ML20094B549

Revises Relief Request from ASME Boiler & Pressure Vessel Code Section XI & Results of Augmented Insps Performed to Support Relief Request

ML20094B549
Person / Time
Site:	Seabrook
Issue date:	10/25/1995
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-95-084, NYN-95-84, NUDOCS 9511010125
Download: ML20094B549 (58)

Text

{{#Wiki_filter:- __7 _ _._ _ . _. _...~.-__ _ _ _. _ l 1 NortLu g.O. So,300 North Atlantic Energy Service Corporation 9 1 l) Atlantic Seabrook, nil 03874 (603) 474 9521, Fax (603) 474-2987 The Northeast Utilities System l Ted C. Feigenbaum I NYN-95 084 Senior Vice president 8. Chief Nuclear Officer October 25,1995 United States Nuclear Regulatory Commission Washington, D.C. 20555 l i l Attention: Document Control Desk

References:

(a) Facility Operating License No. NPF-86, Docket No. 50-443 (b) North Atlantic Letter NYN-95081, dated October 16,1995," Relief Request From ASME Code Section XI Requirements," T. C. Feigenbaum to USNRC (c) North Atlantic Letter NYN-94115, dated October 12,1994," Service Water System Piping Degradation," T. C. Feigenbaum to USNRC (d) 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:

Supplement to Relief Request From ASME Code Section XI Requirements and Results of Augmented Inspections Gentlemen: The purpose of this letter is to revise a relief request from the ASME Boiler and Pressure Vessel l Code Section XI requirements as submitted by North Atlantic Energy Service Corporation (North Atlantic) in a letter datd October 16,1995 (Reference (b)]. This letter also transmits the results of augmented inspections performed to support this relief request. The subject relief request, which was made pursuant to both NRC Generic Letter 90-05 and 10CFR50.55a(g)(6)(i), was in regard to a temporary non-code repair to a leak in the Service Water (SW) System line 1802-14-153-24" (Class 3) at field weld SW-1802-F0901. l The non-code repair, a soft rubber gasket secured with a mechanical clamp, was completed on October 15, 1995, and had successfully isolated the leak. Subsequently, on October 18, 1995, this same weld exhibited leakage from two additional locations. These new leaks were found on the portion of the weld that had previously been prepared (i.e., flat-topped) for ultrasonic examination. One of the leaks is located approximately 90 degrees circumferentially from the original flaw and the second leak is located less than 0.25-inches from the original leak and is part of the original flaw. The total leakage from both flaws at this field weld is estimated to be less than 0.5 gallons per hour. Additional ultrasonic examinations have been performed on this weld using both a scanning technique and a Digital Thickness Meter (DTM) to obtain the profile of the 30007J 9511010125 951025 M I PDR ADOCK 05000443 l Q PDR i i

