ML20100L344

Forwards Rev 0 to GE-NE-B1301786-01, LaSalle Unit 2 RPV Surveillance Matls Testing & Analysis & Rev 0 to GE-NE-B1301786-02, Demonstration of Compliance W/10CFR50, App G for LaSalle Unit 2 Plate Matl

ML20100L344
Person / Time
Site:	LaSalle
Issue date:	02/29/1996
From:	Benes G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20100L346	List: B130178, Demonstration of Compliance W/10CFR50,App G for LaSalle Unit 2 Plate Matl ML20100L344 ML20100L355
References
GL-92-01, GL-92-1, NUDOCS 9603040178
Download: ML20100L344 (3)

Text

Commonwealth Iklison Company 1400 Opus Place Downers Grove, IL 60515-5701 February 29,1995 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

SUBJECT:

LaSalle County Nuclear Power Station Unit 2 Reactor Vessel Material Surveillance Program-Appendix H Facility Operating License NPF-18 NRC Docket 50-374

REFERENCE:

1) D. Saccomando letter to USNRC, dated November 17,1995, Commonwealth Edison Company's Response to NRC Generic Letter 92-01, Supplement 1:

" Reactor Vessel Structural Integrity."

In accordance with Appendix H of 10 CFR 50, Commonwealth Edison Company (Comed) is submitting the following report, GE-NE-B1301786-01, LaSalle Unit 2 RPV Surveillance Materials Testinc and Analysis, Revision 0, February 1996.Section III of Appendix H, " Report of Test Results", requires a summary technical report to be submitted within one year after Reactor Vessel Material Surveillance Specimen Capsule withdrawal. The LaSalle Unit 2 300 degree azimuth location Reactor Vessel Material Surveillance Specimen Capsule was withdrawn from LaSalle Unit 2 on March 1,1995. GE-NE-B1301786-02, Demonstration of Compliance with 10CFR50 Appendix G for the LaSalle Unit 2 Plate Material, Revision 0, February 1996, is also being submitted to demonstrate that the LaSalle Unit 2 RPV remains in compliance with 10CFR50 Appendix G and remains bounded by the Boiling Water Reactors Owners Group upper shelf energy (USE) Equivalent Margins Analysis (EMA) referred to in Reference 1.

In your review of this report the following points should be noted:

Results For the surveillance weld metal, the measured 30 ft-lb Charpy energy transition temperature shift and USE decrease are acceptable in accordance with Regulatory Guide 1.99, Revision 2.

For the surveillance plate, sufficient initial property data in the appropriate rolling direction orientation was not available to establish a measured 30 ft-lb Charpy energy transition temperature shift and USE decrease from the surveillance data. For this reason, the attached analysis; Demonstration of Compliance with 10CFR50 Appendix G for the LaSalle Unit 2 Plate Material, was

._.n 9603040178 960229 ,

PDR ADOCK 05000374 P PDR 2 A Unicom Company

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. USNRC (2) February 29,1996

+

4 performed to provide conservative estimates of transition temperature shift and

- USE decrease. The results demonstrate compliance with 10CFR50 Appendix G requirements and show that the LaSalle Unit 2 RPV remains bounded by the  ;

~ EMA.

GE Surveillance Capsule Testina Corrective Actions Chemical analysis errors were discovered in Revision 0 of the LaSalle Unit 1 -

300* surveillance capsule report (transmitted by G. Benes to USNRC letter dated March 23,1995) and subsequently corrected in Revision 1 (transmitted by G.

Benes to USNRC letter dated June 21,1995). As a result of the errors, corrective

- actions were implemented by GE. To verify that the corrective actions taken by <

GE were effective, and to assess current GE surveillance capsule testing capabilities and performance, Comed Supplier Evaluation Services personnel 1- - perfonned an audit of the GE Vallecitos and San Jose facilities. No deficiencies or problems were noted. j j

j In addition, the GE chemical analysis results for the LaSalle Unit 2 - 300*

J surveillance capsule plate and weld metal specimens were independently l' l

confirmed by Argonne National Laboratory.

i Conclusions l

The surveillance weld and plate materials exhibit acceptable adjusted reference

temperature shifts in accordance with Regulatory Guide 1.99, Revision 2. The i

surveillance materials also exhibit adequate USE for continued safe plant operation, and are projected to maintain an USE greater than 50 ft-lb through 32 j EFPY in accordance with 10CFR50 Appendix G.

Based on the surveillance capsule results, the current 16 and 32 EFPY Technical Specification heatup and cooldown limit curves are conservative and are not

required to be updated at this time.

NRC Reactor Vessel Intecrity Database Summary File Comment .

In the course of verifying the Taalle Unit 2 RPV Surveillance Materials Testing and Analysis, it was determined that the initial RTNDT value for LaSalle Unit 2 weld metal 3P4966 listed on page 52 of the NRC Reactor Vessel Integrity Database (RVID) Summary File for PTS (which was included as part of the

Reference 1 Comed response) should be -6*F rather than the listed -26*F. Initial RTNDT values for 3P4966 were established by the RPV manufacturer, Chicago

Bridge and Iron, for the single and tandem submerged are welding processes.

4 5

.i USNRC (3) February 29,1996 Fabrication records do not indicate which of the pincecaes we..s utilized, so the bounding value of-6*F established for the tandem are process rather than the - ,

26*F established for the single are process should be indicated in the RVID. All l other beltline weld values ofinitial RTNDT listed in the RVID for LaSalle Unit 2 were confirmed to be bounding. All previous evaluations of operating Pressure-Temperature limits for LaSalle Unit 2 have utilized the conservative bounding l value of-6*F for weld metal 3P4966, and therefore do not need to be updated.

Please direct any questions you may have concerning this matter to this

- office. ,

f Very truly yours, l

GS W l Gary . Benes l i

Nuclear Licensing Administrator Attachments:

i GE-NE-B1301786-01, T.aRalle Unit 2 RPV Surveillance Materials Testing and Analysis, Revision 0, February 1996.

GE-NE-B1301786-02, Demonstration of Comoliance with 10CFR50 Annendix G for I the T aRalle Unit 2 Plate Material, Revision 0, February 1996.

i ec: H. J. Miller, Regional Administrator - RIII P. G. Brochman, Senior Resident Inspector - LSCS ,

M. D. Lynch, Project Manager, NRR i

Office of Nuclear Facility Safety - IDNS

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