ML18019A827

Forwards Results of Large Break LOCA Analysis & Radial Peaking Factor Limit Rept for Facility,Including Revised FSAR & Tech Spec Pages.Analyses Should Close Out Sser 3 Confirmatory Issue 9

ML18019A827
Person / Time
Site:	Harris
Issue date:	05/22/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Berlinger C, Harold Denton Office of Nuclear Reactor Regulation
References
NLS-86-167, NUDOCS 8605280149
Download: ML18019A827 (4)

Text

REGULATORY INFORNATIQN DISTRIBUTION SYSTEN (RIDS)

ACCESS IQN NBR: 8605280149 DOC. DATE: 86/05/22 'OTARIZED: NO DOCNET 0 FACIL: 50-400 Shearon Harris Nuclear Power Plant Unit 1 Carolina 05000400 AUTH. NANE -

AUTHOR AFFILIATION Zll'1NERNANi S. R. Carolina Power Zc Light Co.

RECIP. NANE RECIPIENT AFFILIATION DENTQN> H. R. OFFice of Nuclear Reactor Regulation> Director (post 851125 BERLIN('ERi C. Reactor Systems Branch (PWR-A)

SUBJECT:

Forwards results of- large break LOCA analysis Zc radial peaking %actor limit rept for facilitgi including revised FSAR ic Tech Spec pages. Analyses should close out SSER 3.

ConFirmatorg Issue 9.

DISTRIBUTION CODE: 8001D TITLE: Licensing COPIES RECEIVED: LTR Submittal: PSAR/FSAR Amdts 8f JRelated ENCL JCorrespondence SIZE:

NOTES: Application for permit renewal Wiled. 05000400 I

REC IP ENT COPIES RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAI'1E LTTR ENCL PWR-A ADTS 1 PWR-* EB 1 1 PWR-A EICSB 2 2 PWR-A FQB 1 PWR-A PD2 LA 1 1 PWR-A PD2 PD 1 1 BUCVLEY, B 01 2 2 PWR-A PSB i.

PWR-A RSB 1 1 INTERNAL: ADN/LFNB 1 0 ELD/HDS1 0 IE FILE IE/DEPER/EPB 36 1 1 IE/DGAUT/GAB 21 NRR BWR ADTS 1 0 NRR PWR-A ADTS 0 NRR PWR-B ADTS 1 0 NRR ROE N L 1 NRR/DHFT/HFIB 1 1 NRR/DHFT/NTB F 04 1 RGN2 3 3 R / A I/NIB 0 EXTERNAL 24X 1 1 BNL(ANDTS ONLY) 1 DNB/DSS (ANDTS) 1 LPDR 03 1 NRC PDR 02 1 NSIC 05 1 PNL CRUEL,R i.

TOTAL NU))BER OF COPIES REQUIRED: LTTR 34 ENCL 28

'U "I h hi h h I h'

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CKK Carolina Power 8 Light Company SERIAL: NLS-86-167 MAY 2 2 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attention: Mr. Carl Berlinger, Chief Reactor System Branch Division of PWR - Licensing A United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 DOCKET NO.50-000 LARGE BREAK LOCA AND RADIAL PEAKING FACTOR LIMITREPORT

REFERENCE:

Letter dated November 7, 1980, from Mr. S. R. Zimmerman (CP&L) to Mr. H. R. Denton (NRC)

Dear Mr. Denton:

Carolina Power R Light Company (CPRL) hereby submits the results of the Large Break LOCA analysis and the Radial Peaking Factor Limit Report for the Shearon Harris Nuclear Power Plant (SHNPP), Unit 1, Cycle 1. Carolina Power R Light Company submits the revised FSAR and Technical Specification pages and seeks to disposition the need for the APDMS as discussed in Confirmatory Issue 9 (SER Section 0.3.2) and Reference 1. The SHNPP ECCS Large Break LOCA has been reanalyzed using the 1981 Evaluation Model and BART. The result of this analysis was an allowable Peaking Factor of 2.28. The increase in Peaking Factor from the 2.11 value, obtained using the 1978 ECCS Evaluation Model, is consistent with the values obtained for other plants by using BART. The Nuclear Design Peaking Factor in Section 0.3 of the FSAR has been reduced from the generic 2.32 value to 2.28 by performing additional SHNPP specific calculations.