c j 0 United States Nuclear Regulatory Commission October 25,1995 Attention: Document Control Desk Page two flaws and to determine if additional degradation was present. The scanning technique is more rigorous for identifying additional degradation than solely using a DTM, as was initially used on this weld for the results described in Reference (b). He scanning examination confirmed the profile of these flaws No other areas of this weld were found to be less than the calculated minimum wall thickness. As before, approximately 25% of this weld was not examined since weld preparation for ultrasonic examination was stopped immediately upon discovery of the initial through-wall leak. Accordingly, North Atlantic requests relief for a temporary non-code repair of the additional leak locations at this weld. Enclosure I revises the basis for relief that was submitted via Reference (b) to address the current conditior, af this weld. This enclosure addresses the elements of NRC Generic Letter 90-05 including safety significance, root cause, stress analysis, and flaw characterization for this degraded weld. North Atlantic believes that this condition is due to long term degradation or improper application of the compound used to seal the cement pipe liner between field welds, which permitted sea water to come in contact with the carbon steel piping causing localized pitting corrosion at this unprotected field weld. Code repair of the field weld SW 1802-F0901 will be completed during the upcoming refueling outage, which is scheduled to begin on November 4,1995. The NRC Resident Inspectors for Seabrook Station were notified of the additional repairs, which successfully stopped the leakage. In accordance with NRC Generic Letter 90-05, and as committed to in Reference (b), North Atlantic completed augmented ultrasonic inspections at five additional field welds in the Service Water System. Rese welds were of similar configuration, fabrication, and service environment. One weld, SW-1802-F0801, exhibited localized wall thinning (wall thickness of 0.110-inches) of less than the calculated minimum wall thickness of 0.120-inches. One other location on this weld exhibited somewhat less degradation (wall thickness of 0.220-inches). The degradation exhibited at this weld is believed to be caused by the same corrosion mechanism that was experienced at field weld F0901. North Atlantic has evaluated the degradation observed at this weld and has concluded that it does not adversely affect operability of the Service Water System. This evaluation is provided as Enclosure 2 to this letter, Code repair of field weld SW-1802-F0801 will be completed during the upcoming refueling outage. It should be noted that one other field weld, SW-1802 F1001, initially exhibited two locations of wall thinning ofless than minimum wall thickness. Rese readings were taken on the pipe wall outside of the wcld area. Subsequent evaluation determined that these readings were caused by inclusions in the base metal during manufacturing and were not the result of corrosion. These inclusions are acceptable per the code and they do not adversely affect system operability nor require repair. The three other welds in this first sample of five were found to be acceptable with no locations that are less than the calculated minimum wall thickness. However, as a result of the degradation found at field weld SW 1802 F0801, North Atlantic expanded the sample size of the augmented inspections to include a second set of five additional field welds. He results of these examinations indicate that all five additional welds are acceptable with no locations that are less than the calculated minimum wall thickness. The ultrasonic examination data sheets for these five welds, in addition to the four aforementioned welds that were also determined to be acceptable in the first set of five welds, are provided in Enclosure 3. The successful completion of the examinations for the second set of five welds satisfies and completes the

i i United States Nuclear Regulatory Commission October 25,1995 i Attention: Document Control Desk Page three i l j augmented inspection requirements of NRC Generic Letter 90-05. Similarly, this letter satisfies the reporting requirements of the generic letter. Notwithstanding this, North Atlantic intends to ultrasonically i l examine 29 other above ground field welds in the "B" Train Service Water System by the completion of the { upcoming refueling outage. North Atlantic had previously described its intent to perform these inspections j in Reference (c). This letter and its enclosures have been reviewed and approved by the Station Operation Review l Committee (SORC). l Should you have any questions regarding this letter, please contact Mr. James M. Peschel, Regulatory Compliance Manager, at (603) 474-9521 extension 3772. .J f-' l VerypJIy yours, ( 1 / Afd b/d /. Ted C. Feigenbau f _TCPIES:jes a Enclosures I cc: Mr.Romas T. Martin Regional Administrator j U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Albert W. De Agazio, Sr. Project Manager Project Directorate I-4 Division of Reactor 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 l October 25,1995 1 1 l l l ENCLOSURE 1 TO NYN-95084 l i l l l l l t l l l l l

~._ ___ __._.

1. e 1

OPERABILITY DETERMINATION FORM ACR No. ~ ODF No. DESCRIPTION PRELIMINARY FINAL 1. Affected structure, system or component d'@V/W U b 2. Description of degraded or nonconforming condition W M0" M -

• 4 C LEAK. IsJ ftJ

~ 3. Operable Inoperable / #02 - Foto / 4. Basis for operability determination b dM (use additional sheets as e red) /d!/9 I I Prepared by: M Date: (J ' / / / ~ APPROVAL I. PRELIMINARY OPERABILITY DETERMINATION Operations Manager: / Date :/d [ / ~ Pf/f II. FINAL OPERABILITY D INKIION Assigned Responsible Manager: Due Date: (assigned by Operations Manager) ACR Responsible Manager: Date: Manager of Engineering: Date: (when supplying analyses or evaluations) Technical Support Manager: Date: Regulatory Compliance Manager: Date: Operations Manager: Date: SORC REVIEtt SORC Chairman: Meeting No. EXTENSION APPROVAL PRELIMINARY FINAL b Extended Due Date: Station Manager: Date: OE 4.5A Rev. 2

SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS ACR # 95-316 DATE:10/18/95 TIME: Approx.1600 1.0 ORIGINATOR

1.1 DESCRIPTION

OF FLAW There are two through wall flaws causing leakage from Field Weld SW-1802-F0901 on line 1802-14-153-24". One flaw has leakage at two locations approximately 1/4" apart. This field weld connects line 1802-14 to line 1802 153-24" and is downstream of the normally closed "B" train strainer bypass valve SW-V66. (Refer to Attachment 1) These leaks are 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. Each leakage location can be characterized as a pinhole. He first flaw which has two leakage sites is located at approximately 285' relative to plant North (75* relative to the UT coordinate system). The second flaw which has a single leakage site is oriented at plant North ( 0 on the UT coordir. ate system). He total leak rate is estimated to be less than 0.5 gallons per hour. Piping / Component Drawing No.: The piping is carbon steel with 3/8" thick cement lining as detailed on sketch 804998 of specification 248-2 (Refer to Attachment 2 ). P&ID No.: 1-SW-B/D20795 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. 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 hour 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 code repair, thus entry into Technical Specification 3.0.3 would be required and s. plant shutdown would ensue.

1.3 DESCRIPTION

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

SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 1.4 SAFETY SIGNIFICANCE System Interaction Evaluation Flooding: There is a leak ofless than 0.5 gallons per hour coming from these pinhole through-wall flaws in this 24" diameter field weld. Ultrasonic Examination has confirmed that there are no additional locations below required Code minimum wall thickness at this field weld. The leakage is well contained within the Senice Water Strainer Room, elevation 53' of the PAB. More than adequate drainage exists to preclude flooding. Jet Spray: There are no safety related power supplies that could be disabled as a result of the jet spray from these flaws. Motor operated valves SW-V4 and V5, located in this room, have an active safety related function. The valves are at least 20 feet *from the location of the leakage and are well shielded by large pipe and grating from any spray, should it develop. l Loss of Flow: l Loss of SW through these flaws is insignificant to the Senice Water Pump or Cooling Tower Pump capacity to supply design flow during an accident combined with LOP. One Senice Water Pump must supply 8,550 gpm or 12,215 gpm from one Cooling Tower Pump to satisfy design heat loads from ECCS and the Emergency Diesel Generator. These requirements assume maximum permissible IST pump degradation (93% Head) and maximum IST instrument uncertainty in a Post-LOCA/ Loss of Offsite Power scenario. Since the SWP's and CTP's are currently capable of operating at 100% capacity with no observable degradation, there is significant flow margin available with respect to these values. Other Interactions: None Failure Consequences: Significant degradation of this weld could result in SW "B" train inoperability. Because of system configuration, both trains of SW are needed to dissipate 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, a manual shutdown of cooling tower pump SW-P-110B would be required to preclude basin pumpdown to an unacceptable level.

SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS There is no interaction with the SW "A" train which alone can accommodate design base heat loads. Impact to Safe Shutdown Capability: As described above, the SW "A" train would be unaffected by significant degradation of this "B" train weld. The "A" train alone is sufficient for safe shutdown decay heat removal heat loads or heat loads during a design base event i with LOP. The SW "B" Train is also fully capable of bringing the plant to a safe shutdown condition even with the presence ofleakage through these two flaws. l 1.5 ROOT CAUSE INVESTIGATION Root Cause

Description:

Localized long term degradation or improper application of X-Pando or Sikadur Low-Mod-Geljoint compound permitted sea water to come in contact with the carbon steel piping substrate / weld. Pitting corrosion then caused accelerated local j attack at this unprotected field weld. Other Systems Affected: None 1.6 AUGMENTED INSPECTION Assessment of overall degradation of the affected system: These leaks are typical oflocalizedjoint compound flaws at field welds in the carbon steel SW piping. This is the first case of a through wall leak in a 24" piping field weld. UT inspections conducted during OR-03 on A-Train PAB and CT field welds revealed that of 49 welds inspected,2 had base metal degradation. Each of these welds had sufficient margin with respect to required Code minimum wall thickness. One of the two degraded welds (1801-F0701) was the identical A-Train counterpart to the weld currently being evaluated (1802-F0901). Visual and UT inspection of A and B Train field welds in the SWPH during OR-03 also revealed several degraded field welds. None of these welds were below Code muumum required wall thickness. Based on past system history, once pitting commences the resulting flaws are very localized in nature and do not represent a piping structural integrity problem. Based upon the data collected to date, only a small percentage of the total population of field welds are potentially subject to this degradation mechanism. An ultrasonic exanunation of the weld circumference was performed. The only wall loss reported is local to the flaw locations. It should be noted that approximately 25% of this weld could not be examined because the weld

