ML20062C834

Safety Evaluation Granting Relief from Certain Inservice Insp Requirements of ASME Code,Section Xi,Per 881103 & 890823 Requests

ML20062C834
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/24/1990
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062C833	List: ML20062C829 ML20062C834
References
NUDOCS 9011020169
Download: ML20062C834 (4)

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, / UNITED STATES

["3y @% NUCLEAR REGULATORY COMMISSION g ,c e W ASHING TON, D. C. 20555 g

%,,....*,/ .

i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I T

RELATED_TO THE REQUEST FOR RELIEF FROM ASME CODE. SECTION XI ARKANSAS POWER AND LIGHT COMPANY 4 ARKANSAS NUCLEAR ONE. UNIT NO. 1 DOCKET NO. 50-313 i

1.0 INTRODUCTION

The Technical Specifications for Arkansas Nuclear One. Unit 1, state that the-inservice inspection of ASME Code Class 1, 2 and 3 components.shall be performed in accordance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g),

except where specific written relief has been granted by_the U.S. Nuclear.

Regulatory Comission pursuant-to 10 CFR Part 50, Section 50.55a(g)(6)(i)..  ;

1 An inspection was conducted at Arkansas Nuclear One, Unit I during the periods.

of August 15 through September 2, 1988, in the area of inservice inspection for the second ten-year interval, December 19, 1984 to December 19 1994 The-inspectorsfoundthatalimitedexaminationwasreportedfortheultrasonic examination of the vessel head-to-flange weld. The: examination performed was; a3 proximately fifty percent of that required by the ASME Code because of-oystructions from lifting lugs, the superstructure and flange configuration. 'i Failure to notify the Commission of:the obstructions and the-impracticability . <

to ultrasonically examine the weld to code requirements constituted a' violation a to10CFR50.55a(g)(5)(iii). In addition, paragraph 10 CFR 50.55a(g)(5)(iv) l requires that the basis for the determination-be demonstrated not later than  !

twelve mcnths after the expiration of the in.itia' ten-year period:of plant '

operation.

23, 1939.. Arkansas Power.and BylettersdatedNovember3}1988,andAugust Light Company (the licensce requested relief from certain Section XI ASME Code requirements which are impractical- to conduct at Arkansas Nuclear One,  ;

Unit 1, for the secc.4 ten-year inspection interval.' The-purpose of this- i safety evaluation is to ' view and evaluate the information submitted by the-  :

licensee in-suppott of the 3 terminations.

2.0 EVALUATION _

Thelicenseeidentifiedsixty-one(61)weldsduringtheexaminationsofthe first ten-year-inservice inspection interval that could not be fully examined-to Pursuant'to-10 ASME Code req)uirements CFR 50.55a(g due to different (5)(iii), the Comission was notified types of relief and obstructions.

was ' requested- ,

from the impractical Section XI ASME Code requirements. The requested relief, component and the examination area are shown in Table 1.

Y No? 3 i

2-The detailed reasons cited by the licensee for each of the requested reliefs were stated in the enc'nsures to the subject letters. The inservice inspection ,

requirements are based on the requirements of Sectica XI of the ASME Code,1980 '

Edition, Winter 1981 Addenda.

The staff evaluated the information submitted by the-' licensee and finds that for the majority of the relief requests, where no alternative examination is i proposed, the Code requirements are impractical due to the different types of l obstructions as cited by the licensee. Imposition of the Code requirements fc these cases could result in the redesign, replacement, or relocation of a significant nurber of components and systems at the facility. I For the remaining requests, the existing contour of the welds was cited by the licensee as the reason for performing a 'imited examination. However, the licensee proposes to grind the welds to the proper contour and then perform the required examination. The licensee proposes to perform these activities prior to the end of the second ten-year interval, but still needs relief until these l l

activities are performed. The staff finds that for these cases, imposition of I the Code requirements at this time is impractical as it would require an extraordinary amount of weld grinding to take place in a-short amount of time ,

and may be disruptive to plant operations.  !

