ML20052F377

Advises That Sections 3 & 4 of 800515 Revised Inservice Insp & Testing Program Per ASME Boiler & Pressure Vessel Code Section XI of 1977 Edition Through Summer 1978 Addenda Acceptable for Remainder of 120-month Insp Interval

ML20052F377
Person / Time
Site:	Davis Besse
Issue date:	05/05/1982
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Crouse R TOLEDO EDISON CO.
Shared Package
ML20052F378	List: ML20052F377 ML20052F386 ML20052F389
References
TAC-10985, TAC-11316, NUDOCS 8205120400
Download: ML20052F377 (5)

Text

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HAY 5 1982 ISTRTRUIION D'ocket File) dS("C At41 NRG PDR L PDR fEsenu MB Docket No. 50-346 OELD

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Hr. Richard P. Crouse ACRS-10 Vice President, fluclear flECelVED.

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Dear fir..Crouse:

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SUB KCT: REVISED IllSERVICE INSPECTION AND TESTIllG PROGRAM Toledo Edison Company letter of May 15,1980 (flo. 616) submitted a revised Inservice Inspection (and Testing) Program for the renainder of the initial 120 month interval for the Davis Besse Nuclear Power Station. This program was volunt fly revised to be in accordance with the ASME Boiler and Pressu-ssel Code Section X1 of the 1977 Edition through the Summer 19 addenda,

The program is composed of four sections as follows:

Section 1 - Pupp: -

Section 2 e Vilves-Section 3 - Welds (including sup rts, components, and bolting)

Section 4 - Systeu Pressure Tests Program amendments and supplemental infomation were submitted by Toledo Edt' son Company letters dated er 15,1980 (No. 671),

March 31,1981 (No. 702), June 10,181 (No. 715), and February 16, 1982 (flo. 784). The Inservice Ins'iiteti Program, including the referenced supplemental information, was discussed in meetings held with yo>r staff en November 20, 1980 and February 3, 1982.

The NRC staff review of your Inservice Inspection (and Testing) Program referenced above is continuing. Ilowever, the staff review of Section 3 -

Welds (including supports, components. and bolting) and Section 4 - System Pressure Tests is complete.

In Sections 3 and 4. Toledo Edison Company has determined certain ASME code examination requirements to be impractical and has requected relief from performing those examinations. We have evaluated the l

written requests for relief and agree with your detemination that it is impractical for you to meet these requirements. We have detemined that l

life, property or the common defense and security will not be endangered as a result of not perfoming these examinations. We have reached the l

conclusion that relief should be granted as authorized by 10 CFR 50.55a(g)(G)(1).

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s Mr. Richard P. Crouse and that granting such relief, is in the public interest giving due consideration to the burden Toledo Edison Company if the requirements were imposed.

Therefore, pursuant to 10 CFR 50.55a(g)(6)(1), we grant the two written relief requests which relate to:

a) Examination of Reactor Coolant Pumps, P 36-1. P 36-2. P 36-3 and P 36-4 b) Examination of the Control Rod Drive Nozzle Flange Bolts and Nuts With the exception of the to requests for relief from code requirements, our evaluation of Section 3 and Section 4 of Toledo Edison Company's program indicates that examinations are to be perfonned at an extent and frequency that exceeds the minimum requirements of Section XI of the ASME code.

Based on our review of the Inservice Inspection Program, as submitted by Toledo Edison Company and referenced above, we have determined that Section 3 and Section 4 of that program are acceptable for the renainder of the 120-month inspection interval and are in accordance with 10 CFR

50. 55a (g)(4).

We have not completed our detailed review of Sections 1 and 2 of the l

Toledo Edison Company program. The review of these Sections, which relate to the inservice testing of pumps and valves, is scheduled for completion in the near future.

Section 50.55a(g) of 10 CFR 50 requires that your program be revised at 120-month intervals with the start of commercial operation being the reference date. The start of the next interval for your facility is November 21, 1987. Your inservice inspection and testing program must be based on the edition and addenda of the ASME code incorporated by 10 CFR 50.55a(b) 12 months prior to that date. Any changes to ycur Technical Specifications are required to be submitted at least 6 months l

prior to the beginning of a 120-month interval and it is requested that any requests for relief from ASME code requirements be provided on the l

same schedule.

It should be understood that 10 CFR 50.55a(g) does not require NRC approval of your revised program and that the staff review will only address requests for relief from code requirements and Technical Specification changes. Submittal of your revised program is not required unless specifically requested by the staf f to support your relief requests.

It is requested, however, that you provide a summary of the changes from your previous program. The staff review of your relief requests for your next interval will be conducted on a schedule based on the program revision requirements for your facility and is scheduled to be completed by November 21, 1987. Until that time you should follow the inservice inspection program, Sections 3 and 4, l

as proposed by your letters of December 15,1980, March 31,1981, l

June 10,1981 and February 16, 1982, modified as described herein.

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fir. Richard p. Crouse The relief granted herewith supersedes that granted by our letter dated January 3,1979. The relief will remain in effect until llovember 21,1987 unless specifically revoked by the Comission.

The Safety Evaluation Report and a copy of the Federal Register flotice is enclosed.

Singerelyful SI0 G:D By GIGI 30tclE.STopof John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing

Enclosures:

1.

Safety Evaluation Report 2.

Federal Reoister !!otice cc w/ enclosures:

See next page Cw* -Yh& a L<W#

[*See Drevious NRC 318 for concurrence.

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_"gS that granted by our letter dated January 3,y79. The relief.111 romain in effect until flovanber 21, 1987 unless specifically ' revoked.

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Sincerely, WIcnu s1cra g J0ir.i F. STOLZ' i' John F. Stolz, Chief Operating Reactors Beanch #4 Division of Licensing

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Safety Evaluation cc w/ enclosure:

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Toledo Edison Company cc w/ enclosure (s):

Mr. Donald H. Hauser, Esq.

U.S. fluclear Regulatory Commission The Cleveland Electric Resident Inspector's Office Illuminating Ccmpany 5503 fi. State Route 2 P. O. Box 5000 Oak Harbor, Ohio 43449 Cleveland, Ohio 44101 Mrs. Julia Baldwin, Librarian l

Government Documents Collection Gerald Charnoff, Esq.

Shaw, Pittman, Potts William Carlson Library and Trowbridge University of Toledo 1800 M Street, fl.W.

2801 W. Bancroft Avenue Washington, D. C.

20036 Toledo, Ohio 43606 Paul M. Smart, Esq.

-. j Fuller & Henry 300 lbdison Avenue P. O. Box 2083 Reaional Radiation Representative Toledo, Ohio 43603 EP Reaion V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock & Wilcox fluclear Power Generation Division 7910 Woodmont Avenue, Suite 220 Bethesda, flaryland 20814 Ohio Department of Health 4

-l ATTN: Radiological Health Program Director P. O. Box 118 President Board of County Columbus, Ohio 43216 Commissioners of Ottawa County l

Port Clinton, Ohio 43452 l

Attorney General Department of Attorney General 30 East Broad Street Columbus, Ohio 43215 Harold Kahn, Staff Scientist Power Siting Commission i

361 East Broad Street j

Columbus, Ohio 43216 1

Mr. James G. Keppler, Regional Administrator U. S. fiuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

'h Mr. Ted Myers Manager, fluclear Licensing Toledo Edison Company

(

Edison Plaza

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300 Madison Avenue Toledo, Ohio 43652

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