ML20054J715

Application for Amend to License DPR-62,proposing Tech Spec Changes to Correct Odyn Transient Computer Code Used to Perform Cycle 5 Analysis of Pressurization Transients.Tables Re Corrected Min Critical Power Ratio Encl

ML20054J715
Person / Time
Site:	Brunswick
Issue date:	06/24/1982
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20054J716	List: ML20054J715 ML20054J721
References
NUDOCS 8206290486
Download: ML20054J715 (5)

Text

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GP&L Carolina Power & Light Company JUN 2 41982 Office of Nuclear Reactor Regulation 4

ATTN Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 United States Nuclear Regulatory Commission Washington, D.C. 20555 I BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 j DOCKET NO. 50-324 LICENSE NO. DPR-62 RELOAD LICENSING - SUPPLEMENTAL INFORMATION ,

CORRECTION OF ODYN TRANSIENT CODE

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requeste i revisions to Technical Specifications (TS) for the Brunswick Steam Electric Plant (BSEP) Unit No. 2. The attached TS pages supersede comparable TS pages transmitted in our May 20, 1982 submittal. The revisions are necessary to begin Cycle 5 operation. In our May 20, 1982 letter, CP&L stated that General Electric (GE) notified us of an error existing in the current version of the ODYN transient computer code used to perform the BSEP Unit No. 2, Cycle 5, analysis of pressurization transients.

3 This letter is to summarize the error and transmit corrected TS pages to you.

DISCUSSION Carolina Power & Light Company has been notified by GE that an error in programming the axial power distribution calculation occurred accounting for the difference in ACPR values addressed in our May 20, 1982 submittal.

General Electric has also indicated the REDY-analyzed transients are not 4 affected by the ODYN error.

Our May 20, 1982 submittal had incorporated GE's preliminary, yet conservative ACPR correction factors as referenced in the May 6,1982 GE letter. Although the magnitude of error and the resultant impact on ACPR was small, GE reanalyzed ODYN limiting transients with and without recirculation pump trip (RPT) for BSEP Unit No. 2 (Cycle 5) operation. These final, 4 corrected Minimum Critical Power Ratio (MCPR) operating limits specifically for BSEP Unit No. 2 are summarized in the enclosed Tables 1 and 2.

Additionally, CP&L has attached revised TS pages incorporating these BSEP Unit 7

No. 2 specific corrected operating limits resulting from GE's ODYN reanalysis.

1 s206290486 B20624 gf PDR ADOCK 05000324 PDR p

i 411 Fayetteville Street

• P. O. Box 1551

• Raleigh. N C. 27602

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e ADMINISTRATIVE Brunswick Unit No. 2 is presently scheduled for initial criticality on July 10, 1982. We request the Staff review be conducted te allow return to power in accordance with this schedule. We will keep your staff apprised of any changes to the schedule.

In cur May 20, 1982 submittal, CP&L remitted a $4,000 check for a Class III amendment fee; therefore, no additional fees are required.

Should you have any questions regarding this submittal or Attachments, please contact our staff.

Yours very truly, C3.u. 1 P. W. Howe Vice President Technical Services MSG /cr (109C5T2)

Enclosures cc: Messrs: J. P. O'Reilly (NRC-RII)

J. A. Van Vliet (NRC)

P. W. Howe, having been first duly sworn, did depose and say that the information contained herein is true and correct to his own personal knowledge or based upon information and belief.

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Table 1 BRUNSWICK 2 RELOAD 4 (CYCLE 5) - WITH RPT REVISED ODYN ANALYSES (Original / Revised) 717 Br8 8x8R P8x8R GETAB Radial Peaking Factor 1 33/1.32 1.44/1.43 1.58/1.57 1.56/1 56 GETAB Bundle Power (MWt) 5.672/5.646 6.152/6.114 6.723/6.689 6.658/6.620 GETAB Bundle Flow (1000 lb/hr) 122.1/122.3 110 5/110 7 111.0/111.2 112.1/112.4 GETAB Initial MCPR 1.15/1.15 1.19/1.20 1.20/1.20 1.21/1.22 Peak Neutron Flux, TT w/o BP (5 NBR) 330/350 330/350 330/350 330/350 Peak Heat Flux, TT w/o BP (5 NBR) 116/117 116/117 116/117 116/117 ACPR Uncorrected, TT w/o BP 0.08/0.09 0.12/0.13 0.13/0.13 0.14/0.15 MCPR Option A, TT w/o BP 1.20/1.21 1.24/1.25 1.25/1.25 1.26/1.27 MCPR Option B, TT w/o BP 1.12/1.13 1.16/1.17 1.17/1.17 1.18/1.19 Peak Neutron Flux, FWCF (5 NBR) 113/113 113/113 113/113 113/113 Peak Heat Flux, FWCF (% NBR) 109/109 109/109 109/109 109/109 ACPR Uncorrected, FWCF 0.03/0.04 0.04/0.05 0.04/0.05 0.05/0.05 MCPR Option A, FWCF 1.15/1.16 1.16/1.17 1.16/1.17 1.17/1.17 MCPR Option B, FWCF 1.12/1.13 1.13/1.14 1.13/1.14 1.14/1.14