3.0 CONCLUSION

l The staff has concluded from its evaluation-that certain examination requirements I of Section XI of the ASME Code, 1980 Edition, Winter 1981 Addenda, are impractical '

to conduct at the Arkansas Nuclear One, Unit 1, facilit Accordingly, the staffhasdeterminedthatpursuantto10CFR50.55a(g)(y.6)(i), granting reliefs .

i from certain examination requirements of the Code, as requested, is authorized l by law and will not endanger life or property or the common defense and security  ;

and is otherwise in the public interest giving due consideration to the burden that could result if the requirements were imposed on the facility.

Dated: May 24, 1990 '

Principal Contributors: F.Litton(EHCB) .

T. Alexion (PDIV) 1 i

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TABLE I REQUESTED RELIEF FOR ANO-1 Relief Request Examination.

Number Component Area 01-001 Reactor Vestei Shell to Flange 01-011 Reactor Vessel Discharge Nozzle to Vessel 01-015 Reactor Vessel Discharge Nozzel to Vessel 02-001 RV Head Head to Flange i 03-004 Steam Generator Nozzle to Head 01-008 Reactor Vessel Longitudinal Shell 01-009 Reactor Vessel Shell to'shell 01-006 Reactor Vessel Shell to shell 01-003 Reactor Vessel Shell to shell 01-005 Reactor Vessel Shell to shell '01-013 Reactor Vessel 01-017 Core Flood Nozzel to Vessel Reactor Vessel Core Flood Nozzel to Yessel 01-012 Reactor Vessel Inlet Nozzle to. Vessel 01-018 Reactor Vessel 01-016 Inlet Nozzle to Vessel i Reactor Coolant Pipe to RIE Nozzle 01-014 Reactor Coalant Nozzle to Vessel 04-006 Steam Generator 04 003 Outlet nozzle to head-Steam Generator Support Skirt to lower head-10-003 Reactor Coolant Pipe to RTE nozzle 04-022 Steam Generator EFW Nozzle-to Tube Sheet 05-010 Pressurizer-05-011 Heater burdle shell Pressurizer Heater burdle shell 05-008 Pressurizer Heater belt shell 05-022 Pressurizer Support lug to shell .05-023 Pressurizer Support lug ~to shell 05-024 Pressurizer Support lug-to shell 05-025 Pressurizer Support' lug to-shell 05-026 Pressurizer Support lug to shell 05-027 Pressurizer Support' lug to shell 05-028 Pressurizer Support lug to shell' i 05-029 Pressurizer Support lug to shell 10-014 RC-Cold Leg Pipe to Steam Generator i l

t 10-011 RC-Cold Leg Ell Inside Longitudinal i

10-010 RC-Cold Leg Pipe:to Ell Cire Seam 10-004 RC-Cold Leg Pipe to pipe Circ Seam- i 11-010 RC-Cold Leg Ell Inside Longitudinal 1 12-013 . RC-Cold Leg ' Ell Inside Longitudinal' 13-011- RC-Discharge Pipe to Ell Circ Seam'13-012 RC-Discharge Ell Inside Long 15-009 RC-Hot Leg Ell to Pipe Circ Seam )

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1 Table 1 Cont'd i

t 15-002. RC Hot = Leg 20-048 Pipe to E11 Circ Seam HP1 to Al Loop Pipe to Valve Circ Sena 23-057 HP1 to B2 Loop 14-023 Ell to Pipe "A" Hot Leg Pipe to Ell 14-024 "A" Hot Leg OR to Elbow Long Seam 23-060 HP1 to BZ Loop 27-019 Elbows to Pipe-Cir  !

Main FW "B" Pipe to albow Cir 28-014 Main Stean "A"28-006 . Pipe to, Reducing Elbow' l

29-038 Main Steaa "A" Pipe to Ell Cire >

Main Stesa ?A"- Pipe to E11 Circ '30-001 Main Stean "B"30-016 Nozzle to Elbow Main Stean "B"- Pipe to Elbow:

31-002 N:in Steam "B"30-023 Elbow to Pipe = ,

Main Stean "B" Pipe to Tee 31-016 Main Steam "B" 34-0T7 Pipe to Elbow LP1 "A" Loop Pipe to Elbow "41-002 DHR Cooler 41-001

• Shellsto Tubesheet DHR~ Cooler Shell to' Head 26-030 Main Feedwater "A"27-011 . Tee to Pipe-Main Feeuwater "B" Ell. to Pipe 30-012 Main Feedwater ,

E11 to Pipe '

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