ML20209F775

Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary

ML20209F775
Person / Time
Site:	Peach Bottom
Issue date:	07/12/1999
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20137X217	List: ML20209F764 ML20209F775
References
NUDOCS 9907160125
Download: ML20209F775 (12)

Text

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f ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 Docket No. 50-278 Ucense No. DPR-56 i

TECHNICAL SPECIFICATIONS CHANGES Attached Pages Unit 3 i

TS Page 2.0-1

)

TS Page 5.0-21 i

l' 9907160125 990712 PDR -ADOCK 05000278..

P PDR.

o i:

1 i

SLs 2.0 2.0 SAFETY LIMITS (Sts)

-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.

l 2.1.1.2 With the reactor steam dome pressure 2 785 psig and core flow 210% rated core flow:

MCPR snall be 2 1.09 for two recirculation loop operation or 21.11 for single recirculation loop operation.

2'.1.1. 3 Reactor ver.sel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL i

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 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 and the Vice President-Peach Sottom Atomic Power Station.

(continued) l PBAPS UNIT 3 2.0-1 Amendment No.

y

=

.e Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The Average Planar Linear Heat Generation Rate for Specification 3.2.1;

)

2.

The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1; 3.

The Linear Heat Generation Rate for Specification 3.2.3; and 4.

The Control Rod Block Instrumentation for Specification 3.3.2.1.

j b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version as specified l

in the COLR);

i 2.

NEDC-32162P, " Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic i

l Power Station Units 2 and 3,"

Revision 2, March, 1995; 3.

PEco-FMS-0001-A, " Steady-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code";

4.

PEco-FMS-0002-A, " Method for Calculating Transient Critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPECo)";

5.

PEco-FMS-0003-A, " Steady-State Fuel Performance Methods Report";

6.

PEco-FMS-0004-A, " Methods for Performing BWR Systems Transient Analysis";

(continued)

PBAPS UNIT 3 5.0-e1 Amendment No, i

l SLs 2.0

{

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

Je 'Ic-THERMAL POWER shall be s 25% RTP.

.l.1.2 With the reactor steam dome pressure a 785 psig and core flow a 10% rated core flow:

m

^ for two recirculation loop operation

/ /, 09 MCPR 1 be > <

or a for sid e ractreulation loop operation.

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

I. Il 2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.

2.2. SL Violations With any SL violation, the following actions shall be c::aleted:

2.2.1 Within I hour, notify the NRC Operations Center. n accorcance 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 and the Vice President-Peach Bottom Atomic Power Station.

(continued) l Mb v:Tud %Y 2.1.2.2 h ;p!i::T.: : 1y 6fp Cy:!: !! ::: :!95

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EAFS UNIT 3 2.0-1

!cenament No. 225

Reporting Requirensetc 5.6 5.6 Reporting Raoutrecents (continueo) 5.6.5 CORE OPERATING LIMITS REPORT /COLR) a.

Core operating limits shall be established prior to each reloao cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following-1.

The Average Planar Linear Heat Generation Rate for Specification 3.2.1; 2.

The Minimum Critical Power Ratio for Specifications 3.2.2 and 3.3.2.1; 3.

The Linear Heat Geret. tion Rate for Specification 3.2.3; and 4.

The Control Rod Block Instrumentation for Specification 3.3.2.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by J

the NRC, specifically those described in the following i

documents:

1.

NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version as specified intheCOLR);p f

s 4-2.

NIDC-32162P, " Maximum Extenced Load Line Limit and ARTS Ch Improvement Program Analyses for Peacn Egttom Atomic a gie PowerStationUnits2ano3,"Revisiong, gjd4 N,

-v

-^-

c N & m,R9sj

~

~

3.

PEco-FMS-0001-A, "Steacy-State Thermal Hydraulic Analysis of Peach Bottom Units 2 and 3 using the FIBWR Computer Code";

4.

PEco-FHS-0002-A, " Method for Calculating Transient Critical Power Ratios for Boiling Water Reactors (RETRAN-TCPPEco)';

5.

PEco-FMS-0003-A, "Steacy-State fuel Performance Methods Report';

je[o 6.

PEco-FMS-0004-A, " Methods for Performing BWR Systems

]

Transient Analysis';

(continued)

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an PBAPS UNIT 3 5.0-21 Amenoment No. 25

?

ATTACHMENT 4 PEACH BOTTOM ATOMIC POWER STATION UNIT 3 Docket No. 50-278 License No. DPR-56 LICENSE CHANGE APPLICATION ECR 99-01255 Non-Proprietary Version k

I f

Attachament AdditionalInftruction Regardi 3 the June 9,1999 Cycle Speedic SLMCPR f r Peach B:st:m 3 Cycle 13 References

[1]

letter, Frank Akstulewu:s (NRC) to Glen A. Watford (GE), "Acaptance for Refernacmg of 1 -% Topical Rsports NEDC-32601P, Methodology and Uncertaintiesfor Safety Limit MCPR Evaluationt; NEDC-32694P, Power Distribution Uncenamtiesfor Sa.fety Limit MCPR Ewduadon; and Amende==r 25 to NEDE-24011-P-A on Cycle Specific Safety Limit MCPR,"

(TAC Nos. M97490, M99069 and M97491), March 11,1999.

