ML20151X775

Submits Response to RAI Re GL 92-01,Suppl 1, Reactor Vessel Structural Integrity

ML20151X775
Person / Time
Site:	Oyster Creek
Issue date:	09/10/1998
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
1940-98-20489, GL-92-01, GL-92-1, NUDOCS 9809170246
Download: ML20151X775 (3)

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i U.S. Route #9 South orked ve NJ 731 0388 Tel 609-9714000 1940-98-20489 September 10,1998 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Operating License NO. DPR-16 Docket No. 50-219 Response to Request for Additional Information (RAI) regarding Reactor Pressure Vessel Integrity at Oyster Creek Nuclear Generating Station (OCNGS)

Generic Letter (GL) 92-01, Revision 1, Supplement 1, " Reactor Vessel Structural Integrity" was issued in May 1995 which requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments. After reviewing our response, the NRC issued a letter dated April 29,1998 requesting that GPU Nuclear re-evaluate the RPV weld chemistry values that were previously submitted as part of the licensing basis in light of the new information submitted by BWR Vessel and Intemals Project (BWRVIP). The BWRVIP submittal included bounding assessment of new data from the Combustion Engineering Owners Group (CEOG) database.

GPU Nuclear reviewed the CEOG report (CE NPSD-1039 Rev. 2) and compared the best-estimate copper and nickel contents proviaed in the report with those given in the Oyster Creek docketed information (i.e., Technical Specification Change Request No.245 dated August 23,1996 and its approved Amendment No.188 dated March 6, 1997). The results are tabulated in the attached Table 1 per the RAI request.

The adjusted reference temperature (ART) based on the docketed information for weld wire heats No. 86054B and No.1248 are 150 F and 70 F, respectively. The calculated ART, using the best estimates, is 107 F for 86054B and 66 F for 1248. The large discrepancy for the weld wire heat No. 86054B is attributed to the conservative assumption used for a copper content of 0.35% in our original analysis.

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! The results of our analyses indicate (see attached Table 1) that the plate No. G-8-6 is still the limiting material in the Oyster Creek reactor vessel (i.e., the ART of the plate No. G-8-6 forms the basis for the Oyster Creek pressure-temperature limits).

Therefore, it is concluded that the new information submitted by BWRVIP has no l

effect on the current Oyster Creek Technical Specification pressure-temperature (P-T)

. curves.

If you have any questions concerning the information provided in this letter, please contact Yosh Nagai, Corporate Regulatory Affairs, at (973) 316-7974.

Sincerely, 2 h

Michael B. Roche Vice President & Director Oyster Creek Attachment cc: Administrator, Region I NRC Project Manager NRC Resident Inspector '

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TABLE 1 Facility: Oyster Cmek Nuclear Generatine Station Vessel Manufacturer: Combustion Engineerine Information requested on RPV Weld and/or Limiting Materials RPV Weld Best- Best- EOLID Assigned Method of Initial RTer ci ca Margin ART or RTor Wire Estimate Estimate Fluence Material Determining RTerm At 32 EFPY Heatm Copper Nickel (x 10) Chemistry CIS Factor (CF) 86054B 0.21 0.05 0.374 96.0 Table 1 -8*F 0 28 56 107 (best estimate) '

86054B 0.35 0.20 0374 168.0 Table 1 -8 F 0 28 56 150 (docketed) 1248 (best 0.21 0.07 0.374 98.0 Table 1 -50 F 0 28 56 66 estimate) 1248 0.22 0.11 0.374 1053 Table 1 -50 F 0 28 56 70 (docketed) i G-8-6* 0.20 0.51 0.374 138.2 Table 2 +31'F 12.7 17 42.4 158 (1) or the material identification of the limiting material as requested in Section 1.0 (1.)

(2) determined from tables in RG 1.99 Rev. 2 or from surveillance data ,

• This plate is still limiting for the Oyster Creek reactor vessel.

Discussion of the Analysis Method and Data Used for Each Weld Wire Heat Weld Wire Heat Discussion 86054B Best estimate from CEOG Report CE NPSD-1039 Rev. 2, June 1997 1248 Best estimate from CEOG Report CE NPSD-1039 Rev. 2, June 1997 Plate G-8-6 Values docketed in GPUN TSCR 245 (8-23-96), approved by NRC as Tech Spec Amendment No. I88 (3-6-97)

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