ML20135D488

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Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14
ML20135D488
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 12/03/1996
From:
GEORGIA POWER CO.
To:
Shared Package
ML20135D481 List:
References
NUDOCS 9612090396
Download: ML20135D488 (9)
v • d • e


Text

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. Enclosure 3 i

Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Safety Limit Minimum Critical Power Ratios (SLMCPRs)

Page Change Instructions Cycle 13 Unit 2 Insert R_eplace 2.0-1 2.0-1 I

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i l 9612090396 961203 l PDR ADOCK 05000366 P PDR HL-5270 E3-1 i

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow a 10% rated core flow:

MCPR shall be a 1.08 for two recirculation loop operation or 21.09 for single recirculation loop operation.

l 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig.

! 2.2 SL Violations With any SL violatf on, the following actions shall be completed:

2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: i 2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

l 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive l responsible for overall plant nuclear safety, and the offsite j review committee.

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(continued)

HATCH UNIT 2 2.0-1 96-35A-11/18/96  !

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core Sts 2.1.1.1 With the reactor steam dome pressure < 785 psig or core .

flow < 10% rated core flow: l THERMAL POWER shall be s;25% RTP.

2.1.1.2 With the reactor steam dome pressure 2: 785 psig and core flow:  ;

flow 2: 10% rate i.08 MCPR hal be W. or two recirculation loop operation /

or F:07 or s4 recirculation loop operation. i I,09 \

2.1.1.3 Reac vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant Syst'em (RCS) Pressure SL l Reactor steam dome pressure shall be s; 1325 psig.

2.2 SL Violations {

With any SL violation, the following actions shall be completed:  ;

2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.  :

c 2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: 1 2.2.2.1 Restore compliance with all SLs; and  ;

l 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive l

responsible for overall plant nuclear safety, and the offsite l r

review committee.

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. (continued) l 2.0-1 ^: nd; at Nor-135-HATCH UNIT 2 i

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  • . . Endosure 4

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Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

J Safety Limit Minimum Critical Power Ratios (SLMCPRs) j l l Pan _e Channe Instructions Cycle 14 i

l Insert Replace  !

i 2.0-1 2.0-1 l f

f

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1 HL-5270 E4-1

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs l

2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core

, flow < 10% rated core flow:

l THERMAL POWER shall be s 25% RTP.  :

l 2.1.1.2 With the reactor steam dome pressure a: 785 psig and core i

flow 2: 10% rated core flow:

MCPR shall be a: 1.12 for two recirculation 1 cop operation or 2: 1.14 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig.

,2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods, 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.

l (continued) l HATCH UNIT 2 2.0-1 96-35B-11/18/96

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t .

a. .

SLs  ;

2.0 l l l 2.0 SAFETY LIMITS (SLs) ,

2.1 SLs 1 2.1.1 Reactor Core SLs ,

l 2.1.1.1 With the reactor steam dome pressure < 785 psig or core l flow < 10% rated core flow THERMAL POWER shall be 5: 25% RTP.

2.1.1.2 With the reactor steaia dome pressure 2 785 psig and core i flow a 10% rate eg flow-l 1.12 ,

l MCPR ha be 4:96 or two recirculation loop operation i or . or s' e recirculation loop operation.

Ialf 2.1.1.3 Rea essel water level shall be greater than the top  !

of active irradiated fuel.

2.1.2 Reactor Coolant System (RCS) Pressure SL  !

Reactor steam dome pressure shall be s; 1325 psig.  ;

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.  ;

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and i

, 2.2.2.2 Insert all insertable control rods.

1 i

2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite 4

review committee. ,

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(continued) i HATCH UNIT 2 2.0-1 ^ mend cat No.135-

ENCLOSURES GENERAL ELECTRIC NUCLEAR ENERGY l LETTERS REK:96-171 AND REK:96-382 P

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s. , , GE Nuclear Energy j RochardE Kmgston %cerfum amecn I Se9tCI fut! PtC;ect P/pager Gene'd![ig;* tic C:.trcer gh(,] *b &g& y PO Scn 780 UC 433 'wmme niC284010180 i l

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May 8,1996 F )' A f5'0 675 6192 3.'Sk 910 615 5684

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l REK:96-171

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5 gg 9Q P u cc: G. K. McElroy R. G. Cocherell 5 M G! E. B. Gibson

$. M 8 W. E. Grimme S, ~gf B. E. Hunt

' % __ tso T. C. Kanellopoulos W. R. Mertz W. R. Sutton Mr. K. S. Folk, Manager BWR Core Analysis Southem Nuclear Operating Company P. O. Box 1295 Birmingham, AL 35201

Subject:

Verified Safety Limit MCPR Calculation Results for Hatch 1 Cycle 17 and Hatch 2 Cyde 13

Reference:

Letter, REK:96-156, " Unverified Values for Safety Limit MCPR for Hatch 1 Cycle 17 and Hatch 2 Cycle 13", dated 5/2/96

Dear Mr. Folk:

GE has completed the analysis and verification of the Safety Limit MCPR for Hatch 1 cycle 17 and Hatch 2 cycle 13. We evaluated the expected SLMCPR at Beginning of Cycle, Peak Hot Excess, and End of Cycle using approximate methods. Based on this screening we calculated the SLMCPR using our detailed Monte Carlo methodology for the limiting exposure points.