~-- I i SEABROOK STATION l FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS preparation needed for UT was stopped upon discovery of the initial through wall leak. l Additional examinations reqmred (based on root cause)- specify number cf j inspection locations - also specify frequency ofinspections: (ten most susceptible and accessible locations for high energy systems and Gye for moderate energy piping systems) Preliminary Ultrasonic Examinations have been perfonned at Ove additional locations in the SW "B" train (Attachment 3): l l 24" shop wcld at the strainer bypass Tee (upstream side) 24" shop weld at the strainer bypass Tee (downstream side) 24" shop weld in the strainer 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 acceptable. 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. 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 DETAll,S System: Service Water "B" train. In the bypass line for Strainer SW-S-Il and Downstream of valve SW-V-66. Component: Field weld connecting a straight section of 24" diameter pipe and a 24 " diameter Tee fitting. Component Size: 24" diameter cement lined carbon steel pipe. 24" x 24" x 24" cement lined carbon steel Tee. Nominal Wall Thickness: 0.375" Safety Code Class: Class 3 Material: SA-106, Gr B Design Pressure: 150 psig

SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 4 Design / Operating Temperature: 200/34-90 degrees F Code Minimum Wall Thickness: 0.121" 2.2 FLAW CITARACTERIZATION Flaw Description / Size: (i.e., llaw size, adjacent wall thickness, single / multiple flaw, total area examined, etc.) The flaws are localized. The first flaw (75* location on the UT coordinate system) has two pinhole leakage points approximately 1/4" apart. The flaw is eliptical in shape and shown in detail in the attached UT Examination Report per Attachment 3, page S. The second flaw (0* location on the UT coordinate system) has a single leakage location and is shown in detail on Attachment 3, page 4. Flaw Location: The flawed field weld is located downstream of SW-V-66. Method Examination: UT Note: Approximately 25% of this weld could not be examined since weld prep. fbr UT was stopped immediately upon discovery of the first through wall leak) Flaw Type: Through wall flaws due tojoint compound degradation and subsequent pitting corrosion. Referenced UT Measurements: 2.3 FLAW EVALUATION

SUMMARY

Method Used: "Through-Wall Flaw" Approach (GL 90-05). This method very conservatively utilizes a through wall flaw of 1" length and evaluates the flaw stability by a linear elastic 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. The stability of the flaws was evaluated for all loading conditions and determined to be acceptable. Results of this evaluation are summarized below:

~ SEABROOK STATION FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS ASME III, SUBSECTION ND, STRESS EVALUATION DESIGN ACTUAL STRESS ALLOWABLE ACTUAL CONDITION (PSI) STRESS (PSI) ALLOWABLE Normal 2,556. 15,000. 0.11 Upset 5,818. 18,000. 0.32 Faulted 7,600. 27,000. 0.28 FLAW STABILITY CHECK STRESS INTENSITY FACTOR (KSI(IN)") FACTOR OF SAFETY ACTUAL CRITICAL CRITICAIJACTUAL 23.24 35.0 1.50 2.4 FLAW MONITORING p 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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OPERABILITY DETERMINATION FORM "Nb ACR No. ODF No. DESCRIPTION PRELIMINARY FINAL 1. Affected structure, system or component I672 W I 'O 2. Description o degraded or nonconforming condition NAR WW E ~ nao <~ew 3. Operable Inoperable g m gg g 4. Basis for operability determination b <Ob[ (use additional sheets as hired) Prepared by: [M Date; /O E/ N ') f~ / / APPROVAL I. PRELIMINARY OPERABILITY DETERMINATION D of A \\ Date: Operations Manager: m em o asym II. FINAL OPERABILITY DETERMINATION Assigned Responsible Manager: Due Date: (assigned by Operations Manager) ACR Responsible Manager: Date: Manager of Engineering: Date: (when supplying analyses or evaluations) Technical Support Manager: Date: Regulatory Compliance Manager: Date: Operations Manager: Date: SORC REVIEW SORC Chairman: Meeting No. EXTENSION APPROVAL PRELIMINARY b FINAL Extended Due Date: l Station Manager: Date: i OE 4.5A l Rev. 2 l i

