ML20043E257

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Forwards Request for Relief 90-01 from Requirements of Section XI of ASME Boiler & Pressure Vessel Code Re Inservice Insp During Second 10-yr Interval
ML20043E257
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 05/31/1990
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006120202
Download: ML20043E257 (6)


Text

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i: s [ Duke har Comparty ! IIAt R han PO Bat 33198 .

Vice President '

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Charlotte, N C 28242 . Nuclear Production

.!. . (701)373 4531 ,

l DUKE POWER May 31, 1990

n U. S. Nuclear Regulatory Commission

~

Document Control Desk' O" .

Washington, DC 20555

Subject:

Oconee Nuclear Station Docket ."!o. 50-269 1 Second Ten Year Interval Request for_ Relief No. 90-01  ;

Gentlemen:

Pursuant to 10CFR 50, 50.55a, please find attached request for relief j number'90-01 from the requirements of Section XI of the ASME Boiler and 1 Pressure Vessel Code (with Addenda through Winter 1980). This request is

-being submitted due to the impracticality of pressure testing specific

-welds as required by the Code following repair. The attached request concerns the inservice' inspection at Oconee Unit I being performed during j the second ten year interval.

Very truly yours,-

), ,s t -

- I .j i 'Hal B. Tucker-4 PJN/122 i rp.

Attachment s i

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                                                        -g o je5 Qeg gy wo mn*     e qc geSB?ie,                                                        j gm                  nc                                        gg 1p

9 bocumentControl'0eskL May 31,-1990 Page 2 i cc: W/0 Diagrans Mr. S. D. Ibneter Regional Administrator U. S~. Nuclear Regulatory-Commission - Region'II 101~ Mariet:a St. NW Suite 290C'- Atlanta, GA 30323

 ",                Mr. L.-A. Wiens Office of Nuclear Reactor Regulation                i U. S. Nuclear Regulatory Commission Washington,.DC -20555 Mr. Heyward Shealy, Chief Bureau of Radiological' Health 7                   S. C. Department of Health and lt                    Environmental Control 2600 Bull Street Columbus, SC. 29201 Mr. P. H. Skinner l                   NRC Resident Inspector-              '

Oconee Nuclear Station l-1. l  ! u r. l ii.

i g .Q-' Duke Power. Company Oconee Nuclear Station Second Ten Year Interval. , L Request for Relief _No. 90-01 i , I. Component for which relief is requested: t (a). Name and Number: Steam Drain (SD) System welds numbers 24 and 25 for installing valve 150-418. L (b) Function: Drains water which collects at the main steam-stop valves. ' (c) ISI Class /Ouke Class: ISI Class B/ Duke Class F , (d)' IWV-2200 Valve Category: B (e) Design pressure: 105gpsig i Design Temp.: 630 F L Material: 1-inch carbon steel, schedule 60 II. Reference Code requirement that has been determined to be impractical: ASME-Boiler and Pressure Vessel Code Section XI, 1980 Edition-(with Addenda through Winter 1980) paragraph IWA-4400(a),'which states that after repairs _by welding on the pressure retaining boundary, a system l hydrostatic test shall be performed in accordance with IWA-5000. III. Basis for reauesting relief: It is.not possible to isolate the subject welds for hydrostatic testing without filling and pressurizing the condenser and associated piping. != IV. Alternate examination: A liquid penetrant examination will be performed and a VT-2 inspection will be performed at operating temperature and pressure. V. Evaluation of acceptability of proposed alternate testing with respect to the level of quality and safety as well as public health and safety: The specified method of hydrostatic testing verifies that there are no leaks at 1.25 times the design pressure. The' alternate examination of 't the penetrant test assures that no significant flaws are evident in the welds. The VT-2 inspection indicates that no leaks are detectable when the' system is at operating temperature and pressure. The alternate tests provide.an equivalent method to indicate a leak at the higher stress

      +_                 level-which is normally verified by the specified method of hydrostatic testing. As such, the proposed alternate examinations provide an acceptable level of quality and safety and will not endanger the health and safety of the public.

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                                      - Alternate examinations will be performed when welding is complete prior)          ';    '
                                      - to startup' from the Unit i end of cycle 13 currently scheduled for June f'                                    6,' 1990.:                                                                               ;

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