ML20042E911

Forwards Rev 1 to Nonproprietary & Proprietary, Steam Generator Tube Rupture Analysis for Byron & Braidwood Plants.

ML20042E911
Person / Time
Site:	Byron, Braidwood
Issue date:	04/25/1990
From:	Schuster T COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML19302E086	List: ML20042E911 ML20042E912 ML20042E913
References
NUDOCS 9005040085
Download: ML20042E911 (8)

Text

'

Common';;ealth Edison fD. )i 1400 DownersOpus Place Grove, Illinois 60515 s

April 25, 1990 Dr. Thomas E. Murley Office of Nuclear Reactor Regulation U.S. Nuclear Reguintory Commission Washington, DC 20555 Attention: Document Control Desk

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Steam Generator Tube Rupture Analysis HRC_1?osket Nos. 50-454/455 and 50-456/452

Reference:

(a) March 30, 1987, letter from C.E. Rossi to A.E. Ladieu (b) September 1,1988, letter f rom R.A. Chrzanowski to T.E. Murley (c) October 21, 1988, letter from R.A. Chrzanowski to T.E. Murley

Dear Mr. Murley:

In response to reference (a), a Steam Generator Tube Rupture Analysis was submitted for Byron /Braidwood Stations,see references (b) and (c).

Subsequent to these submittals, Commonwealth Edison Nuclear Fuel Services identified an error due to transposition of two digits of a flow area number.

The error necessitated a reanalysis from which it is concluded that the Byron /Braidwood plants are still in compliance with the licensing requirements established by the NRC for the mitigation of a Steam Generator Tube Rupture Event. Attachment 1 providos both a summary of the report's Revision 1 changes and an itemized list of input changes.

Attachment 2 contains the proprietary version of the " Steam Generator Tube Rupture Analysis for the Byron and Braidwood Plants, Revision 1".

Attachment 3 contains the non-proprietary version of the same analysis.

Attachment 4 contains a Westinghouse Application for withholding (letter CAW-90-018), Proprietary Information Notice and a signed Af fidavit.

Since the proprietary version of " Steam Generator Tube Rupture Analysis for Byron and Braidwood Plants" contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity, the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

/ft 9005040085 900425 PDR P

ADOCK 05000454 PDC

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.is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse affidavit should reference CAW-90-018 and should be addressed to R.A. Wiesemann, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355.

Please direct any questions regarding this matter to this office.

Very truly yours, k&lf5 .

T.K. Schuster Nuclear LicenairJg Administrator Enclosed are: 1. 5 copies of " Steam Generator Tube Rupture Analysis for Byron and Braidwood Plants", Rev. 1 (Proprietary).

2. 5 copies of " Steam Generator Tube Rupture Analysis for Byron and Braidwood Plants", Rev. 1 (Non-proprietary).

Attachments: (1) Summary and Itemized list of SGTR, Revision 1 Changes (3 pages). .

(2) Proprietary " Steam Generator Tube Rupture Analysis for Byron and Braidwood Plants, Revision 1."

(3) Non-Proprietary " Steam Generator Tube Rupture Analysis for Byron and Braidwood plants, Revision 1".

(4) Westinghouse Application for Withholding.

cc: Byron Resident Inspector (w/o reports)

Braidwood Resident Inspector (w/o reports)

P.C. Shemanski - NRR (4 copies of each version)

S. Sands - NRR (w/o reports)

NRC Region III Office (w/o reports) 0929T l

l J

Attachment 1 Summary of SGTR, Revision 1 changes:

There are five categories of changes made to the B/B SGTR, Revision 1 report.

Page numbers affected refer to the proprietary version of the report. Those categories were:

A. Correction of an error in the input values for the ruptured tube junction flow area was performed. It was necessary to correct the inadvertent use of areas with transposed digits in the ruptured tube flow calculational model. This was the primary reason for the issuance of 'he B/B SCTR, Rev. I report. See item'1. (Pages affected: A-12, A-15).

B. Changes were made to reflect more accurate input information available which was incorporated into the RETRAN model which could i potentially impact the results of either the offsite dose case- 1 and/or the margin to overfill case. See items 2-13. (Pages affected:

vi, 3-2, 3-3, 3-5, 3-6, 3-7, 3-8, A-3, A-4, A-6, A-9 through A-16) i C. Changes were made to be consistent with all of the WCAP-10698-P-A methodology for conservative directions for input assumptions where they were specified. Results of Commonwealth Edison's SGTR ,

sensitivity studies were used to determine conservative directions  !

for assumptions not specified in WCAP-10698-P-A. See items 14-20.  !

(Pages affected: 2-6, 3-2, 3-3, 3-7, 3-8, A-6)

D. Changes were made so that radionuclide activity released as the- i

, result of an SGTR could be calculated within the RETRAN model j l itself. (Pages affected: vi, vil, 6-2, C-1 though C-19) g 1 i' E. Changes in the B/B SGTR, Rev._1-report text and format were performed to assure consistency with items A,- B, C, and D listed i above. (Pages affected: iv, v, vi, vii, 2-3, 2-4, 2-5, 2-6, 2-8, 3-1, 3-3, 4-1 through 4-30, 6-2, A-1, A-2, A-9 through A-15. )

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s Itemized list of SGTR, Revision 1 input changes:

1. Correction of the single ruptured tube break flow area was implemented. Transposition of two digits in a junction flow area was  :

the error which necessitated Rev. 1. reanalysis. The corrected area

• for a single ruptured tube was 0.002405 square feet. (Pages affected: A-12, A-15).

