFR50.90 10CFR50.36

' September 3,1999 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 SUPPLEMENT TO LICENSE AMENDMENT REQUEST 98-008 -

CREDIT FOR SOLUBLE BORON IN SPENT FUEL POOLS AND SPENT FUEL STORAGE CAPACITY INCREASE (TAC NOS. UNIT 1 - MA4841, UNIT 2 - MA4842)

REF: 1) TU Electric Letter, logged TXX-99001, from C. L. Terry to the NRC dated February 11,1999

2) TU Electric Letter, logged TXX-95187, from C. L. Terry to the NRC dated July 28,1995, Response to NRC RAI regarding License Amendment Request 94-22, (TAC NOS. M91244 and M91245)

Gentlemen:

Pursuant to 10CFR50.90, TXU Electric requested, via Reference 1, an amendment to

' the CPSES Unit 1 Operating License (NPF-87) and CPSES Unit 2 Operating License (NPF-89) to increase the spent fuel storage capacity by incorporating the changes to

! the CPSES Units 1 and 2 Technical Specifications.

C 9909090074 990903 >Q l l DR ADOCK 0 4j5 .

p TXU TXX-99158 Page 2 of 4-These changes revise the specifications for fuel storage to increase the spent fuel storage capacity, to add fuel pool boron concentration, and to revise the storage configurations in the spent fuel pool. These changes apply equally to CPSES Units 1 and 2.

On July 1,1999, TXU Electric was scheduled to update commitment number 27171 provided by Reference 1. As a result of conversations between the NRC Staff (D. H. Jafee) and TXU Electric (C. B. Corbin) on July 1,1999, and August 25,1999, requests for additional infonnation related to the spent fuel pool temperatures were identified. TXU Electric and the NRC agreed that (1) the update to commitment number 27171 and (2) the response to the NRC request for additional information would be addressed in one transmittal at a later date. The purpose of this letter is to provide the information described above.

Reference 1 contained a new commitment which is repeated below.

Commitment Number Commitment 27171- Complete an evaluation of two new spent fuel storage configurations (3/4 and all cell) by June 1999 to assure the concrete thermal loads remain acceptable for spent fuel pool 2. (See Section 4.0 of Enclosure 1 to TXX-99001 for additional information.)

The evaluation of the two new spent fuel storage configurations (3/4 and all cell) has been completed and the thermal loads remain acceptable for spent fuel pool 2.

Enclosure 1 to Reference 1, stated that for the two new storage configurations high

' density (3/4) and high density (all cell), an administrative restriction would be implemented to assure the concrete thermal loads remain acceptable. The refueling procedures would be revised to prevent discharged fuel from being placed in the high density racks in a high density (3/4) or high density (all cell) configuration until 31 days after the reactor is subcritical. The evaluation has determined that this administrative restriction is not required and therefore the refueling procedures will not be revised to incorporate the 31 day restriction. Page 4-1 of the CPSES Fuel Storage Licensing Report is updated to reflect the results of the completed evaluation of the thermal

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W TXU j TXX-99158 Page 3 of 4 4 loads. l Attachment I to this letter provides the affected page 4-1, marked-up to reflect the changes. Replacement pages for Enclosure 1 to Reference 1 are provided in the Enclosure 1 to TXX-99158 for the CPSES Fuel Storage Licensing Report.

The evaluation of the two new spent fuel storage configurations (3/4 and all cell) resulted in'an update to two figures previously provided by pages 73 and 74 of Attachment I to Reference 2. The updated figures are provided in Enclosure 2.

Reference 2 is also listed as Reference 4(b) in Enclosure 1 of Reference 1.

The NRC's Request for Additional Information and TXU Electric's response are provided in Attachment 2.

The information provided by this letter does not affect the proposed Technical

- Specification changes, the safety analysis of those changes, or the determination that the proposed changes do not involve a significant hazard consideration (provided by_

Attachments 2 and 3 ofReference 1).

In accordance with 10CFR50.91(b), TXU Electric is providing the State of Texas with a copy of this additional information regarding the proposed amendment.

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a TXX-99158

- Page 4 of 4

. Should you have any questions, please contact Carl B. Corbin at (254) 897-0121.

/. Sincerely, C. L. Terry By:

D. R. Woodlan Docket Licensing Manager CBC/cbc Attachments 1. . Marked-up Page 4-1 of the CPSES Fuel Storage Licensing Report i

2. Response to NRC Request for AddniunalInformation. l Enclosures 1. Replacement Pages - Title Page and 4-1 for the CPSES Fuel Storage Licensing Report. .

