2CAN039103, Forwards Relief Request 1991-4 for First & Second 10-yr Interval for Facility,Per Which Responded to NRC Request for Addl Info on Inservice Insp Program

Forwards Relief Request 1991-4 for First & Second 10-yr Interval for Facility,Per Which Responded to NRC Request for Addl Info on Inservice Insp Program

ML20076N048
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/21/1991
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN039103, 2CAN39103, NUDOCS 9103270181
Download: ML20076N048 (10)

Text

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i March 21,:1991 20ANO39103

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} .U.-~S. Nuclear Regulatory Commission Document Control Desk k Mail;St'ation P1-137 i

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< SUBJECI: Arkansas Nuclear One - Unit 2 y'

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Docket-No. 50-368 License No..NPF-6 D .-Additional Relief Request for the i l' Tirst' ard Second Ten-Year Intervals

'i g: . Gentlemen:

i Iniletter'2CAN019103,. dated ?anuary 15, 1991, Entergy Operations submitted the responses to the NRC's request for = additional information Lon'thecInservico Inspection.L(ISI) program for Arkansas Nuclear One, Unit

.-2 (ANO-2). ,In that submittal Entergy Operations also provided relief u

requ'ests for the ; first ten-year -inspection interval. Entergy Operations

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has deterwAned - that an . additional- relief-. request for the first- and l

second ten-year Einspection. intervals ;for - ANO-2 is ' required. The purpose l_ -of'thisr_lotter in to submit thisiaoditional relief-request.

i L Thisrelijfrequestisrequired-_in_accordancewith10CFR50.55a(g)with l- respect to-the= inspection of.;a valve body internal' pressure boundary.-

b The~ relief request.is provided in;thelettachment. .t Should you have any questions regoriing-this- issue, pinase contact me.

Very truly yours,:

1

. . . . i g

L 7 Jame. J. Fisicaro. .i Manager,fLicensing .

![-i OJF:RWC:sgw-L Attachment l

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1 9103270181 910321 l PDR- ADOCK 05000368 Q PDR >

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'- U. S. NRC March 21, 1991 Page 2 t cc: Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arkansas Nucicar One - ANO-1 & 2 Number 1, Nuclear Plant Road' Russellville, AR 72801 Mr. Thomas W.-Alexion

-NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 11-D-23 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Ms. Sheri Peterson >

NRR Project Manager,-Region IV/ANO-2 U. S. Nuclear Regulatory Commission

- NRR Mail' Stop 11-D-23 One White Flint North 11555 Rockville Pike

Rockville, Maryland 20852

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A'fTACIIMENT RELIEF REQUEof 1991-4 FOR Tile FIRST AND SECOND TEN-YEAR INTERVAL FOR ANO-2 a

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1 ANO-2 Relief Roquest 1991-4 COMPONENT NUMBER:

Valvo 281-19 COMPONENT DESCRIPTION:

8", 15000, Manual pressuto seal sato valve Manufactured by Volan Engineering Companies Forged stainlese steel body, SS F-316 ASME Class 1. N-1, ASME Section III design Seismic Class 1 Machined to match Schedule 120 pipo Design pressurs: 2465 psig Design temperature: 700 degrees F Velan drawing P2-1528-N-1 (attached)

EXAMINATION CATEGURY:

1. Tables IWB-2500 and IWB-2600, Category B-M-2 Item B6.7, Valvo Bodies (1974, Summer 1975)

2. Tabic IWB-2500-1, Category B M-2 Item B12.50 Valvo Body, Exceeding NPS 4 (1986 Code)

CODE CLASS:

C16ss 1 APPLICABLE ASME CODE SECTION XI EDITION AND AUDENDA:

1974 Edition with Addenda through Summer 1975 (First 10-Year interval March 26, 1980 to March 26, 1990) 1986 Edition (Second 10-Year Interval March 26, 1990 to March 26, 2000)

EXAMINATION REQUIREMENT:

One valvo in each group of valves of the ser constructional design, e.g., globo, gate, or check valve manufactur ug method and manufacturer that performs similar functions in the syst m shall be examined during each inspection interval. Tbo areas shall include the internal pressure boundary surfaces, on valves exceeding 4 inch nominal pipe size.

