ML20199E806

Forwards Suppl Info Re 970521 Request for Amend to Ts.Listed Attachments Reflect Incorporation of 1996 Addendum & Revised WCAP-14824 for Staff Review & Approval by 971231

ML20199E806
Person / Time
Site:	Byron, Braidwood
Issue date:	11/18/1997
From:	Hosmer J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20199E810	List: ML20199E806 ML20199E828 ML20199E853 ML20199E875 ML20199E880
References
NUDOCS 9711240005
Download: ML20199E806 (9)

Text

f.ommonw uhh htwm Omipany I 4m opm lin e low nors Urm e, IL M t $ Pol November 18,1997 U.S. Nuclear Regulatory Commission Washington, D C. 20$55 Attn: Document Control Desk

Subject:

Supplement to the Application for Amendment to Appendix A, Technical Specifications for Facility Operating Licenses liraidwood Nuclear Power Station, Units I and 2 NRC_IMcktLNumbr.tE.1fL-4}iA01 50-457 1

Ilyron Nuclear Power Station, Units 1 and 2 NB.C.DmkcLNumhett10-454 and.10AM Relocation of Pressure and Temperature Limits

References:

1.

J. Ilosmer letter to NRC dated May 21,1997, transmitting Technical Specification Amendment Request 2.

J. Ilosmer letter to NRC dated May 6,1997, transmitting Reactor Vessel Integrated Surveillance Program 10 CFR 50, Appendix 11, Section 111, C 3.

J. Ilosmer letter to NRC dated April 3,1997, transmitting Request for Exemption from Requirements of 10 CFR 50.60 to Use the 1996 Addenda of ASME Section XI, Appendix G, Article G 2000 Reference I transmitted the Commonwealth Edison Company (Comed) request to amend Appendix A, Technical Specifications, of Facility Operating Licenses for Byron and liraidwood to allow licensee control of the Reactor Coolant System Pressure and Temperature 1.imits for heatup, cooldown, low temperature operation and hydrostatic testing. As stated in that letter, Comed requested permission to integrate the weld metal surveillance programs for Byron Units I and 2 and for Braidwood Units 1 and 2.

Additionally, Comed also requested via Reference 3, permission to use a later version of

,i the ASME Iloiter and Pressure Vessel Code than is listed in 10 CFR 50 55a.

g 9711240005 971118 PDR ADOCK 05000454 P

PDR niaibybwd\\ptcun es doc A rnicom n miuny 4

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I U.S. Nucl:ar Regul: tory Commission 2-November 18,1997 The proposed Technient Specification amendment request stated that, pending approval of the use of the 1996 Addenda of the ASMF Code and the integration of weld metal surveillance programs, new pressure tempc.,. are (P/T) curves would be submitted to the Stalt i'er conversations with the Staff, Comed has been requested to submit the attached supplement to the proposed Technical Speelfication before the final approval of the 1996 Addenda of the ASME Code and the integration of weld metal surveillance programs.

We understand that approval of the 1996 Addenda of the ASME is imminent. Comed will be submitting a revision to the description of weld metal surveillance program integration (WCAP 14824)" Byron Unit 1 IIcatup and Cooldown Limit Curves for Normal Operation and Surveillance Weld Metal Integration for Byron and Braidwood "

to the Staffin November.

l The following attachments reflect incorporation of the 1996 Addendum and the revised WCAp-14824:

WCAP-14940 "flyron Unit 2 Ileatup and Cooldown Limit Curves for Normal Operation" and Erratta Sheet (Westinghouse letter CAE 97 210, CCE 97 289);

WCAP 14970 "llraidwood Unit 2 Heatup and Cooldown Limit Curves for Normal Operation" and Erratta Sheet (Westinghouse letter CAE 97-210, CCE 289);

Revision to " Byron Unit 1 Pressure and Temperature Limits Report" and "Braidwood Unit 1 Pressure and Temperature 1.imits Report" which includes the following:

Note added that 1996 Addenda was not used for Byron and Braidwood Unit 1 Pfr curves; Tenable temperature revised ts 200 F based on WCAP-14824 Revision 2 data Revised Table 2.1 and Figure 2.3 for clarity; Revised Table 4.1-4.6, to incorporate WCAP-14824, Revision 2; References modified to incorporate WCAP-14824, Revision 2 throughout the document; Editorial changes to address typos, page numbers and minor comments; and Revision to "Hyron Unit 2 Pressure and Temperature Limits Report" and "Braidwood Unit 2 Pressure and Temperature Limits Report" which includes the following:

Incorporated revised WCAP 14940 (WCAP-14970 data for Braidwood) into Tables 4.1 through 4.6; Tenable temperature revised to 200 F based on WCAP-14824, revision 2 data; nla\\bybwd\\pteurves. doc

~

U.S. Nuclear Regulatory Comndssion 3

November 18,1997 Updated l'igures 2.1,2.2, Table 2.1 with new P.T data; llevised liigure 23 for clarity; Note added that 1996 Addenda used for Ilyron and liraidwood Unit 2 P/r cun'es; References modified to incorporate WCAP 14P24,llevision 2 throughout the document;

!!ditorial changes to address typos, page numbers and minor comments.

Coml!d requests that the StafT review this supplement in a timely manner and approve the pending technical specification by December 31,1997, to support flyron Unit I startup from the steam generator replacement outage (111R08) and to support continued Ilraidwood Unit 2 operation past expiration of applicable Pfr curves. Please address any comments or questions regarding this matter to this ollice.