1 Table 2 BRUNSWICK 2 RELOAD 4 (CYCLE 5) - WITHOUT RPT REVISED ODYN ANALYSES i EOC - 2,000 mwd /ST (Original / Revised)

I

717 818 8x8R P8x8R GETAB Radial Peaking Factor '1 36/1 35 1.46/1.45 1.60/1.59 1.58/1.57 GETAB Bundle Power (MWt) 5.819/5.740 6.239/6.187 6.815/6.757 6.741/6.664 GETAB Bundle Flow (1000 lb/hr) 121.2/121.7 109.9/110.2 110.5/110.8 111.7/112.1 GETAB Initial MCPR 1.12/1.13 1.17/1.18 1.18/1.19 1.19/1.21 Peak Neutron Flux, LR w/o BP ($ NBR) 436/447 436/447 436/447 436/447 Peak Heat Flux, LR w/o BP ($ NBR) 117/117 117/117 117/117 117/117 ACPR Uncorrected, LR w/o BP 0.05/0.06 0.10/0.11 0.11/0.12 0.12/0.14 HCPR Option A, LR w/o BP 1.17/1.18 1.22/1.23 1.23/1.24 1.24/1.26 HCPR Option B, LR w/o BP <1.08/<1.08 <1.08/<1.08 <1.08/<1.08 <1.08/<1.08 Peak Neutron Flux, FWCF (5 NBR) 114/113 114/113 114/113 114/113

Peak Heat Flux, FWCF ($ NBR) 109/109 109/109 109/109 109/109 ACPR Uncorrected, FWCF 0.03/0.04 0.04/0.04 0.04/0.05 0.04/0.05 HCPR Option A, FWCF 1.15/1.16 1.16/1.16 1.16/1.17 1.16/1.17 HCPR Option B, FWCF 1.09/1.10 1.10/1.10 1.10/1.11 1.10/1.11 i

a

Table 2 (continued)

BRUNSWICK 2 RELOAD 4 (CYCLE 5) - WITHOUT RPT ]

REVISED ODYN ANALYSES EOC (Original / Revised) l l

Tr7 818 8x8R P8x8R l

GETAB Radial Peaking Factor 1.25/1.24 1 35/1 33 1.47/1.46 1.44/1.43 GETAB Bundle Power (HWt) 5.344/5.309 5.744/5.686 6.267/6.210 6.144/6.092 GETAB Bundle Flow (1000 lb/hr) 124.3/124.5 113.1/113.5 113.7/114.1 115.2/115.6 GETAB Initial MCPR 1.23/1.23 1.28/1.29 1.29/1 30 1.32/1.33 Peak Neutron Flux, LR w/o BP (5 NBR) 553/582 553/582 553/582 553/582 Peak Heat Flux, LR w/o BP (5 NBR) 127/128 127/128 127/128 127/128 CPR Uncorrected, LR w/o BP 0.15/0.16 0.21/0.22 0.22/0.23 0.25/0.26 NCPR Option A, LR w/o BP 1.27/1.28 1.34/1.35 1.35/1.36 1.38/1.39 HCPR Option B, LR w/o BP 1.17/1.18 1.22/1.23 1.23/1.24 1.26/1.27 Peak Neutron Flux, FWCF (5 NBR) 122/127 122/127 122/127 122/127 Peak Heat Flux, FWCF (5 NBR) 109/110 109/110 109/110 109/110 CPR Uncorrected, FWCF 0.03/0.03 0.04/0.04 0.04/0.04 0.05/0.05 HCPR Option A, FWCF 1.15/1.15 1.16/1.16 1.16/1.16 1.17/1.17 HCPR Option B, FWCF 1.09/1.09 1.10/1.10 1.10/1.10 1.11/1.11

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