ML19263C287

Forwards Addl Info Re Proposed Tech Spec Change to Allowable Valves of Unit 1 Reactor Core Radial Peaking Factor (Fxy)

ML19263C287
Person / Time
Site:	Beaver Valley
Issue date:	02/08/1979
From:	Dunn C DUQUESNE LIGHT CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
TAC-10837, NUDOCS 7902130195
Download: ML19263C287 (5)

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22N r h, Pennsylvania February 8,1979 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attention: A. Schwencer, Chief Operating Reactors, Branch No. 1 Division of Operating Reactors Washington, D. C. 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-3.%

Additional Information on July 6, 1978 Technical Sp cification Change Request Gentlemen:

Enclosed are three (3) signed originals and thirty-seven (37) copies of additional information concerning the Proposed Technical Specification change to the allowable values of the Beaver Valley No. 1 Unit Reactor Core Radial Peaking Factor (Fq) .

This additional information consists of the Final Acceptance Criteria envelopes which are obtained by utilizing the proposed allowable values of Fg. These curves were obtained using the three analysis method with the appropriate 1.03 multiplier as described in the referenced WCAP.

These curves have been prepared for the balance.of Cycle 1 and for Cycle 2. A brief description of the calculational techniques used to generate these curves is also attached. .

If you have any further questions on.this matter, please contact my office.

Very truly yours, C. N. Dunn Vice President, Operations Attachments 7902130196

(CORPORATE SEAL)

Attest:

f O Q H.W. Staas Secretary COMMONWEALTH OF PENNSYLVANIA)

) SS:

COUNTY OF ALLEGIENY )

On this 7 day of [E.R 4 ss 4 / , 1979, before me, DONATT) W RTTammu , a Notary Public in and for said Common-wealth and County, personally appeared C. N. Dunn, who being duly sworn, deposed, and said that (1) he is Vice President of Duquesne Vght, (2) he is duly authorized to execute and file the foregoing abmittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.

/ n2M QE ,-.~.-w DONALD W. SHANNON, Notary Pubk Pittsburgh, e'legheny Co., Pa, My Commission Empires June 7,1979

FIGURE 1 T

E1ximum (F *P Q Re,1) versus Axial Core Hei;;ht During Normal Operation - Cycle 2

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FMURE 2 Maxi =um (Fq T,p Rel) versus Axial Core Height During Nor=al Operation -- for Re:aining Cycle 1 Operation (currently at 11700 13iD/MTU) r ---- .- - . r _ __

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ATTACHMENT RESPONSE TO NRC REQUEST RELATING TO Fg (Z) TECH SPEC REVISION The elevation dependent peaking factor F (2) is the prinary. power distribution 0

parameter limited in the technical spectrication for LOCA protection. Both radial and axial power distributions determine the peaking factor. Discussion of the methods used to calculate F (z) is provided in Reference 1.

q The radial power distributions are relatively fixed and may be bounded by upper limits while axial power distributions are controlled by well defined procedures as outlined in the Technical Specifications. A. component of F (z) is represented 0

by the radial peaking factor Fy(z), which is defined as the rdtio of peak power density to average power densiry in the. horizontal plane at elevation Z. For Cycle 1 with all fresh fuel at the beginning of life FXY(z) exhibits a monotonically varying function reflecting primarily a height dependent density feedback variation.

In the reload core FXY(z) reflects a composite of burned and fresh fuel axial power shapes. In the Central portion of the core, axially, FXY(z) is located in the fresh fuel region and at beginning of life is calculated to be higher than in Cycle 1, resulting in the proposed Technical Specification change on Page 3/4 2-7. The reload core, however, exhibits flatter axial shapes thus resulting in F q(z) still being within allowable limits. F T x relative power was calculated as a function ofheightbyimposingvariousloakfollowtransientsonthereactorthroughinsertion and removal of Banks D and C considering the effects of the accompanying variation in axial xenon and power distributions as discussed in Reference 1. Beginning and end of cycle conditions were included in the calculations and different histories of operation,were assumed prior to calculating the effects of load follow transients on the axial power distribution. The.se different histories assumed base load operation and ' extensive load following without use of part length rods. Results of these calculations are shown for Cycle 2 on Figure 1 where the maximum values of F T.p are plotted versus elevation in the core. InallcasesthecalculatedvaluehareRel maintained below the nuclear design operating envelope 2.32 x K(z) where K(z) is the normalized Fq(z) function shown on Figure 3.2-2 of the Technical Specifi-cations. Similar calculations were done for end of Cycle 1 with the proposed revisien to the Technical Specification and the operating envelope was satisfied.

The results are shown in Figure 2 The Fq(z) limit envelope is verified for each reload.  ;

1. T. Morita, L. R. Scherpereel, K. J. Dzikowski, R. E. Radcliffe, and D. M. Lucoff,

, "Pewer Distribution Control and Load Following Procedures," WCAP-8385 (Westinghouse Proprie.tary) and WCAP-8403 (Non-Proprietary), September 1974.

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