Text

Requests Relief from ASME B&PV Code Section XI Requirements Per 10CFR50.55
	ML20093K291
Person / Time
Site:	Seabrook
Issue date:	10/16/1995
From:	Feigenbaum T; NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NYN-95081, NUDOCS 9510240154
	Download: ML20093K291 (17)
	v • d • e

.

A:..

h i.Nor'tL North Atlantic Energy Service Corporation u

y.o. 8,,300 Atlantic Seabrook, NH 03874 (603) 474-9321, Fax (603) 474-2987 -

The Northeast Utilities System -

Ted C. Feigenbaum Seni r Vice President a.

NYN-95081 -

Chief Nuclear Officer October 16,1995 United States Nuclear Regulatory Commission Washington, D.C. 20555

. Attention:

Document Control Desk

References:

(a)

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

Subject:

Relief Request From ASME Code Section XI Requirements Gentlemen:

North Atlantic Energy Service Corporation (North Atlantic) hereby requests, pursuant to NRC Generic Letter 90-05, relief from the ASME Boiler and Pressure Vessel Code Section XI requirements pursuant to 10CFR50.55a(g)(6)(i). The Enclosure provides a description of actions taken by North Atlantic to make temporary non-code repairs to a leak in the Service Water (SW) System line 1802-14-153-24".

The SW System is a Class 3, moderate energy system. The non-code repair, a soft rubber gasket secured with a mechanical clamp, was completed at approximately 1530 on October 15, 1995. This repair successfully isolated the leak.

The leak is located in a cement lined 24-inch bypass line for Strainer SW-S-II, which is

- downstream of the ocean and cooling tower SW pumps and upstream of the Primary Component Cooling Water (PCCW), Secondary Component Cooling Water (SCCW), and Emergency Diesel Generator Water Jacket heat exchangers. Attachment 2 of the Enclosure depicts the leak location. Specifically, the leak is a 1/32-inch diameter through-wall flaw at a field weld connecting a straight section of 24-inch diameter pipe to'n 24-inch diameter Tee fitting. The leak is approximately one gallon per hour. Ultrasonic examination has identified no additional degradation of this field weld. Ilowever, it must be noted that approximately_

25% of this weld was not examined since weld preparation for ultrasonic examination was stopped p

7 immediately upon discovery of the through-wall leak. Preliminary augmented ultrasonic examinations performed to date on other welds with similar configurations and service environments were found to be

- accepuble.

It is not practical to isolate the leaking SW line to perform a' code repair. A code repair on this line

.would require partial draindown of SW Train B, resulting in the inoperability of the two ocean SW pumps 200013 951d240154 951016 l

^

-.PDR ADOCK-05000443 1-P.

_',m PDR_

i

5

. V United States Nuclear Regulatory Commission October 16,1995

. Attentioni

. Document Control Desk Page two and the cooling tower SW pump within this train. Inoperability of an entire SW loop is allowed by.the requirements of Technical Specification 3/4.7.4 " Service Water System / Ultimate Heat Sink" for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .; However, due to system configuration, both trains of SW are needed to dissipate normal plant heat loads. Additionally, the allowed outage time may not be sufficient to perform a code repair, thus entry into Technical Specification 3.0.3 would be required and a plant shutdown would ensue.

Consistent with the provisions of Generic Letter 90-05, North Atlantic is submitting this. relief request for a temporary non-code repair. Code repair of the degraded piping will be completed during the upcoming refueling outage, which is scheduled to begin on November 4,1995. The Resident Inspector for Seabrook Station, Mr. David Mannai, was notified of this repair.

This letter and its Enclosure have been reviewed and approved by the Station Operation Review Committee (SORC). A supplement to this letter will be submitted by October 31,1995 to provide the results of augmented examinations of SW welds with similar configuration, fabrication, and service environment.

.Should you have any questions regarding this letter, please contact Mr. James M. Peschel, Regulatory Compliance Manager, at (603) 474-9521 extension 3772.