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION ACR # 95-316 DATE: 10/24/95 TIME: Aonrox.1000 1.0 ORIGINATOR

1.1 DESCRIPTION

OF FLAW UT inspection has revealed wall thinning due to pitting at field weld 1802-F0801 on line 1-SW-1802 5-153-24" This field weld joins a vertical riser pipe with a 90* elbow downstream of SW-V67, the SW-S-11 outlet isolation valve (Refer to ). The flaw discovered at this location is characterized as elliptical in shape and has a minimum wall thickness of 0.110". The flaw is located in the weld area as detailed in the Ultrasonic Thickness Examination Report provided in. This field weld 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. Piping / Component Drawing No.: The piping is carbon steel with 3/8" thick cement lining as detailed on sketch 804998 of Specification 248-2 (Refer to Attachment 2 ). P&lD No.: 1-SW-B/D20795 1.2 IMPR ACTICALITY OF CODE REPAIR ~ The discovery of this flaw occurred as a result of the GL 90-05 Augmented inspection due to through-wall leaks found in field weld SW-1802-F0901. It was determined not practical to perfomi a Code repair of this leaking service water weld at that time. A Code repair on this line would have required partial draindown of SW Train "B", resulting in the inoperability of the two ocean SW pumps and the cooling tower pump within this train. 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 hour period. However, due to system configuration, both trains are needed to dissipate nonnal plant heat loads. Furthermore, the allowed outage time may not have been sufficient to perform a Code repair, thus entry into Technical Specification 3.0.3 would have been required and a plant shutdown would have ensued.

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION l

1.3 DESCRIPTION

OF PROPOSED TEMPORARY REPAIR Since this flaw was discovered as part of a GL90-05 Augmented Inspection and through-wall leakage is not occurring and is not predicted to occur up to OR-04, a temporary repair is not required at this time. 1.4 SAFETY SIGNIFICANCE System Interaction Evaluation Flooding: Ultrasonic Examination has confirmed that there are no additional locations below required Code minimum wall thickness at this field weld. The flaw is highly localized. In the event that a pinhole leak develops in this weld, the leak rate would be expected to be less than I gph. The leakage would be well contained within the Senice Water Strainer Room, elevation 53' of the PAB. More than adequate drainage exists to preclude flooding. Jet Spray: There are no safety related power supplies that could be disabled as a result of the jet spray from this flaw. Motor operated valves SW-V4 and V5, located in this room, have an active safety related function. The valves are at least 20 feet from the location of any possible leakage and are well shielded by large pipe and grating i from any spray, should it develop. Loss of Flow: Loss of SW through this flaw would be insignificant in comparison with the Senice Water Pump or Cooling Tower Pump capacity to supply design flow during an accident combined with LOP. One Senice Water Pump must supply 8,550 gpm or 12,215 gpm from one Cooling Tower Pump to satisfy design heat loads from ECCS and the Emergency Diesel Generator. These requirements assume maximum permissible IST pump degradation (93% Head) and maximum IST instrument uncertainty in a Post-LOCA/ Loss of Offsite Power scenario. Since the SWP's and CTP's are currently capable of operating at 100% capacity with no observable degradation, there is significant flow margin available with respect to these values. Other Interactions: None Failure Consequences: Significant degradation of this weld could result in SW "B" train inoperability. Because of system configuration, both trains of SW are needed to dissipate normal plant heat loads. Thus, a forced shutdown would commence.

