RBG-45109, Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted

Provides Comments on Reactor Vessel Integrity Database. Requests That Data Be Corrected as Noted

ML20216E567
Person / Time
Site:	River Bend
Issue date:	09/08/1999
From:	King R ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AC-MA1209, RBF1-99-0263, RBG-45109, NUDOCS 9909150085
Download: ML20216E567 (3)

Text

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Ent:rgy operations, Inc.

4 River Bend Staton 5485 U.S Highway 61

=Entergy Bl5l5:-

Fax 225 635 5068

. , Rick J. King Director Nuclear Safety Assurance September 8,1999 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 l

Subject:

Reactor Vessel Integrity Database Comments as Requested by the Closure of TAC No. MA1209 Letter, Dated July 23,1999 .

River Bend Station I License No. NPF-47  !

Docket No. 50-458 File Nos.: G9.5, G9.3 3.4 RBG-45109 RBF1-99-0263 Gentlemen:

The closure letter for TAC No. MA1209, dated July 23,1999, contained a recommendation for i River Bend Station (RBS) to review the Reactor Vessel Integrity Database (RVID) data on the  !

world-wide-web and provide comments. The attachment to this letter provides our comments on l the RVID. We request that the data be corrected as noted. I Should you have any questions or require additional information, please contact Mr. Bill Fountain of my staff at (225) 381-4625. i Sincerely, RJK/WJF/

i attachment 0

3 p: ,0 9909150085 990908 PDR ADOCK 05000458 P PDR

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i o RBS RVID Comments I September 8,1999 RBG-45109 -

RBF1-99-0263 page 2 0f 2 cc: Mr. Robert J. Fretz U. S. Nuclear Regulatory Commission M/S 04-D-03

. Washington, DC 20555 U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident Inspector

PO Box 1050 St. Francisville, LA 70775 l

1

p Attachment to RBG-45109 RBS RVID Comments Pressure - Temperature (P-T) Limits Summary Report:

1. NRC uses 0.664E19 for neutron fluence at end oflife (EOL). The value RBS provided in previous submittals is 0.660E19. As a result of this difference, calculated values for fluence l factor at EOL, delta-RTndt @ EOL, and RTndt @ EOL are different from previously submitted values.

2. The margin values for axial welds 492L4871/A421B27AE and 492L4871/A421B27AF are different than that previously supplied. NRC uses 47.8 and 36.3, respectively, while our numbers are 42.9 and 32.5, respectively. Consequently, RTndt at end oflife is correspondingly larger in RVID 2 than that supplied by EOI.

3. Sulfur content for weld SP6756/0342(S) should be 0.011 instead of 0.012 per Updated Safety Analysis Report (USAR) Table 5.3-1.

Upper Shelf Energy (USE) Summary Report:

1. The listed values for Unirradiated USE appear to be averages of the values reported in USAR Table 5.3-1 rounded down to the nearest whole number except for welds SP6756/0342(S) and 5P6756/0342(T) which appear to be rounded to the nearest tenths. If this is the case, the value for weld 5P6756/0342(S) should be 91.30 instead of 96.70. {

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2. USE at End of Life at 1/4T and % Drop in USE at End of Life at 1/4T were determined by the NRC using a data base or equations for the curves in Figure 2 of Regulatory Guide 1.99, Rev. 2, and the 1/4T Neutron Fluence at End of Life. The value used for 1/4T Neutron at End of Life is consistent with information supplied previously. Therefore, (except as noted in item I immediately above) the NRC-calculated values are assumed to be correct.

As the two reports cited above form the basis for other information presented in RVID 2, these discrepancies carry forward in the " Detail" reports for the River Bend section of" Forgings, Plates, Welds for This Plant." l

References:

1. RBS USAR Table 5.3-1

2. Gulf States Utilities letter RBG-32835, dated 5/4/90, with GE Report SASR 89-20, Rev.1

3. Entergy Operations Inc. (EOI) letter RBG-44583, dated 8/4/98

4. Chicago Bridge & Iron Nuclear (CBIN) welding procedure WPS-323-2F4F6 l