,/

- Very t ly yours,

/ f&

W/y Ted C. Feigenbaum TCF/JES:jes j

Enclosure -

cc:

Mr. Thomas T. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road i

King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division ofReactor Projects U.S. Nuclear Regulatory Commission Washington,DC 20555 Mr. John B. Macdonald NRC Senior Resident Inspector P.O. Box 1149 Seabrook,NH 03874

North Atlantic October 16,1995 ENCLOSURE TO NYN-95081

. ~.

- ~.. -

SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 4

ACR # 95-316

. DATE: 10/14/95 TIME: Anorox.1625 4

1.0 ORIGINATOR i-1.1 PESCRIFTION OF FLAW i

nere is a thru wall flaw causing leakage on line 1802-14-153-24". The leak is at the field weld which connects line 1802-14 to line 1802-5-153-24" and is l

downstream of the normally closed "B" train strainer bypass valve SW-V66.

(Refer to Attachment 1)

His leak is located in the Service Water Strainer Room at elevation 53' in the PAB. Since routine strainer basket cleaning is performed in this room, the area is very well drained. ne flaw has an approximate dimension of 1/32" diameter. The ~

leak rate is estimated to be less than one gallon per hour.

Piping / Component Drawing No.:

j ne piping is carbon steel with 3/8" thick cement fining as detailed on sketch 804998 of specification 248-2 (Refer to Attachment 2 ).

P&ID No.:

l-SW-B/D20795 f

j 1.2 IMPRACTICALITY OF CODE REPAIR It was determined not practical to perform a code repair of the leaking SW line at this time. A code repair on this line'would require partial draindown of SW Train "B", resulting in the inoperability of the two ocean SW pumps and the cooling tower pump within this train.

i Inoperability of an entire SW Loop is allowed by Technical Specification 3/4.7.4a

" Service Water System / Ultimate Heat Sink" for up to a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months period. However, due to system configuration, both trains are needed to disipate normal plant heat loads. Furthermore, the allowed outage time may not be sufficient to perform a j

code repair, thus entry into Technical Specification 3.0.3 would be required and a plant shutdown would ensue.

a

1.3 DESCRIPTION

OF PROPOSED TEMPORARY REPAIR A soft rubber gasket with mechanical clamp has been installed.

i SEABROOK STATION

~ FQRM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS

+

1.4 SAFETY SIGNIFICANCE System Interaction Evaluation Flooding:

There is a leak ofless than one gallon per hour coming from the 1/32" diameter thru wall flaw in this 24" diameter field weld. Ultrasonic Examination has confirmed that there is no additional degradation at this field weld.

I The leakage is well contained within the Service Water Strainer Room, elevation 53' of the PAB. More than adequate drainage exists to preclude floodmg Jet Spray:

There are no safety related power supplies that could be disabled as a result of the j

jet spray from this flaw. Motor operated valves SW-V4 and V5, located in this i

room, have an active safety related function. %c valves are at least 20 feet from the location of the leak and are well shielded by large pipe and grating from any spray, should it develop.

i i

Loss of Flow:

Loss of SW thru this flaw is insignificant to the Service Water Pump or Cooling Tower Pump capacity to supply design flow during an accident combined with LOP. One Service Water Pump must supply 8,339 gpm or 11,360 gpm from one Cooling Tower Pump to satisfy design heat loads from ECCS and the Emergency Diesel Generator.

Other Interactions:

~

Nm Failure Consequences Total failure of this weld could result in SW "B" train inoperability. Because of system configuration, both trains of SW are needed to disipate normal plant heat loads. Thus, a forced shutdown would commence.

System pressure loss via the postulated break would most likely cause a tower actuation signal to occur. Since this line is within the pressure boundary of the SW system when on the tower, cooling tower pump flow would degrade sufficiently to necessitate a shutdown of SW-P-110B.

Dere is no interaction with the SW "A" train which alone can accommodate design base heat loads.

o i

d SEABROOK STATION FQRM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS Impact to Safe Shutdown Capability s

As described above, the SW "A" train would be unaffected by total failure of this "B" train weld. De "A" train alone is sufficient for safe shutdown decay heat

^

removal heat loads or heat loads during a design base event with LOP.

