ML20206D611

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Forwards Relief Request 88-09,requesting Relief from ASME Code Section XI Requirements to Allow Removal & Reinstallation of Safety Injection Sys Piping.Fee Paid
ML20206D611
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 11/11/1988
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8811170152
Download: ML20206D611 (7)
v • d • e


Text

_ _ _ _ _ _.

s' DUKE POWEn Goxiwxy l'A). HOX LKileMI CilAHl.OTT7* NA1. W3u42

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$NEESn November 11, 1988 U.S. Nuclear Regulatory Comission Document Control Desk Washington. 0.C.

20555

Subject:

McGuire Nuclear Station, Unit 1 Docket Nos. 50-369 ASME Code Section XI Requirements Relief Request No. 88-09 Gentlemen:

Pursuant to 10 CFR 00.55a(g)(5)(iii), find attached the subject relief request involving the Unit 1 Safety Injection system. As a result of a modification tc.

the Reactor Coolant system and interference with the Safety injection system,..

soall portion of injection piping was required to be removed and re-installed to complete the modification. As previously discussed with Mr. D. Hood, Project Manager ONRR, it is requested that the NRC review and approve this request prior to the date on which Unit 1 is scheduled to enter Mode 4, Hot Shutdown, (November 30,1988).

Pursuant to 10 CFR 170, an application fee of $150.00 has been included.

Should there be any questions concerning this matter or any consideration by the staff to deny thle request, please contact S.E. LeRoy at (704) 373-6233 as soon as possible.

Very truly yours,

{

fG Hal B. Tucker l

SEL/ relief /sel 1

Attachment

' I\\49 8811170152 881111

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'U.5/ Nuclear Regulatory Commission Relief Request No. 88-09 November 11, 1988 Page 2 xc: Mr. M.L. Ernst Deputy Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 Mr. Darl Hood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulction Washington, D.C.

20555 Mr. P.K. Van Doorn NRC Resident Inspector McGuire Nuclear Station r

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n U.S. Nuc'.:sc Wegulatory Commission November,'

'88 DUKE POWER COMPANY McGUIRE NUCLEAR STATION, UNITS 1 REQUEST FOR RELIEF FROM ASME CODE set, TION XI Ri.QUIREMENTS RELIEF REQUEST NO. 88-09 1.

Component For Which Relief Is Requested:

A.

Name and Number:

Weld Nos. NI244-5, N!244-6, NI244-7, and N!24 8 3.

Function:

Dui,g the implementation of Nuclear Station Modification MG-1-1764, RTO System Deletion / Modification, a portion of the Safety injection (NI) system interfered with the implementation of the modification.

Approximately six (6) feet of the 1.5 inch safety injection branch line supplying injection to the cold leg of the Reactor Coolant Loop 1B fr)m the centrifugal charging pump was removed.

The affected portion of the 1.5 inch line is upstream of check valves INI-17 and 1NI-347 which prevent back flow from the Reactor Coolant system.

Following completion of the modification, the 1.5 inch line will be reinstalled utilizing socket welded full couplings resulting in four welds.

The system configuration is such that an isolation valve does not exist between the replaced section of piping and the Reactor Coolant system.

Hydrostatic testing of the four welds required by Section XI of the ASME Boiler and Pressure Vessel Code has been determined to be impractical. The function of the affected line is to provide a flow path for the injection of borated water into IB Cold Leg of the Reactor Coclant system in the event of a break in either the Reactor Coolant system or the Main Steam system.

C.

ASME III Code Class:

Code Class 2, Duke Class B O.

Materials:

The piping is 1.5 inch schedule 160, SA37C, type 304. The couplings are 1.5 inch 6000 #, SA 182, type 304, 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-4000, Paragraph IWA-4210, Article IWA-5000, and Article i

IWC-5000. These articles require and specify hydrostatic prestere testing of i

pressure boundary components following repairs by welding.

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U.S. Nuclear Regulatory Commission November 11, 1988 Attachment Page 2 3.

Basis For Requesting Reliaf:

There are no isolation valves downstream of the toubject welds up to and including the point at which the injection line ties into the Reactor Coolant system 1B Loop cold leg.

Alternate methods of isolation have been considered but are deemed impractical because they would result in substantial additional work force expenditure, additional personnel exposure, delays to plant start-up, and technical difficulties.

The alternate methods of isolation considered were:

1)

Modify the 1.5~ inch check valve to serve as the Reactor Coolant Loop 18 isolation point.

This alternative method was deemed impracticable because significant technical problems exist with modifying the affected Kerotest check valve for use as an isolation valve in the forward flow direction. Thsse problems include potential valve seat damage from substituted components and the inability to maintain hydrostatic test pressure since the valve would be attempting to contain pressure in a direction it was not designed for. Hydrostatic test pressure would be in excess of 3000 PSIG. The affected 1.5 inch Kerotest valve is in a high radiation area.

Significant work hours in this environment would be required to modify and replace the original components of the check valve with no guarantee of successful valve operation; 2)

Install a manual isolation valve in the injection line to serve as an isolation peint for Reactor Coolant Loop 1B cold leg. This method wu assumed to be impractical since an isolation valve of any type would be welded into place and the welds on the non-hydro side of the isolation

~

valve would also have to tested resulting the same isolation problem;

and, 3) perform hydrostatic pressure testing by placing a freeze plug on the j

line between the affected piping area and the Reactor Coolant loop 1B cold leg. Hydrostatic testing utilizing a freeze plug was considered impossible at the test pressure involved. Alt.o. the possibility of damage to other welds in the area, duc to the expanding ice plug, was a concern.

In conclusion, the only way to perform a hydrostatic pressure test on this section of piping is to pressurize the Reactor Coolant and Safety injection system at the same time, which is deemed impracticable based on tha limited number of Reactor Coolant System pressure tects allcwed, (10 per life of plant).

4.

Alternative Testing:

Duke proposes to perform a liquid penetrant test on all weld root passes and final passes followed by a visual examination. Also, a system inservice lesk test will be performed at system operating pressure and temperature.

's U.S. Nuclear Regulatory Commission November 11,-1988 Attachment Page 3 5.

Why The Alternate Proposed Testing Will Prnvid An A ::ptshl Level of Quality'And Safety:

Liquid penetrant testing of the weld root passes in addition to the normal examinations and inspections required to be performed on ASME Class 2 welds will ensure the integrity of the subject welds.

System inservice leak testing at normal operating pressure and temperature will ensure leak tightness of each new weld.

6.

Implementation:

As previously stated, this work is being performed during the current Unit i refueling outage.

It is requested that this request be reviewed and approved by November 30, 1988. On this date, the unit is scheduled to enter Mode 4, Hot Shutdown.

Should there be any reasons or doubts as to whether the NRC will approve this request, please contact S.E. LeRoy at (704,.

373-6233 as soon as possible.

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