ML20062J776

Requests,Per GL 90-05,relief from ASME Boiler & Pressure Vessel Code Section XI Requirements.Description of Actions Taken by Util to Make Temporary non-code Repairs to Leak in SWS Line 1801-6-153-3 Encl

ML20062J776
Person / Time
Site:	Seabrook
Issue date:	11/12/1993
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-90-05, GL-90-5, NYN-93156, NUDOCS 9311170255
Download: ML20062J776 (21)

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P.O. Box 300

-M 4 Seabrook, N H 03874 Telephone (603)474-9521

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Facsimile (603)474-2987 Energy Service Corporation Ted C. Feigenbaum Senior Vice President and

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4 Chief Nuclear Officer NYN-93156 I

I November 12,1993 l

United States Nuclear Regulatory Commission Washington, D.C. 20555

.f Attention:

Document Control Desk

References:

(a)

Facility Operating License No. NPF-86, Docket No. 50-443

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I (b)

NRC Generic Letter 90-05 " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Piping", June 15,1990

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Subject:

Relief Request From ASME Code Section XI Requirements I

Gentlemen:

i North Atlantic Energy Service Corporation (North Atlantic) hereby requests, pursuant to NRC

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Generic Letter 90-05, relief from the ASME Boiler and Pressure Vessel Code Section XI requirements l

pursuant to 10CFR50.55a(g)(6)(i). Attachment 1 provides a description of actions taken by Nonh Atlantic

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to make temporary non-code repairs to a leak in the Service Water System (SW) line 1801-6-153-3". The SW System is a Class 3, moderate energy system. The non-code repair, a sof1 rubber gasket secured with a mechanical clamp, was completed at approximately 8:00 pm on November 11, 1993. This repair j

successfully isolated the leak.

-l The affected 3 inch line is one of three pressure sensing lines downstream of the two Train A i

ocean SW pumps. Attachment 2 identifies the leak location which is at a weldolet to flange shop weld.

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The cooling tower actuation logic (2/3) in each SW Train senses ocean SW pump discharge pressure. A l

low pressure condition, indicative of a low-low SW pumphouse level, will initiate cooling tower actuation I

for the associated SW Train. The cooling tower actuation logic and function are unaffected by the non-l code repair.

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The leaking SW pressure sensing line cannot be isolated to perform a code repair. A code repair l

on this line would require panial draindown of SW Train A, resulting in the inoperability of the 2 ocean i

SW pumps and the cooling tower SW pump within this train. The inoperability of an utire SW Train

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is not allowed by the requirements of Technical Specification 3/4.7.4 " Service Water System" and thus entry into Technical Specification 3.0.3 would be required and a plant shutdown would ensue.

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Consistent with the provisions of Generic Letter 90-05, Nonh Atlantic is submitting this relief l

request for a temporary non-code repair. Code repair of the degraded piping will be completed during i

the next outage exceeding 30 days but not later than the next refueling' outage which is scheduled to begin

.l in March 1994. The Resident inspector for Scabrook Station, Mr. Richard Laura, was notified of this i

repair.

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9311170255 931112 l'

I PDR ADOCK 05000443 l

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I United States Nuclear Regulatory Commission November 12,1993 Attention:

Document Control Desk Page two l

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Should you have any questions regarding this letter, please contact Mr. Terry L. Ilarpster, Director

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of Licensing Services at (603) 474-9521 extension 2765.

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Very truly yours, j

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/1 led C. Feigenbdum_

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TCF/ALL:sm Enclosure 4

cc:

Mr. Thomas T. Martm i

Regional Administrator U.S. Nuclear Regulatory Commission Region !

l 475 Allendale Road King of Prussia, PA 19406 l

l Mr. Albert W. De Agazio, Sr. Project Manager l

l Project Directorate 1-4 i

Division of Reactor Projects U.S. Nuclear Regulatory Commission i

Washington, DC 20555 3

Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 i

Seabrook, Nil 03874 t

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November 12,1993 l

NYN-93156 i

REllEF REOUEST FROM ASME CODE SECTION XI REOUIREMENTS l

Brown, B. E.

01-62 Cliche, R. R.

01-62

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DiProfio, W. A.

49-SS Garfield, G.

DB&ll Kacich, R. M.

NUSC Kline, G. J.

02-08 Sobotka, J. E.

49-CE Vargas, J. M.

01-62 Executive Offices 01-40 LIC Routing Offices 01-48 Subject File 01-48 j

File 0001 01-48 RMD 02-06 i

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SEABROOK STATION 1

FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 1

i SIR # 93-099 DATE 11/11/93 TIME: Approx. 2:00 a.m.

1.0 ORIGINATOR l

1.1 DESCRIPTION

OF FLAW i

There is thru wall flaw causing leakage on line 1801-6-153-3". The leak is at a shop weld between the weldolet and flange upstream of valve SW-V48 and SW-PT8273.

i The flaw has an approximate dimension of %" x %".

This location on the Service Water "A" train is in a well drained pit, el. 4*-0", in the Service Water Pumphouse.

Piping / Component Drawing No.:

j The weldolet and flange are carbon steel with 1/8" thick cement lining as detailed on sketch 804998 of specification 248-2 (Refer to Attachment 2).

F P&ID No.:

l-SW-B/D20794 i

1.2 IMPRACTICALITY OF CODE REPAIR I

The leaking SW pressure sensing line cannot be isolated to perform a code repair. A -

code repair on this line would require partial draindown of SW Train A, resulting in j

the inoperability of the 2 ocean SW pumps and the cooling tower SW pump within this train. The inoperability of an entire SW Train is not allowed by the requirements of Technical Specification 3/4.7.4 " Service Water System" and thus entry into Technical Specification 3.0.3 would be required and a plant shutdown would ensue.

