ML20069G941

Forwards Slide Presentation from 820813 Meeting Re Safety Relief Hydrodynamic Loads.Position Similar to Criteria Outlined in NUREG-0763.Encls Withheld (Ref 10CFR2.790)

ML20069G941
Person / Time
Site:	Perry
Issue date:	10/08/1982
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0763, RTR-NUREG-763 NUDOCS 8210190326
Download: ML20069G941 (2)

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< THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P.o. box $000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLOG. - 55 PUBLICSoUARE Serving The Best Location in the Nation Dalwyn R. Davidson NSTEM E G NEERING AND CONSTRUCTION October 8,1982 Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 PROPRIETARY INFORMATION -

Safety Relief Valve Hydrodynamic Loads

Dear Mr. Schwencer:

This letter documents our meeting of August 13, 1982, and telephone conference call of August 20, 1982, with regard to the safety relief valve (SRV) hydrodynamic loads at the Perry Nuclear Power Plant. In our meeting, we presented the Cleveland Electric illuminating Company (CEI) position that the Kuosheng SRV test data has confirmed the conservative design of the Mark Ill containment for SRV loads and that plant-unique tests of SRV discharges are not required for Perry.

As discussed, the sirrilarity criteria outlined in NUREG-0763, " Guidelines for Confirmatory Inplant Tests of Safety-Relief Valve Discharge for BWR Plants",

indicates that the Kuosheng data is typical and confirmatory for Perry. Inplant testing to be performed by Mississippi Power and Light Company on the Grand Gulf Nuclear Station will further confirm the conservative containment design.

Attached are copies of the meeting slides and presentation by CEI on August 13, 1982. This presentation provided a detailed plant comparison between Kuosheng, Perry, and Grand Gulf relative to the NUREG-0763 requirements for similarity of the discharge device, discharge line parameters, steam flow rates, quencher /

suppression pool configuration and containment structure in the pool region.

In addition, responses to the questions identified in our August 20, 1982, conference call by the Containment System Branch (CSB), Structural Engineering Branch (SEB), and Mechanical Engineering Branch (MEB) reviewers are also attached.

The analysis requested by the Structural Engineering Branch using Kuosheng test data in the Perry containment model is ongoing, and will be provided by November 5,1982.

The information contained in the meeting materials and responses on the Kuosheng testing report is proprietary to the Taiwan Power Company (TPC). This information has previously been submitted as proprietary by TPC to the NRC under the technical exchange agreement between TPC and NRC. The same information has been provided by TPC to CEI under proprietary agreement. We therefore request gl t

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-- % .: - A. Schw:nc r October 8,1982 PROPRIETARY INFORMATION -

Safety Relief Valve Hydrodynamic Loads Page 2 that this information submittal be handled as proprietary in accordance with 10 CFR 2.790. Copies of all attachments have been provided to the CSB, SEB, and MEB reviewers for their use. -

As discussed in our conversations and this submittal, review of the Kuosheng ,

test data supports the conclusion that the data is confirmatory for Perry. Consistent !

with the CSB assessment, that plant-unique tests are not required, it rerr-ins our intent not to perform any additional testing for Perry Nuclear Power int. ,.

' If you have any questions, please let me know. i Very truly yours, -

2 '

Dalwyi R. Davidson Vice President  ;

System Engineering and Construction DRD:mb cc: -Jay Silberg, Esq.

John Stefano Max Gildner -

3. Kudrick L. Yang D. Terao N. Chokshi F. Eltawila 4