-.-. - - - -.. - - - ~. l i SEABROOK STATION i OE4.5 OPERABILITY DETERMINATION i l.3 DESCRIPTION OF PROPOSED TEMPORARY RF.PATR l Since this flaw was discovered as part of a GL90-05 Augmented Inspection and through-wall leakage is not occurring and is not predicted to occur up to OR-04, a temporary repair is not required at this time. 1.4 SAFETY SIGNIFICANCE System Interaction Evaluation Flooding: 3 l Ultrasonic Examination has confirmed that there are no additional locations below j required Code minimum wall thickness at this field weld. The flaw 'is highly localized. In the event that a pinhole leak develops in this weld, the leak rate would 1 be expected to be less than 1 gph. The leakage would be well contained within the l Service Water Strainer Room, elevation 53' of the PAB. More than adequate drainage exists to preclude flooding. l Jet Spray: ) l i There are no safety related power supplies that could be disabled as a result of the { ] jet spray from this flaw. Motor operated valves SW-V4 and VS, located in this room, have an active safety related function. The valves are at least 20 feet from the location of any possible leakage and are well shielded by large pipe and grating from any spray, should it develop. Loss of Flow: i Loss of SW through this flaw would be insignificant in comparison with the 4 j Service Water Pump or Cooling Tower Pump capacity to supply design flow during an accident combined with LOP One Service Water Pump must supply j 8.550 gpm or 12,215 gpm from one Cooling Tower Pump to satisfy design heat loads from ECCS and the Emergency Diesel Oenerator. These requirements assume maximum permissible IST pump degradation (93% Head) and maximum IST instrument uncertainty in a Post LOCA/ Loss of Offsite Power scenario. Since the SWP's and CTP's are currently operating at 100% capacity with no observable degradation, there is significant flow margin available with respect to j these values. Other Interactions: { None Failure Consequences: Signifcant degradation of this weld could result in SW "B" train inoperability. Because of system configuration, both trains of SW are needed to dissipate normal plant heat loads. Tims, a forced shutdown would commence.

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION l 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, a manual shutdown of cooling tower pump SW-P-110B would be required to preclude basin pumpdown to an unacceptable level. There is no interaction with the SW "A" train which alone can accommodate design base heat loads. Impact to Safe Shutdown Capability: As described above, the SW "A" train would be unaffected by significant degradation of this "B" train weld. The "A" train alone is sufficient for safe shutdon decay heat removal heat loads or heat loads during a design base event with LOP. The SW "B" Train is also fully capable of bringing the plant to a safe shutdown condition even with the presence ofleakage through this flaw. 1.5 ROOT CAUSE INVESTIGATION Root Cause

Description:

Localized long term degradation or improper application of X-Pando or Sil$dur Low-Mod-Geljoint compound permitted sea water to come in contact with the carbon steel piping substrate / weld. Pitting corrosion then caused accelerated local attack at this unprotected field weld. Other Systems Affected: None 1.6 AUGMENTED INSPECTION Assessment of overall degradation of the affected system: This weld degradation is typical oflocalized joint compound flaws at field welds in the carbon steel SW piping. This weld and weld SW-1802-F0901, which was initially evaluated under an ASME XI Relief Request in ACR 95-316 for through-wall leakage, are the only cases whereby wall thinning below the Code minimum required value has been observed. UT inspections conducted during OR-03 on A-Train PAB and CT field welds revealed that of 49 welds inspected,2 had base metal degradation. Each of these welds had sufficient margin with respect to required Code minimum wall thickness. Visual and UT inspection of A and B Train field welds in the SWPH during OR-03 also revealed several degraded field welds. None of these welds were below Code minimum required wall thickness. Based on past system history, once pitting commences the resulting flaws are very localized in nature and do not represent a piping structural integrity problem. Based upon the data collected to date, only a small percentage of the total population of field welds are potentially subject to this degradation mechanism.

