ML20033E877

Forwards Supplemental Response to Generic Ltr 89-21 Re Implementation of USI A-11, Reactor Vessel Matl Toughness. GE Rept Re Upper Shelf Energy Analysis for Beltline Matls Encl

ML20033E877
Person / Time
Site:	LaSalle
Issue date:	03/05/1990
From:	Morgan W COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
REF-GTECI-A-11, REF-GTECI-RV, TASK-A-11, TASK-OR 0741T, 741T, GL-89-21, NUDOCS 9003150008
Download: ML20033E877 (3)

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3.^N) Commonwealth Edison -

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. Dr. Thomas E.'Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission

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. Washington, DC 20555 fs l

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Subject:

LaSalle County Station Units 1 and 2 7

Supplemental Response to Generic Letter 89-21 (Request for Information concerning status of

' implementation of Unresolved Safety Issue (USI) requirements).

HRC Dockets Nos. 50-373 and 50-374 l

Reference (a)I W.E. Morgan letter to T.E. Mu' rley dated October 20, 1989 (LaSalle County Station response'to GL 89-21).

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-(b) W.E. Morgan Jetter to T.E. Murley dated November 29, l

'1989 (LaSalle County Station supplement request for i

amendment to revise Pressure-Temperature curves) p L

- De'ar.Dr. Murley1-

Reference (a) submitted Commonwealth Edison's 'LaSalle County Station'

~ response to Generic Letter 89-21 (Status of Unresolved Safety Issue Requirements). Contained in that submittal LaSalle Station indicated that Unresc,1ved Safety. Issue ~ A-11 " Reactor Vessel Material Toughness" was currently l;

under evaluation for' applicability.

?The~following attachment'provides the LaSalle County Station evaluation of. Unresolved Safety Issue A-11.

Note: Reference 2 of the attachment was transmitted in the above Reference (b).

Please direct any-questions you may have regarding this matter to this office.

1 Very truly yours, t

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. Morgan

.PDR ADOCK 05000373 ff Nuclear Lie sing Administrator P

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'v ATTACHMENT GE Nuclear Energy j

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February 26, 1990 i

i Mr. R. L. Scott ec:

A. DeVita, GE j

Commonwealth Edison Company G. Cerzen, CECO

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1400 Opus Place, Suite 400 S. Ranganath, CE i

Downer's Crove, IL 60515 R. Tamminga, Ceco l

i Subj e'e t :

UFFER SHELF ENERGY ASSESSMENT FOR IASALLE UNITS 1 AND 2

References:

1. -

Response to NRC Qvestion 121.15, LaSalle 1 and 2 Final Safety Analysis Report, Amendment $6, May 1981.

l 2.

Caine, T.A., *LaSalle Units 1 and 2 Fracture Toughness Analysis t

per 10CFR50 Appendix G," GE Peport SASR 88 10, DRF 137 0010, March i

1988.

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Dear Bob,

As requested, below is an assessment of the upper shelf energy (UEE) predictions for LaSalle Units 1 and 2.

The assessments have been made at 32 effective full power years (EFPY) for normal operation and at 48 EFPY for life extension purposes.

METHODS The methods of predicting 32 and 48 EFPY USE values follow Regulatory Guide 1.99, Revision 2.

Initial values of USE are based on Reference 1.

Fluence and copper content information is from Reference 2.

The steps in calculating decreased USE, per the regulatory guide, can be followed in Table 1.

Reference 1 discusses initial USE values for the plates and welds of Units 1 and 2.

The discussion conservatively demonstrates that transverse USE meets at least 70 f t lb for the Unit 1 plates and welds, and meets at least 75 f t lb for the Unit 2 plates and welds.

These values are used as conservative lower bound values of initial transverse USE in Table 1.

I 17 n/cs? and f

&ased on P.tforence 2 data, the 32 EFFY fluences are 3.9x10

+

4.2x1017 n/ce2 for Units 1 and 2. respectively.

The 48 EFFY fluences are 5.9x1017 n/en2 and 6.3x1017 n/c.? for Units 1 and 2, respectively.

The copper content information from Reference 2 was reviewed, and the highest values taken for use in Table 1.

Tlr.e highest value for Unit 1 plates is 0.151, and for Unit 1 welds is 0.371.

N highest value for Unit 2 plates is 0.121 and for Unit 2 welds is 0.041, i

RESUI.TS The results are summarised in Table 1 below.

Table 1 l

UFPS $HE1J ENERCY ANALYS!$ FOR 1ASAL12 1 6 2 SELTLINE MATERIALS INITIAL 32 Em 32 Em 32 Em 46 Em 48 Em 48 trrY TRANS.

TwpCE $ DECR.

TRAles, rwpCE $ DECR.

TRANS.

COMPONEXT U$t Sco (m10*17)

U$t U$t (m10'17)

U$t U$t UNIT 1:

i Flate 70.0 0.16 3.9 11.$

l 62.0 l S.9 12.5 l 61.3 l v44*

70.0 0.37 3.9 27 l 51.1 \\

5.9 28 I 50.6 l l

UNIT 2:

(

Plate 75.0 0.12 4.2 10 l 67.5 l 6.3 11 l 66 6 l Weld 75.0 0.04 4.2 9

l 68.3 l 6.3 10 i 67.5 l t

I Act.a1 Unit I weld CharTy data, tested at only 10 F.

rante from initial values of 79 ft.lb to 126 ft lb.

l Therefore, the actual.i2 and 48 E m U$1 values will be significantly higher t'.an those shown sbove.

In conclusion, the conservative predictions for USE of the Unit I and 2 beltline materials are above 50 ft.lb, as required by 10CTR50 Appendix G.

If you have any further questions on the subject, please call se at the number _

below.

Regards, f"'..

Im

7. A. Caine, Senior Engineer Materials Monitoring & Structural Analysis Services (408) 925 4047, Mail Code 747

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