2. Improved S/G tube bundle nodalization in tubesheet region.

(Pages affected: A-9, A-10, A-13). i

~

3. Improved accuracy in tube bundle heat transfer input parameters.

(Changes did not affect-text of report, only the results).

4. Initial S/G secondary mass reduced to reflect improved accuracy in determining the maximum mass at 60% power consistent with NCAP-10698-P-A. The new mass used was 120,200 lbm per S/G from the LOFTRAN basedeck for the MTO case and an initial mass of 78,570 lbm for the 00 case from FSAR data. Total S/G volumes were reduced also to reflect values typically used in the Hestinghouse B/B LOFTRAN '

basedeck. New secondary volumes were 5949.0 cubic feet per S/G, (Pages affected: 3-5, 3-7, A-9, A-13).

5. Improved accuracy for the S/G PORV flow capacity was modeled. The p valves were found to have maximum design flow capacity well-in excess of the nominal FSAR capacity which was used in the original SGTR analysis. Limitations of maximum stroke' time were also imposed on-the S/G PORV model. The maximum S/G PORV flow rate was changed to 133.889 lbm/second per valve with a. stroke time of 20.0 seconds to open or close the valve. (Pages affected: 3-6, 3-8, A-4, A-12, A-15).

6. Auxillary feedwater flow was increased to account for small _ .

variations in pumping capacity and for uncertainties in'the test data itself. The new AFH flow used in Rev. 1:was 375 GPM (OD) and 464:GPM (MTO) per S/G. (Pages affected:.3-6, 3-8).

7. Initial RCS mass flowrates were reduced to reflect full T-Hot reduction. The previous _ analysis was done using-Improved Thermal Design flow at nominal-temperature conditions. .

Revision I corrects both cases for Standard Thermal Design flow with full T-Hot reduction. The new RCS flow rate used'for Revision I was 10,013.8889 lbm/sec per loop. These values were based on HCAP-11388.

(Pages affected: 3-2, 3-5, 3-7, A-11, A-12, A-14, A-15).

8. Core power was reduced from 3425 to 3411.0 MHt since the other 14 MHt is generated by the RCP's in the loops for a total rated power of 3425 0 MHt. (Page affected: 3-7).

9. Core volumes were reduced'to 215.4413 cu ft for improved accuracy in i calculating the flow area. Previously,. flow:was allowed between the control rod and its guide tube, but this was removed since core flow does not proceed through there. The specified flow area and

• hydraulic diameter were adjusted accordingly. Bypass flow was changed from downflow to upflow. (Pages affected: A-3, A-9, A-11, A-13, A-14).

ID:ZBXL:48:6

Itemized list of SGTR R; vision 1 input changes:- 1

10. Reactor trip and SI initiation-setpoints were evaluated and were' i changed to account for uncertaintles. Previously, a' larger pressure 1 uncertainty was unnecessarily used. The revision 1 M10 case setpoints were 1929.7-psia and 1873.7 psia respectively,.and OD case setpoints were both 1859.7. Initial pressure for the OD case was raised to 2280 psia. (Page affected: 3-5, 3-6, 3-8).

l 1

11. Noda11zation of the vessel internals was updated to model bypass flow' around the core using Hestinghouse assumptions typically used in the B/B LOFTRAN model. (Pages affected: vi, A-9, A-11, A-13, A-14, A-16),

12. The core exit thermocouple model was updated to be more accurate by using the core exit junction fluid properties rather than the upper plenum fluid properties. (Changes did not affect text of report, only the results).

13. The ECCS model was further refined to include more data points and conservatively _model flow capacities. The HTO case utilized actual pump flow with 5% conservatism and the 00 case utt11 zed the Tech Spec minimum pump flow with 20% conservatism with average piping losses '

for both SI models. (Pages affected: 3-6, 3-8). ' ,

14. Initial secondary mass flowrates were reduced also.for full T-Hot reduction. The previous analysis was done using nominal -secondary . .

flow at nominal (00) and reduced-(MTO) T-Hot conditions. Revision I corrects the MT0 case secondary flows which were slightly lower than nominal T-Hot conditions and utilized the same full T-Hot conditions for the OD case. The new secondary flow rate used:for, Revision 1 was 1,043.75 lbm/sec per steam generator. These values'were based on.

HCAP-11388. (Pages affected: 3-2, 3-3, 3-5, 3-6, 3-7, A-6, A-11, A-12, A-14, A-15),

15. Control systems and volumes were initialized to" reflect full T-Hot l- reduction. These values were based on HCAP-11388.- (Pages affected:

l 3-2, 3-3, A-6, A-9, A-10, A-13).

l

16. Pressurizer initial level was changed to be consistent with Hestinghouse methodology specified in NCAP-10698-P-A. Initial level was raised from 60% span to 65% span to include allowance for instrumentation errors. (Pages affected: 3- 2, 3-3, A-6) .

, 17. Decay heat was changed to 1.2x ANS for both ' cases per HCAP-10698.

l (Pages affected: 3-2, 3-3, 3-8, A-6).

1 L 18. Operator action time for termination of SI flow after depressurization was reduced from 3.0 minutes to 1.0 minutes based upon HCAP-10698 methods and simulator demonstrations.

(Pages affected: v, 2-6, 2-9).

19. Ruptured S/G PORV lift and full open setpoints were reduced based

, upon HCAP-10698 methods. (Pages affected: 3-2, 3-3, 3-6, 3-8, A-4, A-6).

20. AFH flow temperature entering the S/G was raised from 42 F to 120 F based upon HCAP-10698 methods for the MT0 case only.

(Pages affected: v, 3-2, 3-3, 3-8, A-6).

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