1.3 DESCRIPTION

OF PROPOSED TEMPORARY REPAIR A soft rubber gasket with mechanical clamp will be used.

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1.4 SAFETY SIGNIFICANCE: System Interaction Evaluation i

Flooding:

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There is a leak of approximately 2% gpm coming from the %" x %" thru wall flaw at f

the 3 inch shop weld described above. Ultrasonic Examination has confirmed there to l

be no additional degradation at this shop weld.

The leakage is well contained within the SW pumphouse " pit area" and more than j

adequate drainage capability exists to preclude flooding.

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j SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS i

Jet Spray:

There are no safety related power supplies or equipment that could be disabled as a result of the jet spray from this flaw. The leakage and spray is well contained in the i

SW pumphouse " pit area", el. 4'-0", approximately 15 feet below any equipment of this type.

Loss of Flow-Loss of SW thru this flaw is insignificant to the Service Water pump or Cooling Tower pump capacity to supply design base flow during an accident combined with i

LOP. One Service Water pump must supply 8,700 gpm or 11,360 gpm from one 4

Cooling Tower pump to satisfy design heat loads from ECCS and the Emergency Diesel Generator, a

Other Interactions:

None.

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Failure Consequences?

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Total failure of this weld could result in SW "A" train inoperability and per technical specifications a forced shutdown would commence.

System pressure loss via this postulated 3 inch diameter break would most likely cause I

a tower actuation signal to occur. Since this line is within the pressure boundary of a

the SW system when on the tower, cooling tower pump flow would degrade sufficiently to necessitate a shutdown of SW-P-110A.

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There is no mteraction with the SW "B" train which alone can accommodate design base heat loads.

Impact to Safe Shutdown Capability?

As described above the SW "B" train which would be unaffected by total failure of i

this "A" train weld. The "B" train alone is sufficient for safe shutdown decay heat removal heat loads or heat loads during a design base event with LOP.

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T SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 1.5 ROOT CAUSE INVESTIGATION Root Cause

Description:

A localized flaw in the cement lining caused accelerated corrosion at this shop weld.

Other Systems Affected:

None.

1.6 AUGMENTED INSPECTION Assessment of overall degradation of the affected system:

The leak is typical of localized cement lining flaws in carbon steel SW piping. These leaks do not result from large areas of damage but from very localized wall loss.

An ultrasonic examination of the shop weld circumference was performed. The only wall loss is at the %" x M" flaw location.

Additional examinations required (based on root cause) - specify number of inspection locations - also specify frequency of inspections: [ ten most susceptible and accessible locations for high energy piping system and five for moderate enery,y piping system]

Ultrasonic Examination has been completed at the same shop weld at five additional locations (Attachment 3,5 pages):

"A" train upstream of SW-V116 "A" train upstream of SW-V114 "B" train upstream of SW-V119 "B" train upstream of SW-Vil7 "B" train upstream of SW.V49 No wall loss found at any of the above locations.

Description of areas selected for augmented inspection:

These are locations of similar fabrication, configuration, and service environment.

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SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME Sr ' TION XI REQUIREMENTS 2.0 STRESS ANALYSIS 2.1 DESIGN DETAILS System:

Service Water "A" Train Downstream of SW Pump 110A Component:

Weld between weldolet and weld neck flange Component Size:

3" x 24" weldolet 3" 150 lb weld neck flange Nominal Wall Thickness:

0.215" (minimum)

Safety Code Class:

Class 3 Alaterial:

SA-105 i

l Design Pressure:

150 psig 1

I Design / Operating Temperature:

200/34-65 Code Afinimum Wall Thickness:

0.015" 2.2 FLAW CH AR ACTERIZATION I

Flaw Description / Size: (i.e., flaw size, adjacent wall thickness, single / multiple i

flaw, total area examined, etc.)

The flaw is highly localized. The through wall portion of the flaw is %" x %" and i

the minimum adjacent wall thickness is 0.330".

Flaw Location:

The flaw is located upstream of SW-V48.

l Alethod Examination:

UT Flaw Type:

Through wall flaw due to erosion / corrosion Referenced UT Afeasurements: (3 pages) 2.3 FLAW EVALUATION

SUMMARY

i Alethod Used:

j "Through-Wall Flaw" Approach (GL 90-05). This method considers a through wall flaw and evaluates the flaw stability by a linear elastic fracture mechanics methodology.

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SEABROOK STATION j

FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS Results of Evaluation:

Loading conditions included dead weight, pressure, thermal, and seismic. All code i

stress equations were considered and determined to be acceptable. Stability of flaw was evaluated for all loading conditions and determined to be acceptable. Results of i

evaluation are summarized below.

ASME III, SUBSECTION ND, STRESS EVALUATION '

DESIGN ACTUAL STRESS ALLOWABLE

~ ACTUAL CONDITION (PSI)

STRESS (PSI)

ALLOWABLE Normal 2,391 1 7,58 i 0.14 Upset 5,728 21,000 0.27 Faulted 7,896 31,500 0.25 t

.1 FLAW STABILITY CHECK STRESS INTENSITY FACTOR (KSI (IN)'*)

FACTOR OF SAFETY l

ACTUAL CRITICAL CRITICAL / ACTUAL 13.01 35.0 2.69 t

i 2.4 FLAW MONITORING Walkdown Frequency: (for leak monitoring) f At least once per week.

i Frequency of Follow-up NDE: (for erosion rate assessment)

~j At least once every three months.

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