Sincerely.

. hypov, tv John 11. Ilosmer lingineering Vice President Attachments ec:

llegional Administrator-11111 Ilyron/llraidwood Project Manager - NRR Senior Resident inspector - Ilyron

' senior Resident inspector Ilraidwood Office of Nuclear 1:acility Safety - IDNS nla\\bybwd\\pteurves. doc

4 CAE-97-210 CCE-97-289 n nas Westiagbosse Energy Systems wn Doctrk Corporation November 4,1997 Raf:

EDRE-EMT 308 Mr. Tom Spry

(*mnFJ 1400 OpusPlace DownersOrove,IL 60515 Comed Brass and Braidwood Units 2 y-;::2 af U=d:ed T "-- la WCAh14940 - ' 14970

Dear Mr. Spry:

For your inforemation and uns are the attached tables Aom WCAPe14940 and 14970 wh contain the following updated infonnation: :

Ta'olo 6

15) froni WCAP-14940 (For Byron Unit 2) contains and ARTvalues on Position 1.1 for the Table 4 (page 11) Rosa WCAP-14970 (For Braidwood Unit 2) :

contains updated Capsule designation for the Br-8dwood Unit 2 Wald Metal. The second capsule for Braldwood (Jnit 2 was changed to X.

This letter and/or each table must be inserted into an known copies of WCAP-14940 (Attachment 1) and WCAP-14970 (Attachment 2).

- win.n

2-CAE47-210 Mr. Tom Spry CCPr97-289 If you have any questions or need additional idormadon, please contact the undersigned or

'!homas J. Laubham at 412 374-6788, vwyindy yours, WESTD4GHOUSEEUiCTRIC CORPORATION C. S.Hauser, Project Manager Comed Project Nuclear Serviou Attomaat oc:

Brad Adams - Byron MikaGorski Braidwood P. McHale t

e

l e

ATTACIBfENT 1 Updated Table 6 to WCAP-14940 4

P I

TABLE 6 Summary of Adjusted Reference Temperatures (ART) at 1/4T and 3/4T Locations for 12 EFPY 12 ' FPY Matenal c

1/4T ART 3/4T ART Intermediate Shell Forging 12.1 1.7 490329/49C297 1 1 (RQ Poemon 1(*))

using credih4 surveillance 31.7,

14.9 capsula data (ftG Posnien 2(a))

Lower Shell Forging 11.8 1.5 l

490330/49C298 1 1 (R3 Poston 1(*))

CircumferentialWeld 119.2 83,7 (Ro Poems 1(a))

using credble surveillance 87.8M 71.8*

ospsule dattu(RG Poetkm 2(a))

NOTE $;.

(a)

Calculated unio) a chemistry factor based on Regulatory Guida (RG) 1.99 Revlolon 2 Positons i

1 and 2.

(D)

These ART values were used to generste the Byron Unit 2 heatup and cookkwn curves.

Byron Unit 2 Heatup and Coondown Limit curves October 1997 t

i k:

j i

f i

1 1

I I

i W

A1TACHMENT 2: Updated Table 4 to WCAP-14970 N

i

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4 I l' ) ~

4 P

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6 I

a s

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a-aw.,~,.<.--n-,,' ear,m-n-~---,-a.-

.~ranew,,,ne--.--+w,n,w.new

,-.-.en,----

,-.--m wn~

,--+,.,-n.-+--,-n.---~

---.-n.,,---, - - - -.

,--n--,---.

,,ev

TABLE 4 Calculation of Chem';try Factors Using Credible Braidwood Urts 1 and 2 Surveillance Capsule Data Material Capsule Capsule FF*'

Measured FF' FF8 Fluence f ART.

ART.

Lower Shell Forging 5001021/50C971 U

3 933 x 10

O.741 0

0 0.550 (Tangential)

X 1.126 x 10

1.033 3

3.099 1.067 1.ower Shell Forging U

3.933 x 10

O.741 5

3.707 0.550 5001021/50C971 X

1.126 x 10

1.033 35 36.160 1.067 Sum-42.996 3.234 Chemistry FactorM = 42.996 + 3.234 = 13.3*F Braldmxxf 1 Weid U

3.614 x 10" 0.733 10 7.333 0.538 MetalWF 562N X

1.144 x 10*

1.038 25 25.95 1.077 Braidwood 2 Wtid U

3.933 x 10" 0.741 0

0.00 0.550 MetalWF-562M X

1.126 x 10" 1.033 20 20.66 1.067 Sum:

53.943 3.232 Chemistry Factor * = 53.943 + 3.232 = 18,7'F NOTES:

(a) FF = Fluence Factpr a f"8*40 (b) Braidwood Unit 1 ART,evalues were obtained from WCAP 14243. The Bradwood Unit 1 capsule fluence values were recalculated using the ENDF/B-V scattering cross sechons in 1994 and are l

documented in WCAP-14044m, (c) Braldwood Unit 2 capsule fluenoa, FF, and ART., values were cbtained from the surveillance Capsule X anahsis (WCAP 1422805) using the ENDF/B-V scattaring cross sections.

(d) Chemistry Factor = RFPART,a) + UFF2) l l

October 1997 Braidwood Unit 2 Heatup and Cooldown Umit Curves a

-,--m.

+ ' - - -

.