1.5 ROOT CAUSE INVESTIGATION Root Cause

Description:

Localized flaw in the cement lining caused accelerated corrosion at this field weld.

4 Other Systems Affected:

j Nam 1.6 AUGMENTED INSPECTION 4

Assessment of overall degradation of the affected system:

%e leak is typical oflocalized cement lining flaws at field welds in the carbon steel SW piping. Rese leaks do not result from large areas of damage but from very localized wallloss.

y An ultrasonic examination of the weld circumference was performed. The only wall loss reported is local to the flaw location. It should be noted that -

m approximately 25% of this weld could not be examined because the weld i

preparation needed for UT was stopped upon discovery of the thru wall leak.

Additional examinations required (based on root cause) - specify number of inspection locations - also specify frequency ofinspections: (ten most susceptible and accessible locations for high energy systems and five for l

moderate energy piping systems)

Prelinunary Ultrasonic Examinations have been performed at five additional locations in the SW "B" train (Attachment 3):

1 24" shop weld at the strainer bypass Tee (upstream side) 24" shop weld at the strainer bypass Tee (downstream side) 24" shop weld in the stramer bypass (elbow below flaw location) 16" field weld at the 24"x16" Tee to the DG Heat Exchanger 24" field weld at an elbow downstream of SW-V-67 All additional locations evaluated were found acceptible. At least three additional field weld locations will be included in the augmented inspection plan. These locations and finalized UT results will be submitted in a supplement to this Relief Request.

1

SEABROOK STATION

)

FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS Description of areas selected for augmented inspection:

These locations will be of similar fabrication, configuration, and service environment.

2.0 STRESS ANALYSIS 2.1 DESIGN DETAILS System:

Service Water "B" train. In the bypass line for Strainer SW-S-11 and Downstream of valve SW-V-66.

Component:

Field weld connecting a straight section of 24" diameter pipe and a 24 " diameter Tee fitting.

1 Component Size:

24" diameter cement lined carbon steel pipe.

24"X24"x24" cement lined carbon steel Tee.

Nominal Wall Thickness:

0.375" 4

Safety Code Class:

Class 3 Material:

SA-105 4

Design Pressure:

150 psig Design / Operating Temperature:

200/34-90 degrees F Code Minimum Wall Thickness:

0.171" 2.2 FLAW CIIARACTERIZATION Flaw Description / Size: (i.e., flaw sin, adjacent wall thickness, single / multiple flaw, total area examined, etc.)

The flaw is highly localized. The through wall portion of the flaw is approximately 1/32" diameter and the minimum adjacent wall thickness is 0.174".

~

I Flaw Location:

The flaw is located downstream of SW-V-66.

Method Examination: UT Note: Approximately 25% of this weld could not be examined since weld prep. for UT wm stopped immediately upon discovery of the thm wall leak)

l SEATROOK STATION l

FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS Flaw Type:

Through wall flaw due to erosion / corrosion Referenced UT Measurements:

2.3 FLAW EVALUATION

SUMMARY

Method Used:

i

Ihrough-Wall Flaw" Approach (GL 90-05). 'Ihis method considers a through wall flaw and evaluates the flaw stability by a linear clastic fracture mechanics methodology.

Results of Evaluation:

Loading conditions included dead weight, pressure, thermal, and seismic. All code 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 this evaluation are summarized below:

ASME III, SUBSECTION ND, STRESS EVALUATION DESIGN ACTUAL STRESS ALLOWABLE ACTUAL CONDITION (PSI)

STRESS (PSI)

ALLOWABLE Normal 2,932.

15,000.

0.20 Upset 8,223.

18,000.

0.46 Faulted 11,052.

27,000, 0.41 FLAW STABILITY CHECK STRESS INTENSITY FACTOR (KSI(IN)")

FACTOR OF SAFETY ACTUAL CRITICAL CRITICAIJACTUAL 5.24 35.0 6.68 2.4

_FbAW MONITORING Walkdown Frequency: (for leak monitoring)

At least once per week.

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

At least once every three months.

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