ML20094S646

Forwards Relief Request 30 Requesting Exemption from Testing Valves DH-11 & DH-12,per Requirements of 10CFR50,App J,Section III.A.1.d & Iii.C.Revised Pages to Inservice Insp Valve Program,Submitted on 800515,also Encl.W/O Rev

ML20094S646
Person / Time
Site:	Davis Besse
Issue date:	08/15/1984
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
1068, TAC-55824, NUDOCS 8408210345
Download: ML20094S646 (3)

Text

o Docket No. 50-346 Totsoo EDISON License No. NPF-3 Serial No. 1068 I[,,N "

uwa August 15, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division. of Operating Reactors United States Nuclear Regulatory Commission .

Washington, D. C. 20555

Dear Mr. Stolz:

Toledo Edison is submitting a Specific Relief Request for the Davis-Besse Nuclear Power Station Unit No. 1, for an exemption from testing valves DH-11 and DH 12, per the requirements.of 10CFR50, Appendix J, Section III.A.l.d and III.C. The attached Specific Relief Request gives the basis for the request.

Transmitted with this letter are five (5) copies of the revised pages to the Inservice Inspection Valve Program for the Davis-Besse Nuclear Power Station, which was submitted on May 15, 1980 (Serial No. 616).

Any additions to the program that become' necessary during the remainder of the 120 month interval, which do not meet the code testing requirements will be implemented as needed. A fully documented notification to the Nuclear Regulatory Commission (NRC) will be placed on the docket subsequent to implementation of the changes.

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Very truly yours, '

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RPC:JDE:SGW:sc/nif cc: DB-1 NRC Resident Inspector Pete Whold, NRC Region III 8408210345 840815 01 PDR ADOCK 05000346 l G PDR -

t THE TOLEDO EDISON COMPANY EDISON PLAZA '300 MADISON AVENUE TOLEDO. OHIO 43652 ,

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Docket Ns. 50-346 License No. NPF-3

, Serial No. 1068 August-15, 1984 Attachment 1 Page.l.of 2 Relief Request Number 30 Components: P&ID M-033 DH-11, DH-12 Function: Decay Heat Removal pump suction isola-tion, containment isolation, and class boundary valves.

Class 1 Testing Requirements: Per 10 CFR 50 Appendix J Sections III.A.I.d a'nd III.C, pneumatic pres-sure testing every refueling outage.

Basis for Relief Request: 10 CFR 50 requires the performance

.of a Type 'C' test on the containment isolation valves of the decay heat removal system. The decay heat. removal system cannot be tested pneumatically

-due to the fact it is required to maintain the plant in safe condition during all modes of plant operation and, therefore, can not be drained and vented to containment atmosphere.

Alternate Testing: Surveillance Test Procedure ST 5066.01,

" Decay Heat Removal System ASME Section XI Inservice Hydro Test", requires valves DH-11 and DH-12 to be water pressure leak tested at 296 PSIG during every refueling outage and hydrostatically tested at 2371 PSIG once every 10 years.

This test is conducted to meet ASME Section XI IWB requirements (2371 PSIG

= 2155 PSIG x 1.10 at < 100*F). Normal operation during plant startup requires opening the valves at 200*F (approxi-mately 200 PSIG) and closing the valves at 280*F (approximately 300 PSIG).

DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Pag ~e _1 of a VAINE TEST PROGitAM i

4 System DECAY HEAT AND EMERGENCY CORE COOLING Drawing No. 033 Rev. 34

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