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION Additional exnminations 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 moderate energy piping systems) This flaw was discovered during the GL 90-05 Augmented Inspection required as a result of through wall leakage on field weld 1802-F0901. Ultrasonic Examinations have been perfomied at nine additional similar field welds in the SW "B" train: Initial Augmented Inspection: SWl802-F1001 SWl812-F1002 SWI802-F0701 SWI802 F0902 Supplemental Augmented Inspection: SW1802-F1003 ~ SW1802-F0602 SW1802-F0601 SW1812-F1001 SW1812-F0903 All additional locations evaluated have been found acceptable. Prior to OR-04, the balance of above ground 24" B-Train field welds in the PAB and Cooling Tower will be inspected (approximately 40 total). 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 line for Strainer SW-S-Il and Downstream of valve SW-V67. Component: Field weld connecting a straight section of 24" diameter pipe and a 24 " diameter 90* elbow fitting. Component Size: 24" diameter cement lined carbon steel pipe. 24" cement lined carbon steel 90* elbow

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION Nominal Wall Thickness: 0.375" Safety Code Class: Class 3 Afaterial: SA-106, Gr B Design Pressure: 150 psig Design / Operating Temperature: 200/34-90 degrees F Code Minimum Wall Thickness: 0.120" 2.2 FLAW CIIARACTERIZATION Finw Description / Size: (i.e., flaw size, adjacent wall thickness, single / multiple flaw, total area examined, etc.) The flaw is localized. The flaw is elliptical in shape with a measured minimum wall thickness of 0.110". The flaw is shown in detail in the attached UT. Examination Report per Attachment 3. Flaw Location: The flawed field weld is located dosmstream of SW-V 67. Afethod Examination: UT Flaw Type: Field weld flaw due to joint compound degradation and subsequent pitting corrosion. Referenced UT Afeasurements: 2.3 FLAW EVALUATION

SUMMARY

Method Used: i "Through-Wall Flaw" Approach (GL 90-05). This method very conwrvatively utilizes a through-wall flaw of 1" length and evaluates the flaw stability by a linear elastic fracture mechanics methodology. Results of Evaluation: j Loading conditions included dead weight, pressure, thermal, and seismic. All Code stress equations were considered and determined to be acceptable. The stability of the flaw was evaluated for all loading conditions and determined to be acceptable. Field weld SW1802-F0801, its associated piping and the service water system are therefore OPERABLE. Results of this evaluation are summarized below: 1

SEABROOK STATION OE4.5 OPERABILITY DETERMINATION ASME III, SUBSECTION ND, STRESS EVALUATION DESIGN ACTUAL STRESS ALLOWAHLE ACTUAL CONDITION (PSI) STRESS (PSI) ALLOWABLE Normal 2,839 15,000 0.19 Upset 7,749 18,000 0.43 Faulted 9,772 27,000 0.36 FLAW STABILITY CIIECK STRESS INTENSITY FACTOR (KSI(IN)") FACTOR OF SAFETY ACTUAL CRITICAL CRITICAL / ACTUAL 33.51 35.0 1.044 i 2.4 FLAW MONITORING [ Walkdown Frequency: (for leak monitoring) This weld will be repaired in accordance with ASME XI during OR-04 which ~ commences in less than two weeks on i 1/04/95. Frequency of Follow-up NDE: (for erosion rate assessment) l This weld will be repaired in accordance with ASME XI during OR-04 which I commences in less than two weeks on 11/04/95.

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ULTRASONIC THICKNESS EXAMINATION REPORT l i LOCATION 566 SELN SYSTEM SW WORK REQUEST 96 woo 0 6% { EXAMINAVON AREA /RESULTS CESCRIPTION OF EXAMINATION AREA ANO RESULTS wrt05: $w I eo t - Fioo 3 Svd / 001 - F o (,o 1 SW i 001-FO lo O l Sw aBil-6100I SW f012-F0963 2 3 SxETCH onceue. coeruceans. cxrnpanene essermons. eca DATE /413M / j EXAMINED _ _m LEVEL e EXAMINEL LE'v d DATE c 21 / EXAMINATION RESULTS ACcaPTASLE ALUATION M90'O 1 7 LEVEL [DATE /QM REMEWED --'t REVIEWED DATE W A0fl~- itc4& I W$ %"l'/00J \\ ATTACNED INSTRUMENT DATA INSTRUMENT; MFG /NODEL 60AJ# C /3(, GTE/SN (#TE 2(9Y4: ^ P RT [ CRT/ DIGITAL 0 o'crt^' FORLZONTAL UNEARITY PERFORMED (Ad8)8M) PTTCH / CATCH COMP SURFACE TEMP >128-M O YES FLS No. M[4 CAL DUE DATE M/4 hULSE/ ECHO meness , i Q:) " l,3oc*l,foC",/ foo" MFG. M S E 8.h'8 su e 033o I(,33o ! (.o330 ' (o s B 3 me OEnD SER# O6POTY cm De oss 9-20 98 I 9 2o 96 i 92096: 9-211 6 SIZE M FREQ. 4 MHz j ~ . to o" l 300* .soo"

