ML20235H099

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Forwards Relief Request 89-01 from ASME Code Section XI Hydrostatic Testing Requirements to Replace Nuclear Svc Water Pumps 1A & 1B Suction Carbon Steel Expansion Joints W/ Stainless Steel Expansion Joints
ML20235H099
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 02/13/1989
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8902230476
Download: ML20235H099 (9)


Text

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DateIbuxr Cornpany HAL B Tudu -

  • PO B<a 33198 Vice President Charlotte, NC 28242 klear Production (704)373-1531 i

DUKEPOWER February 13,.1989-U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555'

Subject:

McGuire Nuclear Station, Unit 1 Docket Nos. 50-369 ASME Code Section XI Hydrostatic Testing Requirements Relief Request No. 89-01 Gentlemen:

Pursuant to 10 CFR 50.55a(g)(5)(iii), find attached the subject relief request involving modification NSM MG-12130 Rev. O, which replaced Nuclear Service Water Pumps 1A and 1B suction carbon steel expansion jeints with stainless steel expansion joints.

The. modification was implemented during the Unit 1 1988 refueling outage prior to seeking relief from the ASME code requirements.

For details concerning this oversight, please' refer to McGuire Licensee Event Report 50-369/88-47.

Also, clease note that a previous request for relief from ASME Hydrostatic testing requirements was approved by NRC when one of the same expansion joints was-replaced in January 1988. The NRC letter transmitting that relief was dated March 14, 1988, and was assigned NRC TAC No. 67032.

Should there be any questions concerning this matter, please contact S.E. LeRoy at (704) 373-6233.

Very truly yours, M

s Hal B. Tucker SEL/ relief 2/sel Attachment Oh I

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U:S.* Nuclear Regulatory Commission Relief.-Request No.89-01

. February 13, 1989 Page 2 xc: Mr. M.L'. Ernst Deputy-Regional' Administrator, Region-II J

.U.S. Nuclear Regulatory Commission-101 Marietta St., NW, Suite 2900.

Atlanta, GA.30323 I

Mr.-Darl' Hood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation

~

Washingt>n,.D.C. -20555 Mr. P.K.1 Van Doorn.

-NRC Resident Inspector McGuire Nuclear Station

U.S..N'u.cle'ar Regulatory Commission Relief Request No. 89-01

-February 13, 1989 Page 3 bxc: A.F. Batts (MNS QA)

C.B. Cheezem (QA)

H.E. Edwards R.L Gill E.

Matthews (CMD ';)

E.0. McCraw (MNS)

P.B. Nardoci R.0. Sharpe (MNS)

.I.S. Warren

' FiC-801.01 l

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c.

U.S. Nuclear Regulatory Commission February 13, 1989-DUKE POWER COMPANY McGUIRE NUCLEAR STATION, UNITS 1 REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS' RELIEF REQUEST NO. 89-01 1.

Component For Which Relief Is Requested:

A.

Name and Number:

Weld Nos. RN1FW24-1 and RN1FW57-1, and flange connections associated with Nuclear Station Modification (NSM) MG-12130 Rev. O, (see drawings attached).

B.

Function:

The Nuclear Service Water system (RN) is a nuclear safety related, Class C system that provides assured cooling water to various station heat exchangers during all phases of plant operation.

In conjunction with Lake Norman and the Standby Nuclear Service Water Pond, the RN system is designed to assure cooling for normal plant operation, and to provide cooling for safe shutdown normally, or as a result of a postulated Loss of Coolant Accident.

NSM MG-12130 involved the installation of new flanges and expansion joints on the suction piping to RN Pumps 1A and 1

18.

The old expansion joints were welded into place and were exhibiting signs of corrosion.

To correct the problems associated with the expansion joints and to facilitate future removal and repair, stainless steel expansion joints and flanges were installed.

The replacement of the expansion joints was also due a recent failure of tne Unit 1 Train B expansion joint that failed due to corrosion and fatigue.

The function of the expansion joints is to reduce nozzle loading on the RN Pump suction casing.

C.

ASME III Code Class:

Code Class 3 D.

Materials:

Piping Elbow - Grade B SA-234 j

Flange

- Grade B SA-105 Type Weld

- Groove Weld 2.

ASME Code Section XI Requirement That Has Been Determined To Be Impractical:

ASME Boiler and Pressure Vessel Section XI, 1980 Edition through Winter 1980 addenda, Article IWA-4400 and Article IWD-5000 1

U.S.*Naclear Regulatory Commission February 13, 1989 Attachment Page 2 3.

Basis For Requesting Relief:

The RN system is a low pretsure, low temperature raw water system.

The piping at the suction side of the RN pumps which includes the new expansion joints has a design pressure of 35 PSIG and a design temperature of 95 degrees-F. The required hydrostatic test pressure for an ASME Class C system is 110% of the design pressure or 38.5 PSIG in this case.

Hydrostatic testing at this pressure has little or no usefulness, or practicality for detecting weld defects, and very little advantage over an in-service leak test for detecting defective flange connections.

Also, the hydrostatic test boundary isolation valves include a 36 inch butterfly valve and an 18 inch butterfly valve on each train. These valves do not offer adequate isolation to accomplish a hydrostatic test using conventional hydro equipment.

Another concern and possibly the most important is the potential for over pressurizing and damaging the bellows assembly on the expansion joints while conducting a hydrostatic test. The expansion joints have a design pressure of 35 PSIG.

For this low pressure section of piping, the alternate NDE specified in Section 4 below was an adequate method of detecting weld and flange defects with no risk of over pressurizing the bellows assembly.

4.

Alternative Testing:

All welding was subjected to a magnetic particle examination on root pass and final weld pass.

An in-service leak test at system pressure and temperature was performed on all welds and flanges.

5.

Why The Alternate Proposed Testing Will Provide An Acceptable Level Of Quality And Safety:

The ASME Code requires only a dye penetrant (PT) or magnetic particle (MT) examination on the finished weld surface for greater than 4 inch NpS. The alternate NDE specified an additional MT on the root pass weld which did not detect any defects in the root weld. The inservice leak test as described above was performed and did not reveal any weld defects or defects in the flange connections.

6.

Implementation:

NSM MG-12130 Rev.0 was implemented during the Unit 1 1988 refueling outage.

Actual implementation dates were between October 25, 1988 and November 16, 1988.

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