The SHNPP ECCS Large Break LOCA analysis was performed for a power level of 2775 MWt with F H of 1.55. The analysis utilized initial fuel conditions generated by the Revised Pad Thermal Safety Model (WCAP-8720, Addendum 2). Pertinent analysis assumptions include: a 6 percent steam generator tube plugging level, 17x17 standard fuel, and an accumulator water volume of 1050 ft per tank. The analysis was performed with a modified version of the 1981 Westinghouse ECCS Evaluation Model as described in WCAP-9220-P-A, Revision 1 (Proprietary). This version includes the BART computer code, documented in WCAP-9567 (Proprietary).

The break sizes analyzed in the study were the CD OA, 0.6, and 0.8 DECLG. The worst break size is the CD 0.0 which resulted in a peak clad temperature of 2168'F at a total peaking factor of 2.28. This analysis result demonstrates conformance with 10 CFR 50.06 requirements for the SHNPP ECCS Large Break LOCA analysis.

'ille Street o P. O. Box 1551 o Raleigh, N. C. 27602 8b05280149 Bb0522 PDR ADOCK 05000400 E PDR

(Mr. H. R. Denton NLS-86-167 / Page 2 The SHNPP design employs an improved load follow package which was developed by Westinghouse to improve the return to power capability of Westinghouse PWRs during operation.. The operation and safety analysis aspects of an improved load follow package which employs a widened hl band, such as (+3, -1296), are discussed in a Westinghouse letter from T. A. Anderson (Nuclear Safety) to K. Kniel (NRC), Letter No. TMA-80-2198 dated 3anuary 31, 1980. Due to less BOL margin existing in F~ for an initial core, the width of the hl band is typically limited to + 5 percent for the first 20 percent (3000 MWD/MTU)of Cycle 1. For SHNPP Unit 1 Cycle 1, this AI restriction (+ 596) will be extended out to 6000 MWD/MTU to provide additional margin in F~ during early Cycle 1 operation.

In Supplement No. 3 of the SHNPP SER, Confirmatory Issue 9 was resolved via the CPRL commitment to use the Excore APDMS. This commitment was based on the original SHNPP analysis which justified a LOCA Peaking Factor of 2.32. Since the attached analyses justify a value of 2.28 for both the LOCA and Nuclear Design Peaking Factors, utilization of the Excore APDMS, or an alternate system, to achieve 100 percent power is no longer necessary. Therefore, the attached analyses close out Confirmatory Issue 9 without requiring the use of the Excore APDMS.

Attachment 1 contains the revised FSAR pages pertaining to the aforementioned LOCA and Peaking Factor analyses. These revised pages will be formally incorporated into the FSAR in a future amendment. Attachment 2 contains the revised Technical Spegyation pages. Attachment 3 providqs the F y limits for Rated Thermal Power

) and the plot of the predicted (F via the Radial (FXV P rell . vs. Axial Core Height

~

o Peaking Factor Limit Report as required ny TecrInical Specification (TS)

Section 6.9.1.6. Copies of this letter with the attachments are being provided to the NRC Regional Administrator to fulfillthe TS requirements.

If you have any questions, please contact me at (919) 836-6202.

Yours very truly,

~

S..

~ ~ Zimm rman er Nuclear Licensing Section SRZ/GB/crs (3890OSU)

Attachments CC: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. 3ohn D. Runkle Dr. J. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Dr. 3. H. Carpenter (ASLB)

Wake County Public Library Mr. J. L. Kelley (ASLB)

Mr. M. Dunenfeld (NRC-RSB)