[2]

Ietter, 'Ihanus H. Essig (NR.C) to Glen A. Watford (GE), "A-

,2== for Referencmg of Ijamassag Topacal Raport NEDC-32505P, Revison 1, R-Foctor Calculatsm Methodfor Gell, GE12 and GElJ Fuel,"(TAC No. M99070 and M95081), January 11,1999

[3]

Geesnel Electric BWR Dermalhealysis Basis (GETAB): Data, C orrelation and Design Application, NEDO-10958-A, January 1977.

Comparison of Peach Bottom 3 Cycle 13 and Cycle 12 SLMCPR Values Table 1 summarues the relevant input parameters and results of the SLMCPR determmation for the Peach Bottosa 3 Cycle 13 and Cycle 12 cores. 'Ihe SLMCPR evalustans were performed usmg NRC approved===hada and unceriantiesM These evalustaans yield ddFeras calculated SLMCPR values i

because ddforant impues were used. The quantmans that have been shown to have some impact on the deternmention of the sainty lissit MCPR (SLMCPR) ase provided.

In companas the Peach Bottom 3 Cycle 13 and Cycle 12 SLMCPR values it is important to note the unpact of the ddruences in the com and bundle dose *Ihese differences are summarized in Table 1.

IDI

[01 l

The uncontrolled bundle pm-by-pin power distributions were compared between the Peach Bottom 3 Cycle 13 bundles and the Cycle 12 bundles Pin-by-pin power distributions are characterized in terms of R-faccom usmg the NRC approved =h~1ala=y[2]. [0]

l I

Non-Proprietary Informauon pageIcf3

Attachment AdditionalInform: ties Regarding the June 9,1999 Cycle Speedic SIJiCPR for Peach B:tt:en 3 Cycle 13 S - ry

[G] have boat used to compare quaannes that impact the =lentatari SLMCPR value. Based on these compensons, the conclusion is reached that the Peach Bottom 3 Cycle 13 core / cycle has a more peaked core MCPR distribution (0] and flatter m-bundle power distributions (0) than what was used to perform the Cycle 12 SLMCPR evaluanon.

h e=Im1=*ari 1.09 Monte Carlo SLMCPR for Peach Bottom 3 Cycle 13 is consistent with what one would expect [Q] the 1.09 SLMCPR value is appropnate.

Based on all of the facts, observanons and argusannes preseted above, it is concluded that abs cakaisted SLMCPR value of 1.09 for the Plant Cyeic n oose is appropnate. It is reasonable that this l

value is 0.02 lower than the 1.11 value calminuwt for the previous cycle.

For single loop operanons (SLO) the calculated safety limit MCPR for the limiting case is 1.11 [0]

Prepared by:

Venfied by:

I ff Y

S. B. hitaa W.E. Russell I

Technical Project Manager Nuclear Fuel Fng=g g Peach Bottom Project Non-Proprietary Information page 2 of 3

Attachment Additional Inforniation Regarding the Ju:e 9,1999 Cycle Specine SLMCPR for Peach B:ttran 3 Cycle 13 Table 1 Comparison of the Peach Bottom 3 Cycle 13 and Cycle 12 SLMCPR IUl I

Non-Preprietary Information page 3 of 3

7 7

p OU GE Nuclear Energy a.-wames can ar P, o. ans 700, Hampma, NC 2840r Affidavit I, Craig F. Kipp, being duly sworn, depose and state as follows.

(1) I am Geeral Manager, Nuclear Fuel, General Electne Company ("GE") and have been delegated the funcnon of remewmg the aformanon described in paragraph (2) which is sought to be withheld, and have been authorund to apply for its withholdmg.

(2) De information sought to be withheld is marziand in the letter, G. D. Edwards (PECO Energy Company) to the U. S. Nuclear Regulatory Comnussion h-~* Control Desk, Peoch Bottom Atomic Power Station. Unit 3 License Change Application ECR 99-01255, Docket No. 50-278, I ima** No. DRP-56.

(3) In makms this applicanon for withholdag of proprietary aformater. <. which it is the owner, GE relies upon the caempaan from A=cla=m set forth in the Freedom ofInformaten Act ("FOIA"),

5 USC Sec. 552(b)(4), and the Trade Secrets Act,18 USC Sec.1905, and NRC regulatmos 10 CFR 9.17(a)(4) and 2.790(a)(4) for " trade secrets and commercial or finnammi informanon obtained from a person and privdeged or maMaarial" (Exemption 4). The matenal for which exemption from disclamre is here sought is all "maMaarial commercial information," and some pornons also quahfy under the narrower dafinirian of" trade secret," within the mesmngs assigned to those terms for purposes of FOIA F-P 4 in, respectively, Critie=1 M=== Faerry Prr-a* v.