2. Replacement Pages for Page 73 and 74 of Attachment 1 to j TXX-95187, dated July 28,1995. l

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c- E. W. Merschoff, Region IV J. I. Tapia, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES l

Mr. Authur C. Tate Bureau of Radiation Control Texas Department of Public Health  !

1100 West 49* Street Austin, Texas 78704  ;

Attachment 1 to TXX-99158 Page1of1 4.0 MECHANICAL, MATERIAL AND STRUCTURAL CONSIDERATIONS The mechanical, material and structural considerations contained in Sections 4.1 through Sections 4.6 of Enclosure 1 to Reference 4(a) [as supplemented by Ref 4 (b) through (e)] remain l valid and bounding for the changes in this Licensing Report.

The structural (concrete temperature) analysis performed to support License Amendment

. Request 94-22 [Ref. 4(a)] was based on a core thermal power of 3411 megawatt thermal power (MWt). TU Electric has requested an increase in core thermal power from 3411 MWt to 3445 l l

MWt [Ref. 8]. If the power uprate license amendment is approved as requested, the decay heat of assemblies discharged subsequent to the power uprate will be increased slightly. Therefore the decay heat of previous bounding analyses (based on an assumed total capacity of 3386 spent fuel assemblies) will be increased slightly. The overall impact of the power uprate on the previous bounding analyses has been evaluated as part of the power uprate license amendment request [Ref. 8] and determined to remain acceptable.

or the two new storage configurations high density (3/4 and high density (all cell gadministrative restriction will be implemented to assure e concrete thermalloads remad

[cceptabgThe refueling procedures will be revised to prevent discharged fuel from being I fplaced in the high density racks in a high density (3/4) or high density (all cell) until 31 days after the reactor is subcritical. This restriction is based on an evaluation scheduled to be complete by June 1999. TU Electric does not believe this process will result in changes to this administrative restriction; however, if changes to this administrative restriction should be  ;

required, TU Electric will expeditiously provide a supplement to this submittal.

i It should be noted that the 31 day restriction does not apply to fuel placed in the high density in a high density (2/4) or high density (1/4) storage configuration.

Avyd h Y LICENSING REPORT 4-1 (February 3,199

Attachment 2 to TXX-99158 Page 1 of 2 NRC Request for Additional Information # 1 i

What is the maximum bulk pool temperature at a full core off-load during a refueling outage? If the temperature exceeds 150' F, provide the following:

l a) Describe the details of the SFP structural analysis including the material properties (i.e., modulus of elasticity, shear modulus, poisson's ratio, yield stress and stalu, ultimate stress and strain, compressive strength) used in the analysis for the reinforced concrete slab and walls and liner plate, welds and anchorages in the analysis.

b) ACI Code 349 limits a concrete temperature up to 150' F for normal operation or any other long term period. Provide technical justifications for exceeding the required temperature of 150* F.

TXU Electric Response The maximum bulk pool temperature at a full core off-load during a normal refueling

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outage is 141" F.

Temperature profiles for the slabs and walls were previously provided by Reference 1 and updated by Enclosure 2 to TXX-99158. The concrete thermal loads were evaluated in accordance with requirements of Section A.4.3 of Appendix A of ACI Code 349 and remain acceptable.

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F-Attachment 2 to TXX-99158 Page 2 of 2 NRC Request for Additional Information # 2 The boron dilution analysis (Enclosure 3 to Reference 2) considered the effect of several pipe lines in the vicinity of the spent fuel pool which were seismically qualified. Are there any other pipe lines in the vicinity of the spent fuel pool which were not seismically qualified?

TXU Electric Response No.

A walkdown was performco to identify all pipe lines in the vicinity of the spent fuel pool.

The pipe lines identified by the walkdown were discussed in the boron dilution analysis (Enclosure 3 to Reference 2).

References

1) TU Electric Letter, logged TXX-95187, from C. L. Terry to the NRC dated July 28,1995, Response to NRC RAI regarding License Amendment Request 94-22, (TAC NOS.

M91244 and M91245)

2) TU Electric Letter, logged TXX-99001, from C. L. Terry to the NRC dated February 11, 1999 (TAC NOS. MA4841 and MA4841)

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ENCLOSURE I TO TXX-99158 i (This page + 2 pages) i i

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