ML20086C687

Rev 1 to VT Yankee Nuclear Power Station Cycle 15 Core Operating Limits Rept

ML20086C687
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	11/15/1991
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20086C679	List: BVY-91-114, Forwards Rev 1 to VT Yankee Nuclear Power Station Cycle 15 Core Operating Limits Rept ML20086C687
References
NUDOCS 9111250044
Download: ML20086C687 (5)

Text

.. _ _ _ _ _ __

Vermont Yankee Nucient Power Station Cycle 15 Core Operating Limits Report Revision 1 1

October 1991 Reviewed 4 /- 7 M Plano 0perations

/ ///f[7/

Date Review Comittee Approved _t M /%d >' /# !'7/_

h/antManag6f bat.e Approved Sen,I[rVice("1 bdent/ // /(_.!/

6 ate Ope:ations Controlled Copy No.

WPP40/9 n i n wo44 title f'Ir p f-DOCi1 O'!<WQ271 r in<

• i

' REVISIDN_ RECORD i

-Reviaion Dale _Deacription 4

0 9/90 Initial printing. Reviewed by PORC and  :

approved by management.

i 1 11/91 Incorporate new MCPR limite to allow l operation within the exposure window.

Reviewed by P0FC and approved by management.

l I

I i

1 1

f, I

i t

4 e

i.

l WPP40/9-l I

i

-- . . . . -.h.,. - - - - _ _ _ , . -

.__--,-,m,m- - - - _ _ _ , - . . . , _ , . . . , _ - _ . . . + , - _ _ - . . . . .

-,_...m_-,,,-,..- _ - - , ,* ...E-

i type, which evelope the lattice MAP 131CR values employed by the process

! computer. When hand .siculations are required, these MAPLHGR values are used for all lattices in the bundle.

1 2.2 Minimum Critical Power Ratio Limits  ;

During steady-state power operation, the Minimum Critical Power Ratio (MCPR) shall be equal to, or greater than, the limits shown in Table 2.2-1.

The EO)PL exposure in Table 2.2-1 is 9,054 mwd /ST cycle average exposure based on to analysis in Reference 18. This value will be used in the implementation of the exposure-dependent MCPR limits regardless of Une subsequent, more accurate predictions of EOFPL. Justification for this interpretation is the sensitivity study, described in Reference 20. The difference between the licensing analysis EOFPL' and the actual plant EOFPL can affect the validity of the MCPR limits. However, the MCPR limits are valid, l if the actual EOFPL exposure falls within an exposure window defined as 8,192

, to 9,647 mwd /ST. The MCPR limits are also valid during coastdown beyond EOFPL.

For single recirculation loop operation, the MCPR limits at rated flov shall be the values from the Table listed under the heading, " Single Loop Operation." The single locp values are obtained by adding 0.01 to the two ,

loop operation values. For core flows other than the rated enndition, the >

. MCPR limit shall be the appropriate value from Table 2.2-1 multiplied.by Kf where Kg is given in Figure 2.2-1, as a function of the flow control method in use. These limits are only valid for the fuel types in the Present Cycle.

2.3 Maximum Linear Heat Generation Rate Limits During steady-state power operation, the Linear Heat Generation Rate (LHGR) of _any rod in any fuel bundle at any axial location shall not exceed the maximum allowable LHGR limits in Table 2.3-1. There are different LHGR limits for different fuel types. - These limits are only valid for the - fuel -

types in the Present Cycle. The ANFIX bundle-will be monitored as if it were ,

' a BPSDVB311 bundle. Therefore, the limits for the ANFIX bundle are the same f as the BP8DWB311 bundle, i

WPP40/9

.. .- . _ a_. - ;--.- ,...... _,a. . . . _ . . , . , , , . . . - _ - . . - _ _ , . _ _ , _ . . . . - _ _ - _ _ . . - . , - , . - . . - , - . - - - . _ _ _ . , .

, wn e e .

TABLE 2.2-1 ,

MCPR Operating Limits MCPR Operating Limits Value of "N" Two-Loop Single-loop in RBM Average Control Cycle Exposure Range Operation Operation (2)

Equation (1) Rod Scram Time BOC to EOFPL-2 CWD/T 1.34 1.35 42% Equal or better 1.35 EOFPL-2 GWD/T to EOFPL-1 CWD/T 1.34 l than L.C.O. 1.35 EOFPL-1 GWD/T to EOFPL 1.34 3.3 C.I.1 1.35 BOC to EOFPL-2 GWD/T 1.34 Equal or better 1.35 EOFPL-2 GWD/T to EOFPL-1 GWD/T 1.34  !

than L.C.O. 1.35 EOFPL-1 CWD/T to EOFPL 1.34 3.3.C.I.2 1.29 BOC to EOFPL-2 CWD/T 1.28 41% Equal or better 1.29 EOFPL-2 GWD/T to EOFPL-1 CWD/T 1.28 l than L.C.O. 1.28 1.29 3.3 C.l.1 EOFPL-1 GWD/T to EOFPL I.28 1.29 Equal or better BOC to EOFPL-2 GWD/T EOFPL-2 GWD/T to EOFPL-1 CWD/T 1.28 1.29 than L.C.O. 1.31 I EOFPL-1 GWD/T to E01/L 1.30 3.3 C.1.2 1.25 1.26

___(40% Equal or better BOC to EOFPL-2 GWD/T EOFPL-2 GWD/T to EOFPL-1 CWD/T 1.25 1.26 than L.C.O. 1.27 I EOFPL-1 CVD/T to EOFPL 1.26 3.3 C.I.1 1.25 1.26 Equal or better BOC to EOFPL-2 GWD/T EOFPL-2 GWD/T to EOFPL-1 CWD/T 1.25 1.26 than L.C.O. 1.31 EOFPL-1 CWD/T to EOFPL 1.30 l 3.3 C.I.2 Sources: Cycle 15 Core Performance Analysis Report, YAEC-1749. Reference 18. and End-of-Full-Power-Life Sensitivity Study fo,r the Revised BWR Licensing Methodology, YAEC-1822, Reference 20.

Technical Specification

References:

3.6.G.la and 3.11.C.

(1) The Rod Block Monitor (RBM) trip setpoints are determined by the equation shown in Table 3.2.5 of the Technical Specifications.

(2) MCPR Operating Limits are 2ncreased by 0.01 for single loop operation.

_9-WPP60/9

i +

16. Letter, USNRC to VYNPC, SCR, November 30, 1977.

17. Report, Vermqnt_Xankccluclear Power Station Singlglapp_Dperation, NEDO-30060, February 1983.

18. Report, M. A. Sironen, Vermont.lanknLCycic-.U_ Care _EcrioImance Analysin '

Report, YAEC-1749, August 1990.

19. Report , M. E. Gar ret t, K. D. Hartley, and M. B. S. tith, Vermcat._Yankte -

939-IX oualifict. tion _EueL2asen%%faly_Analyelalercr.t, ANF-90-018 May 1990. ,

20. Report, B. Y. Hubbard, et al. , End-of-Full-PoEcI-Liig_S.ensitivity Stt'dv for the_ Rey.11e1LMRlicensint_de.thadology, YAEC-1822, P*tober 1991.

1 P

i e

l l '

l WPP40/9

.-.- -- --. . .