PY-CEI-NRR-2312, Forwards Response to NRC 980504 RAI Re RPV Integrity at Pnpp,Per GL 92-01.Encl Contains Tables Re RPV Weld & Plate Matl re-evaluation of Bounding Assessment

Forwards Response to NRC 980504 RAI Re RPV Integrity at Pnpp,Per GL 92-01.Encl Contains Tables Re RPV Weld & Plate Matl re-evaluation of Bounding Assessment

ML20237B882
Person / Time
Site:	Perry
Issue date:	08/04/1998
From:	Myers L CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, PY-CEI-NRR-2312, TAC-MA1205, NUDOCS 9808200049
Download: ML20237B882 (3)

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! Perry Nuclear Power Plant P ox 9 m Perry Ohuo 4408I W ',

Lew W. Myers 440-280-5915 Vice President Fat 440-2808029 August 04,1998 PY-CEl/NRR-2312L United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Perry Nuclear Power Plant Docket No. 50-440

' Response to Request for Additional Information Regarding Reactor i Pressure Vessel Integrity (TAC NO. MA1205) I l

Ladies and Gentlemen:

The response to a Request for Additional Information (RAI) regarding reactor pressure vessel ,

(RPV) integrity at the Peny Nuclear Power Plant (PNPP) is attached. The RAI was forwarded by l letter dated May 4,1998. Attachment 1, Tables 1 and 2, contain the requested information on l RPV weld and plate material, l The RAI requested re-evaluation of the bounding assessment in the response to Generic Letter 92-01. The assessment concluded that one weld wire heat in the RPV beltline region was the limiting material. The weld data in Table 1 is the same as the PNPP weld data presented in Table 6-1 of a letter dated February 18,1997 (PY-CEl/NRR 2129L),"Results of Reactor Vessel Material Specimens Pursuant to 10CFR50, Appendix H". The os and oa values, as determined  ;

using Regulatory Guide 1.99, Revision 2, were added to complete the table. The re-evaluation, I completed by the General Electric Company, confirms that previous evaluations remain valid. l The bounding heat of material used in producing the Pressure-Temperature curves (submitted by letter dated August 28,1997(PY-CEl/NRR-2206L)) has not changed. No additionallicense amendments or assessments are necessary.

Table 2 is included in order to provide the ci and oavalues for the plate material. Although these values were not specifically requested by the NRC, they are provided to complete Table 6-1 of the letter dated February 18,1997.

No commitments were generated as a result of this letter or its attachment. If you have

/l questions or require additional information, please contact Mr. Henry L. Hegrat, Manager -

Regulatory Affairs, at (440) 280-5606. g Very truly yours, Attachment _ .t y92 cc: NRC Project Manager NRC Resident inspector f NRC Region lll l

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