For Hatch 1 cycle 17, our calculations show that the !imiting SLMCPR is 1.06. The Tech Spec value of 1.07 is not exceeded, and thus, there is no impact on the plant.

For Hatch 2 cycle 13, the maximum value for the SLMCPR is 1.08. Based on the Tech Spec value of 1.06, the impact on Hatch 2 is 0.02.

In accordance with the verbal agreement with the NRC, you should modify the MCPR limits in your core monitoring system databank to reflect an increase in your MCPR operating limit of 0.02 in lieu of your current administrative limit. Also, for the interim, -

l the MCPRf curve for your plant should be adjusted upward by multiplying by the ratio  ;

1.08/1.06 and rounded to the nearest 0.01. The off-rated MCPRp curve for your plant I should be recalculated as MCPRp(new) = SLMCPR(new) + DCPRp, defined as, l DCPRp = SLMCPR(new)*(DIMCPR)/(1.0-DIMCPR), where DIMCPR = [MCPRp(old)-

l SLMCPR(TS)]/MCPRp(old). We have started evaluation of the impact of the change in SLMCPR on plant analyses other than reload specific, including MCPRf and the MCPRp curves, and expect to have results later this month. The impact on Single Loop l Operation has been evaluated and determined to continue to be 0.01 higher than the l

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' s, ,

normal two-loop operation SLMCPR. If you need guidance in changing your core monitoring system databank to reflect these changes, please contact us.

We will also provi6 a revised Supplemental Reload Licensing Reports (SRLR) to reflect these changes in the near future, including revised MCPRf and MCPRp curves.

Upun receipt of the revised SRLR you should modify your Core Operating Limits Report (COLR). It is our intent to modify the SRLR such that the Operating Limit MCPR is moc'ified to account for the increase in the SLMCPR , without changing the SLMCPR, and thus not requiring a change to your Technical Specifmations. Wo plan to review this approach with the NRC May 6-10,1996, during their visit here in Wilmington.

We also intend to send the NRC a letter documenting the interim procedure for cycle specific calculation of the SLMCPR. This will be the basis for the licensing activities until sub mittal and approval of our procedure for plant / cycle specife SLMCPR based on revised GETAB uncertainties.

We will have a plan and schedule for all remaining activities by May 22,1996.

Per your request, we have estimated the exposure at which the Tech Spec value of the SLMCPR would be exceeded in Hatch 2 cycle 13.

The verified analytic estimate (not Monte Cario calculation) for Hatch 2 cycle 13 BOC SLMCPR was 1.03. Based on a linear interpolation between the estimated BOC SLMCPR and the Peak Hot Excess SLMCPR (1.08 calculated with Monte Cario methodology), the SLMCPR would not be above the Tech Spec value of 1.06 until an exposure of approximately 3600 MWD /st. Note that this is an estimate only and does not imply that no action is required until this exposure. i 1

i inank you for your patience in this matter. Please call me if you have any questions.

Yours truly,

%d+

R. E. Kingston Senior Fuel Project Manager

- M/C A33, (910) 6754192 rk l

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GE Nuclear Energy i k

Richard L Kingston N: icky fuel Amocas 5' f :e F~. e:t Yra:;e' GenmI Dec:nc Cormry Care Hsive Road P O B2< is.i V C A23 Vtemm;:cn. NC 2Wt 4780 November 18,1996 mous stn cc: R. G. Cocherell 3

REK:96-382 ["'$'3 322" W. E. Grimme l B. E. Hunt T. C. Kanellopoulos l G. K. McElroy l W. R. Mertz i Mr. K. S. Folk, Manager BWR Core Analysis Southern Nuclear Operating Company i P. O. Box 1295 )

Birmingham, AL 35201

Subject:

Safety Limit MCPR (S' MCPR) Calculation for Hatch 2 Cycle 14

Dear Mr. Folk:

1 We have completed calculation of the SLMCPR for Hatch 2 Cycle 14. This calculation is based on the fuel cycle and loading pattern provided by SNC. The core design is the first cycle of I

operation with a mixed core of GE9 and a full reload of GE13 fuel. The SLMCPR was evaluated '

at three exposure points over the cycle; BOC, MOC, and EOC-2000 mwd /st. The particiption of each fuel type in determining the limit is identified.

This analysis explicitly addresses the GE13 fuel as being the limiting fuel for determination of

. MCPR thermal limits throughout the eyeb ad insures that the SLMCPR established near the end of cycle is bounding for the entire cycle.

He SLMCPR was calculated per GE procedure TDF -0049. l The results are tabulated below:

3 EOC SLMCPR 1.12 1

Single Loop EOC SLMCPR 1.14 Details of this calculation are documented and verified in the DRF.

If you have any questions, please call me. l l

Yours truly, cIl- M I R. E. Kingston Senior Fuci Project Manager M/C A33, (910) 675-6192 rk

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