ML20138K757

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Grants Request for Withdrawal of 840815 Inservice Test Relief Request Re Testing of DHR Sys Line Valves DH-11 & DH-12.Test Procedure ST 5051.03 Modified to Include Visual Insp & Leakage Measurement of DHR Sys Line
ML20138K757
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 10/18/1985
From: Stolz J
Office of Nuclear Reactor Regulation
To: Williams J
TOLEDO EDISON CO.
References
TAC-55824, NUDOCS 8510300294
Download: ML20138K757 (2)


Text

. ,, OCT 181985 Docket No. 50-346 -DISTRIBUTION (Docket File JPartlow GEdison NRC~PDR - ACRS-10 KRidgway Mr. Joe Williams, Jr. L PDR RIngram Vice President, Nuclear ORB #4 Rdg ADeAgazio Toledo Edison Company HThompson~ Gray File Edison Plaza - Stop 712 OELD EBrach 300 Madison Avenue EJordan H0rnstein Toledo, Ohio 43652 BGrimes WPaulson

Dear Mr. Williams:

SUBJECT:

WITHDRAWAL 0F IN-SERVICE TEST RELIEF REQUEST N0. 30 - DAVIS-BESSE NUCLEAR POWER STATION In response to Open Item 50-346/80-19-03 in Inspection Report 80-19 (August 12,1980), Toledo Edison Company (TED) submitted a request for exemption from certain requirements of Appendix J to 10 CFR 50 on August 15, 1984 (Serial No. 1068). This item concerned testing of Decay Heat Removal System lfne valves DH-11 and DH-12 on Penetration 29 per the requirements of 10 CFR 50, Appendix J, Sections III.A.I.d and III.C. Further review of this open item 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.

i Although the valves are exempt from the Type C testing requirements of Appendix J, the exemption requires a demonstration that the integrity of the DHR System line is being maintained. Consequently, Toledo Edison Company has modified 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.

We have reviewed the applicable part of ST 5051.03 and consider it to be acceptable. Consequently, thq TED request that the relief request be withdrawn is granted.

Sincerely, ecc:c n.", m:w LT JU. .A. M % :.*

John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing cc: See next page ORB #4:DL/7/k OR L ADeAgazid;cr JSto s 10//p/85 10/ /85 8510300294 851018 PDR ADOCK 05000346 P PDR

I F Mr. J. Williams Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. 1 cc:

Donald H. Hauser, Esq. Ohio Department of Health The Cleveland Electric ATTN: Radiological Health Illuminating Company Program Director P. O. Box 5000 P. O. Box 118 Cleveland, Ohio 44101 Columbus, Ohio 43216 Mr. Robert F. Peters Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General Edison Plaza 30 East Broad Street 300 Madison Avenue Columbus, Ohio 43215 Toledo, Ohio 43652 Mr. Janes W. Harris, Director Gerald Charnoff, Esq. Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Relations and Trowbridge 2323 West 5th Avenue 1800 M Street, N.W. P. O. Box 825 Washington, D.C. 20036 Columbus, Ohio 43216 Paul M. Smart, Esq. Mr. Harold Kohn, Staff Scientist Fuller & Henry Power Siting Commission 300 Madison Avenue 361 East Broad Street P. O. Box 2088 Columbus, Ohio 43216 Toledo, Ohio 43603 Mr. Robert B. Borsum President, Board of Babcock & Wilcox Ottawa County Nuclear Power Generation Port Clinton, Ohio 43452 Division Suite 200, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission 5503 N. State Route 2 Oak Harbor, Ohio 43449 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road .

Glen Ellyn, Illinois 60137

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