ML20065C688

Forwards Relief Request Re Third Interval ASME Section XI Pressure Test Program

ML20065C688
Person / Time
Site:	Point Beach
Issue date:	03/29/1994
From:	Maxfield G WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PBL-94-0109, PBL-94-109, NUDOCS 9404050296
Download: ML20065C688 (4)

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' POWER COMPAOY -

Point Bco 5 Nuclear Plant 6610 Nu.;lo or Rd, Two Rivers. WI $4241

-(414) 755-2321 PBL 94-0109 t

' March _29, 1994 U. S.

NUCLEAR REGULATORY COMMISSION Document Cvntrol Desk Mall Station P1-137 Washington, DC 20555 Gentlemen ppCKETS 50-266 AND 50-301 ASME SECTION XI PRESSURE TEST PROGRAM

' REQUESTS FOR RELIEF POINT BEACH NUCLEAB_ PLANT UNITS 1 AND 2

Enclosed-is a request for relief associated with our Third Interval ASME Section XI Pressure Test Program.

Following telephone discussions on March 28,-1994, between-our. engineering; personnel and members of your staff, we have prepared a specific' request'for upcoming modificationc~to our Main Feedwater System. These ' modifications are':-

intended to enable series check valves CS-00466 AA&BB and CS-00476'AA&BB to be leak tested independently, and are scheduled to be' accomplished during our upcoming Spring 1994 refueling outage _on Unit 1, and during'our Fall.1994-

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refueling outage on Unit 2.

Should you have any questions or require any additional information'regarding-this matter, please do not hesitate to contact us.

Sincerely, e

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G.'J.

field LPlant Manager DEK/ caw i

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4 RELIEF REOUEST PTP-3-04 COMPONENTS:

ASME Class 2 EB-9 Main Feedwater Piping (Units 1&2), associated with Point Beach ;

Modifications 89472 (Unii 1) and 89-073 (Unit 2),

DRAWINGS:

M-202 Sh 2 (Unit 1)

M 2202 Sh 2 (Unit 2)

ASME SE(TON XI REOUIREMENT:

IWA-5214 REPAIRS AND REPLACEMENTS (a)

A component repair or replacement shall be pressure tested prior to resumption of service if required by IWA-4400 and IWA-4600.

(b)

The test pressure and temperature for a system hydrostatic test subsequent to the component repair or replacent nt shall comply with the system test pressure and temperature specified in IWB-5222, IWC-522 2, and IWD-5223, as applicable to the system which contains the repaired of replaced componnt.

IWC-5222 SYSTEM IIYDROSTATIC TEST 1

(a)

The system hydrostatic test pressure shall be at least 1.10 times the system pressure P I f 8788858 u

with Design Temperature of 200*F or less, and at least 1.25 times the system pressure P for systems e

with Design Temperature above 200*F. The system pressure P shall be the lowest pressure setting g

- among the number of safety or relief valves provided for overpressure protection within the boundary --

of the system to be tested. For systems (or portions of systems) not provided with safety or relief valves, the system design pressure P shall be substitute <' for P -

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PROPOSED ALTERNATE REOUIREMENT:

(a)

A pressure test at nominal operating pressure shall be acceptable in lieu of the hydrostatic test oflWC-5222 following modifications to the specified main feedwater piping.

(b)

Prior to puforming VT-2 visual examination, the system shall be pressurized to nominal operating pressure for a minimum of 10 minutes. The system shall be maintained at nominal operating pressure during the performance of the VT-2 visual examination. The pressure retaining portions of the component which has undergone repair or replacement shall remain uninsulated until the VT-2 visual examination is completed.

(c)

In addition to the pressure test specified in (a) above, a surface examination of the final weld pass shall be performed on all socket welds which are part of the modification. Surface examinations of the root weld pass and final weld pass shall be performed on all full penetration welds joining socket-weld pipets (see figure 1) to the 16 inch ASME Class 2 EB-9 main feedwater piping.

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BASIS FOR RELIEF:

Modifications89-072 (Unit 1) and 89-073 (Unit 2) install bypass assemblies around main feednater series check valves CS-00466 AA&BB and CS-00476 AA&BB (4 valves per unit) to permit these components to be leak tested independently.' Each check valve is provided with a 2 inch bypass assembly (see figure 2), which consists of 2 socket-weld pipets providing attachment to the 16 inch ASME Class 2 EB-9 main feedwater piping and approximately :

nine other 2 inch components connected at socket welded joints.

Main feat vater piping and components within the ASME Claw 2 boundary are not isolable from their respective steam genervors.

• hydrostatic test performed in accordance with IWC-5222 following completion of the bypass assembly for any mae fvr awater check valve would also necessitate hydrostaticclly testing the associated steam generator, which is not practical. Use of volumetric NDE methods to examine the welds associated with the bypass assembly is also not practical because of either the size or joint type. Consequently, the pressure test and surface examinations outlined in the Proposed Alternate Requirement section above constitute the only practical alternative.

STATUS:

Awaiting NRC Response.

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