' BASIS FOR REblEF:

Valve 281-19 provides for draining the refueling canal into the common return line to the suction of the shutdown cooling / low pressure safety injection pumps. It also serves as the class break between the Class I reactor coolunt system and the Class 3 fuel pool system, and is a teactor coolant pressure boundary as defined in 10CFR50.2 (the second of two valves normally closed during normal reactor operation in system piping which does not penetrate primary teactor containment). The system piping configuration is shown on H-2232, coordinates F-6, and H 2235, coordinates A-7, en the at t ached drawings. A simplified piping diagram is also provided.

Valvo 2SI-19 is in an ASME Section XI valve group, with a population of only one valve; therefore, there are no similar valves installed in a Class I system in AND-2. This valve must be in service (closed) during conditions requiring shutdown cooling to isolate shutdown cooling from the refueling canal. it must also remain closed during the refueling activities to prevent draining the refueling canni, in order to dinnssemble this valve for visual inspection of the internal pressure boundary surface, the platit would have to be placed in an undesirabic condition. The reactor would have to be defueled such that shutdown cooling would not be required, and the refueling cannt would have to be drained. As described in the ANO-2 Safety Analysis Report, Section 9.1.4.3.2, during refueling activities, the refueling canni is flooded for both fuel movement and for temporary storage and shielding of the reactor internal upper guide structure. It would cause a considerable hardship to suspend all activities in t he containment building for draining of the refueling canni during defueling. This could possibly entall reinsert ion of the upper guide structure into the vessel to allow for draining the canni, greatly impacting outage schedules. This level of effort is not warranted to perform an inspection of a valve which has displayed no degradation.

The valve cannot be disassembled during startup or shutdown when the plant is above the reactor coolant pressure (300 pain) when shutaswn cooling is not required because of the design bases of the tenctor coolant pressure boundary. This valve was classified as a " Category f." valve under the 1974 Edition of the ASME code. This valve is required to be locked closed prior to plant hentup above 200 degrees F. Therefore, the plant conditions required for disassembly of this valve during hentup or cooldown with the reactor coolant system temperature within the pressure and temperature limit.s of the Technical Specifications, and above the shutdown cooling pressure (300 psin), are prohibited. Disassembly of this valve would violate Design Critorion 15 of 10CFR50, Appendix A.

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Alternatively to valve internal inspection, a repetitive task for preventive maintenance (pH) purposes provides for cleaning and lubrication of the valve stem, and inspection of the valve for leakage at a regular  ;

frequency determined by the pH engineering group. There has been no j evidence of valve body pressure boundary leakage during these inspections. l In the 1988 Addenda to Section XI, the requirement to disassemble pump and valves solely for the purpose of performing examination of the internal pressure boundary autface was deleted by requiring examination only when a pump or valve is disassembled for maintenance, repair, or volumetric examination. This valve does not require volumetric examination; therefore, the only time it would be disassembled would be if a maintenance or repair activity were required for the valve internals.

Relief is requested for the first and second 10 year inspection intervals for 2SI-19, based on the limiting conditions required for disassembly of the valve and on the later changes to Table IWB-2500-1 Category B-H-2, Item 212.50. Footnote 2, requiring examination only when disassembled for other purposes. This will prevent placing the plant in undesirable or prohibitive conditions for the sole purpose of inspection. If, at any time

-in the future, the valve requires disassembly for maintenance or repair, an inspection of the valve body internal pressure boundary will be nerformed.

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• t simplified Piping Diagram Refueling Canal l

Prom RCS C2CV-5084-1 Class 3/ Class 1 i

2SI-19 7

2CV-5086 .1 To LPSI/SDC Pumps i

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