Nuclear Regulatory Commissen. 975F2d871 (DC Cir.1992), and hbhc_CitizRILEARkb Research Groun v. FDA. 704F2dl280 (DC Cir.1983).

(4) Some examples of categories of information which fit into the definition of proprietary informaten are:

a.

Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by General Electric's compeutors without i

hcense from General Electric consugtes a competitive economic advantage over other j

4 carapnaia.-

b. Informatre which, if used by a rh, would reduce his eg= E ure of resources t

or impame his compeutive posman in the deman, manufacture, shipmat, ia*-11 +6 i

assurance of quahty, or licensmg of a samlar product; c.

Informaten wiuch reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers;

d. Informanon which reveals aspects of past, present, or future General Electric c'tstomer-funded development plans and programs, of potential commercial value to General i

Electnc; Informanon wiuch discloses patentable subject matter for which it may be desirable to

. c.

obtam patent protecten Page!

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f j

Amd:vst The aformanon sought to be withbeid is considered to be proprietary for the reasons set forth in both paragraphs (4)a. and (4)b., above.

(5) The informatmo sought to be withheld is being submitted to NRC in enaManes ne info

on is of a sort -

===ily held in confidace by GE, and is in fact so held. Its initial designanon as proprietary aformanon, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in (6) and (7) followmg. The informance sought to be withheld has, to the best of my knowledge and behef, ena.m n ly been held in en=Mance by GE, no public disclosure has bem made, and it is not avadable in public sources. All diaelaanres to third parnes including any required tr====nerale to NRC, hcve been made, or must be made, pursuant to rgniatory provisions or proprietary agreements which prcmde for ronmtanarice of the infor==hna in ennrubeme (6) Initial approval of proprietary treatment of a document is made by the manager of the origmatag the person most likely to be==M with the value and sensitivity' of the ca=ar~

infor== nan in relaten to industry knowledge. Access to such daen-ts within GE is imuted on a "need to know" basis.

(7) De procedure for approval of external reicase cf such a 6-t typically requires review by the staff manager, project manager, precipal scianst or other equivalent authonty, by the manage of the cogmzant ir.a.' sung fhaenna (or his delegate), and by the legal Operation, for eachaie=1 consent, ---;-- 6ve effect, and determmarion of the accuracy of the propnetary designanon Disclosures outside GE are knused to regulatory bodies, customers, and possanal customers, and their agents, suppliers, and u

. and others with a legitimate need for the informanon, and then only in accordance with appropriate segulatory provisions or p.w.;et-iy agreements.

(8) The informanon idenafied in paragraph (2) is classafied as proprietary because it contains dotads of GE's Safety Limit MCPR analysis and the w.A results which GE has applied to this specific plant and cycle's actual core design with GE's fuel.

& dc.e' ;== of the n=rhads used in these analysis, along with the testmg, development and approval of the supporung critical power co.ide:ics was achieved at a significant cost, on the order of several million dollars, to GE.

(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-makmg opportunities.

The stability analysis is part of GE's comprehannive BWR safety and technology base, and its commercial value extends beyond the original dra'- ;- = cost. The value of the '~ haatag base goes beyond the extasive physical database and analyncal methodology and includes developmmt of the experuse to deterame and apply the appropnate evaluatmo process. In addshan, the technology base includes the value derived from providag analyses done with NRC-approved innhads De research, development, engmeenng, analytical, and NRC reviev costs comprise a subarmahal investmet of time and money by GE.

h precise value of the expertise to devise an evaluation process and apply the correct analytical av*hadalogy is dif5 cult to quantify, but it clearly is substantial.

Page 2

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_Af6d:vit GE's ---- =-:n advantage will be lost ifits competitors are able to use the results of the GE exponence to normahze or verify their ow.1 process or if they are able to claim an equivalent understandag by '=- =-E.Gug that they can anive at the same or simdar conclusions.

The value of this is.. don to GE would be lost if the information were disclosed to the public.

Malung such informanon avadable to e-- ge%rs without their having been required to undertake a simdar e5=f 1-e of resources would unfairly provide competitors with a wmdfall, and deprive GE of the opportunity to exercise its w-@Gve advantage to seek an adequate return on its large aw=r=== in developes these very valuable analytical tools.

State ofNorth Camhna

)

SS:

County ofNew Hanover )

Craig P. Kipp, being duly sworn, deposes and says:

That he has read the foregomg af5 davit and the matters stated therem are true and correct to the best of his knowledge,icn,.

Gee, and behef.

Executed at W"-'aa North Carolina, this 8 dayof L s a_

.1999

/

C+,

Craig P.

General Electric Company N ay of I h

.19 99 Subscribed and sworn before me this f d

(/

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Public, State ofNorth Carolma My Commissen Expires

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