1CAN028501, Forwards 10-yr Inservice Insp Program Relief Requests Re ASME Class I Components

Forwards 10-yr Inservice Insp Program Relief Requests Re ASME Class I Components

ML20106C184
Person / Time
Site:	Arkansas Nuclear
Issue date:	02/04/1985
From:	Enos J ARKANSAS POWER & LIGHT CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
1CAN028501, 1CAN28501, NUDOCS 8502120165
Download: ML20106C184 (5)

Text

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ARKANSAS POWER & LIGHT COMPANY I POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72PD3 (501) 371-4000 February 4, 1985 1CAN028501 Director of Nuclear Reactor Regulation ATTN: Mr. J. F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51

'ANO-1 Second 10-Year Inservice Inspection Program Relief Request Submittal Gentlemen:

'Our letter dated January 31, 1985, (ICAN018507) indicated that we would transmit the relief requests for the ANO-1 second 10 year Inservice Inspection Program under separate cover. Our requests for relief are enclosed with this letter.

Very truly yours, J. Ted Enos Manager, Licensing JTE:DET:ds Attachment 8502120165 850204 ~ 0 0 PDR ADOCK 05000313 g ,

G PDR MEMBEA MtOOLE SOUTH UTILITIES SYSTEM

ATTACHMENT TO 1CAN828581'

.ASME CLASS I COMPONENTS NDE INSERVICE INSPECTION RELIEF REQUESTS FOR ANO-1 BASED ON ASME'SECTION XI-1980 CODE;THROUGH WINTER 1981 ADDENDA IMPRACTICAL IWB-2500-l' EXAMINATION SYSTEM OR AREA TO BE CODE REASON FOR LICENSEE PROPOSED ITEM NO. CATEGORY ' COMPONENT EXAMINED REQUIREMENT- REQUEST ALTERNATE EXAMINATION B5.10 B-F Reactor Two Core Surface Access would require removal None .These welds will Vessel Flood Safe Examination of the canal seal plate, be examined 100% from End Butt- of Safe End- shielding bricks, shielding the I.D.

Welds; Weld Circumferen- supports in the nozzle areas, Nos.01-025 tial: Butt and insulation removal. This and 01-026. Welds. would. require approximately 300 manhours of. cork in a 700-1000 mR/hr area.

B9.11 .B-J Reactor Two. Inlet Surface Access would require removal None - These welds will Vessel Nozzle to' Examination of the canal seal plate, be examined 100% from Pipe Circum- .of Inlet shielding bricks, shielding the I.D.

ferential Nozzle to supports in the nozzle areas,

' Butt Welds; . Pipe Circum- and insulation removal. This Weld Nos. 'ferential would require approximately 019.and Butt Welds. 300 manhours of work in a 01-022. 700-1000 mR/hr area.

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' ATTACMENT TO 'ICANf285fl..(Continued) . -

, ASME CLASSil COMPONENTS NDE INSERVICELINSPECTION' RELIEF REQUESTS

. FOR ANO-1-BASED ON ASME SECTION XI-1980

' CODE THROUGH WINTER 1981 ADDENDA- ,

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. IMPRACTICAL" IWB-2500-1' EXAMINATION SYSTEM OR' 0 AREA TO BE CODE ' REASON FOR LICENSEE PROPOSED.

< ITEM NO. CATEGORY COMPONENT EXAMINED REQUIREMENT' REQUEST ALTERNATE EXAMINATION 89.11 B-J Piping Circumferen - 'The= area of High-pressure injection welds None -

Pressure _ , tial-: Pipe ~ .

examination 200-008A,'21-026,!22-024A Boundary :  : Welds: High~ shall'in-~. and 22-027A'.are inside pene-Pressure clude'100% trations Nos. 13, 34, 8 and

-. Injection . of the weld 15 respectively in the shield Lines; Weld . length. --

wall'and are not accessible.

4 Nos. 20-008A for examination. Core flood 21-026,- welds 19-0198 and 19-021A are 22-024A and inaccessible for examination

22-027A. Core- due-to pipe supports. Theste

- flood lines;. welds were not examined during weldinos. baseline and this face is 119-0198land: . documented in the preopera-

.19.021A. ational inspection report.

B12.10 B- L-l ' Reactor .

Pressure' . Volumetric: Pump Casing internal surfaces ' Volumetric: Approxi-

. Coolant. Pump- ; Retaining :100% of the' Lare inaccessible without' mately 95% of the Pressure, Weldslin pressure ~ dismantling the pump'. .

pressure retaining weld Boundary. Pump Casings retaining in at.least one pump

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weld in at in the 120 month least-one inspeciton interval.

l pump in-the .

120 month in-spection interval.

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ATTACHMENT TO ICAN028581 (Continued) d ASME. CLASS I COMPONENTS NDE INSERVICE INSPECTION RELIEF REQUESTS

.FOR ANO-1 BASED ON ASME'SECTION XI-1980

. CODE THROUGH WINTER 1981. ADDENDA

. . IMPRACTICAL IWB-2500 EXAMINATION.-SYSTEM OR AREA TO BE CODE REASON FOR LICENSEE PROPOSED' ITEM NO. CATEGORY ' COMPONENT- EXAMINED REQUIREMENT REQUEST ALTERNATE EXAMINATION ,

B12.20 B- L-2 Reactor Pump Casing Visual Pump casing internal -Partial. surface repli-

. Coolant Pump Internal- surfaces are inaccessible cation obtainable from Pressure Pressure without. dismantling the pump. casing weld volumetric Boundary Boundary. examination.

Surfaces.

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