ML20033E300

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Rev 0 to Core Operating Limits Rept for Operating Cycle 9
ML20033E300
Person / Time
Site: Hatch 
Issue date: 02/27/1990
From: Randy Baker
GEORGIA POWER CO.
To:
Shared Package
ML20033E292 List:
References
NUDOCS 9003120219
Download: ML20033E300 (18)


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- Interoffice Core;rdence GeorgiaPower A

I f-I DATE:

February 15, 1990 I,

-RE:

Core Operating Limits Report for Hatch 2 Cycle 9 File: Fuel Cycle Technical XREF: X7GJ13-H800 Log: HP-7

. PROM:

R. D. Baker TO:

ALL UNIT 2 TECHNICAL SPECIFICATIONS HOLDERS By Amendment 106 to-the Unit 2 Technical Specifications, the NRC has authorized relocation of certain fuel related limits out of the Technical Specifications into.an adjunct Core Operating Limits Report. This letter transmits to all Unit 2 Technical Specifications holders a copy of Revision 0

.I of the Core Operating Limits Report for Hatch 2 Cycie 9.

This document should be utilized in conjunction with Amendment 106 of the Unit 2 Technical -

Specifications, if changes to the core operating limits contained in this report are required during the operating cycle, a complete revised document will be issued at that time.

-E If there. are any nuestions regarding this report, please contact me at E

extension 8-821-7367, or telephone number (205)-877-7367.

RDB/

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S. J. Bethay NORMS l

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.l GEORGIA POWER COMPANY EDWIN I. HATCH NUCLEAR PLANT-

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UNIT 2 FUEL CYCLE 9 I

-CORE OPERATING LIMITS REPORT 1

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Prepared by:

SOUTHERN COMPANY SERVICES, INC.

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P.O. BOX 1295 L

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' FEBRUARY. 27, 1990 REVISION 0 l

LB HATCH t CYCLE 9 CORE OPERATING LIMITS REPORT l,

REVI510N 0. EFFECTIVE DATE: FEBRUARY 27, 1990 1.

INTRODUCTION This CORE OPERATING. LIMITS REPORT for Hatch Unit-2 Cycle 9 is prepared in accordance with'the requirements of Hatch Technical Specification 6.9.1.11.

g;

- The core operating limits presented here were developed using NRC-approved

.E methods (References 1 and 2). Results from the reload analyses for the General Electric fuel in Hatch Unit 2 Cycle 9 are documented in References f

3 and 4.

The following cycle-specific core operating limits are included in this

report, a.

Control Rod Program Controls - Rod Block Monitor (Technical Specification 3/4.1.4.3) b.

Average Planar Linear Heat Generation Rate (APLHGR) Limit (Technical Specification 3/4.2.1) c.

Minimum Critical Power Ratio (MCPR) Operating Limit (Technical Specification 3/4.2.3) d.

Linear Heat Generation Rate (LHGR). Limit (Technical Specification-3/4.2.4) 2.

R0D BLOCK MONITOR (TECHNICAL SPECIFICATION 3/4.1.4.3)

Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3/4.1.4.3 and when:

a.

THERMAL POWER is < 90% of RATED THERMAL POWER and the MCPR is less

.g a

than 1.70, or _

1 I

- h' HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT REVI5!0N 0. EFFECTIVE DATE: FEBRUARY 27, 1990 b.

THERMAL POWER is 190% of RATED THERMAL POWER and the MCPR is less than 1.40.

3.

gffit.j,lHIT (TECHNICAL $PECIFICATION 3/4.2.1) l.

The ~AR9GR limit is given by the applicable rated-power, rated-flow limit taken from Figures 3-3 through 3-7, multiplied by the smaller of either:

I a.

The factor given by Figure 3-1, or b.

The factor given by Figure 3-2.

h For the. fuel types whose APLHGR limits are shown in Figures 3-3 through-3-7, the APLHGR limit shown shall be applied to each axial location in the fuel assembly.

4.

MCPR LIMIT (TECHNICAL SPECIFICATION 3/4.2.3)

The MCPR operating limit (OLMCPR) is a function of fuel design, average I.

scram time, core flow, number of operating recirculation loops, and core

power, 4.1 Two Recirculation LooD ODer8 tion For 25% 5 Power < 30%, the OLMCPR is given in Figure 4-1.

For Power 130%,

the OLMCPR is the greater of either:

l a.

The applicable limit determined from Figure 4-2, or I-b.

The appropriate Kp given by Figure 4-1, multiplied by the lh appropriate limit from figure 4-3, where IL I

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L HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT I

REV!510N 0.. EFFECTIVE DATE: FEBRUARY 27, 1990

!I T=

0 or lave - TR-, whichever is greater

,g TA - TB

5 '.

g where:. TA = 1.096 see (Specification 3.1.3.3, scram time 1

5 limit to notch 36)

{

~

~

/2 1

l TB = p + 1.65 H1_

o n

!E INj

,5 i=1.

where: p

=

0.822 see (mean scram time used in the transient-analysis)

.018 sec (standard deviation of y) o

=

n INj Ti ave

  • i"I T

1 I:-

n I

INj i=1 where:

n=

number of surveillance tests performed to date

.)

in the cycle --

Ni= number of active control rods measured in the 1

~

. ith surveillance test i

average scram time to notch 36 of rods in Ti

=

4

_the.ith surveillance test y

?

p',

LI L

HATCN 2 CYCLE 9

[

CORE OPERATING LIMITS REPORT REVISION 0, EFFECTIVE DATE: FEBRUARY 27, 1990 N1= total number of active rods measured in Specification 4.1.3.2.a Note that.T= 1.0 prior to the initial scram time measurements-

, l for the cycle performed in accordance with Specification 4.1.3.2.a, because Tave is assumed equal to TA (Specification'4.2.3.1.a).

4.2 Sincle Recirculation Loon Doeration For single-loop operation, the MCPR operating limit shall be 0.01 greater h

than the two-loop value which is determined as specified in Section 4.1.

5.

LHGR LIMIT (TECHNICAL SPECIFICATION 3/4.2.4)

.The LHGR limit shall be 13.4 kw/ft for all 8x8 fuel. There is no corresponding limit for 9x9 fuel.

6.

REFERENCES 1.

" General Electric Standard Application for Reactor Fuel,"

NEDE-24011-P-A-9 (September.1988).

I 2.

Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of Amendment Nos. 151 and 89 to Facility Operating Licenses DPR-57 I

and NPF-5 -- Edwin I. Hatch Nuclear Plant Units 1 and 2 (TACS 66524/66525)," January 22, 1988.

3.

" Supplemental Reload Licensing Submittal for Edwin I. Hatch Nuclear Plant Unit 2, Reload 8, Cycle 9," GE Document 23A6470, Rev. 0 (November 1989).

lj

.; r

'l HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT REVISION 0. EFFECTIVE DATE: FEBRUARY 17. 1990 f h-Letter, CJP:90-006, " Hatch 2 Cycle 9 Operating Limik. MCPR 4.

Modification,' C. J. Paone to K. S. Folk, January 8,1990.

5.

NEDC-31376P, 'Edwin I. Hatch Nuclear Plant Units 1 and 2

'g SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis,' December IB-1986.

[

6.

Technical Specifications Bhses for Sections 3/4.1.4.3,3/4.2.1, 3/4.2.3, and 3/4.2.4.

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i HATCH 2 CYCLE 9 CORE OPERATING LIMITS REPORT l

4 REV!sION 0. EFFECTIVE DATE: FEBRUARY 17, 1990 MCPR Limit os function of. Averoge. Scrom Tigne 1.32 1.31

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