ML20115J071

Requests Withdrawal of Specific Relief Request 30 Re Open Item 50-346/80-19-03 Concerning DHR Sys Line Valves DH-11 & DH-12.Exemption to App J Type C Testing Already Provided for Valves DH-11 & DH-12

ML20115J071
Person / Time
Site:	Davis Besse
Issue date:	04/15/1985
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
1138, TAC-55824, NUDOCS 8504230363
Download: ML20115J071 (2)

Text

p-g c TOLEDO EDISON Docket.No. 50-346 , RICHAn] P. CROUSE Vce Presdert License No. NPF-3 )$$499g Serial No. 1138 April 15,_1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactot Branch No. 4 Division of Licensing United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear 'M r. Stolz:

Toledo Edison (TED) submitted Specific Relief Request No. 30 (Serial No. 1068) to the NRC on August 15, 1984, for the Davis-Besse Nuclear Power Station Unit No. 1 in response to Open Item 50-346/80-19-03 in Inspection Report 80-19 dated August 12, 1980. This open item concerned testing of Decay Heat Removal (DHR) System line valves DH-11 and DH-12 on Penetration 29 per the requirements of 10 CFR 50, Appendix J, Sections III.A.1.d and III.C. This item was identified as unresolved pending the submittal by TED of a request for an exemption from testing those valves to Appendix J.

Further review of this open item by TED identified that DH-11 is specifically exempted from Type C testing per Technical Specification 3/4.6.3 (Table 3.6-2). Valve DH-12 is not a containment isolation valve and, therefore, also exempt from the Type C testing requirements of Appendix J.

In a telephone conference call on February 28, 1985, with TED represent-atives, Mr. A. W. DeAgazio of your staff and Messrs. L. Reyes and F. Maura of NRC Region III concurred that valves DH-11 and DH-12 are exempt from Type C testing requirements of Appendix J, Sections III.A.I.d and III.C.

However, to ensure that the integrity of the DHR System line is maintained as an extension of the containment boundary, TED has revised Surveillance Test procedure ST 5051.03, Low Pressure Injection and Containment Spray Systems Leak Rate Test, to include visual inspection and significant leakage measurement of the portion of the DHR System line from the external containment wall to valves DH-1517 and DH-1518 located outside of containment.

' Valves DH-1517 and DH-1518 are included in the leakage testing under Surveillance Test procedure ST 5051.03. ST 5051.03 is conducted pursuant to Technical Specification 4.5.2.d.3 which limits Decay Heat Removal System leakage to 20 gallons per hour.

8504230363 850415 8

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PDR ADOCK 05000346 i G PDR 0 THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. DHIO 43652

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Dockat No. 50-346 Lic:nr2 Ns. NPF-3 Serial No.'1138 April 15, 1985 ,

Page 2 Therefore, since an exemption to Appendix J Type C testing is already provided to valve DH-11 by Technical Specification 3/4.6.3 and valve DH-12 is not subject to Type C testing, Toledo Edison requests that its Specific Relief Request No. 30 be withdrawn from the NRC.

Very truly yours.

R P WQ RPC:DRW:SGW:lah cc: DB-1 NRC Resident Inspector