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Service Water System Corrosion Monitoring Program s Line /gz Weld No. g/003 Date /c -z3-ff Show location and thickness of thinnest point in each sector TDC Top Deed Center of non-vertical pipe or la fina with extrados of nearsat elbow (for 1 vertie : pip.) r i X C l l 'ld, i iL B l lx2 l l ' d 1s0-270 hrh WM 3 S" ro.w" t = At.sA i D/S

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Service Water System Corrosion Monitoring Program m s Line Weld No. posoz. Date <c/2 s/9g jgoz. Show location and thickness of thinnest point in each sector TDC

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simcz cam sis m \\ CORROSION MONITVRIBG FIOGRAM r.ine so. /602. weld wo. 40G0/ IDWEST CIRC. FROM AXIAL ME W m.IxEhT oaxoRxwr azxoIwo xExsunzxtrr arf. rr. raca m o c m za LINE 0 - 90 56" /" 90 W'l % d. U/s 3s* l 90" @k D/s .so~ 49e 90 3/v"e, f 90-150 40" '/z,

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Service Water System ~ l + Corrosion Monitoring Program s Line f g,o t Weld No. pu c, f Date /o/23/9s-Show location and thickness of thinnest point in each sector TDC '.'a'.". "."i.'."wo. a"- % 'd" i i j ve. pir.) g F l A r l O onI W i r in i

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hi/RTS No. OfWOCO h 881 SEEnct :Am svS zx CORROSION MONIERING PIDGRAM Lir.e No. / blb-Weld No. [/00I 14MEST CIRC. FIOM AXIAL F.r.ASURD(DiT CCADRAYr READING MEASURDENT RET. PT. IICM WEID CEhTER LINE O - 90 sz O" o' / "m 4 TMO+M U$ 3S* 41L 9a

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FROM AXIAL PE.ASURD(DiT QUADRA.Yr READING MEASUIL N REF. PT. F74H WELD CDTER LDE O - 90 <H ~ lo 'l9 " 90* .yy "m f rem u.s 3</ '/2." o* eue 9r e y+" 90 3/9"w f 90-180 .yz 6" /80' 3/4" ed a 9s" 9/2." / go" 6i D/S .ys' 3%" 90* Jh* ni 190-270 'N " /" /bo* '/4"fo~d 4G" 572 27o 6 d. D/S ,9g 5/4 " 27o J/q'm f a 270-0 39' 33/q " 3/4" w f o zyo 39 O" O* @- { D/S .qz-z" o % ~4. ES1E07.C13A Page ef Rev. C1 Chg. C1

Service Water System Corrosion Monitoring Program f@l-k. Weld No. [O 70.3 Date /o-23-7f Line Show location and thickness of thinnest point in each sector T D C CTop Dead Csater of non ver6 cal p s in line with exttsdos of nearest elbow (for /- venical pipe) e-i i A Y l l 'I h i l s i i = i l Yf 3// l 4f .420s,2" 3 g LJ 42o e > p 4--- ys y f y 'O Iff yllj' 'D ty.o,' 5%" gg+*.%b 4Qo L y l f,, ?.M

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ULTRASONIC THICKNESS EXAMINATION REPORT i LOCATION SVJ tool-AoO t SYSTEM 50 WORK REQUEST 4moco -ruto I l EXAMINATION AREA /RESULTS DESCRIPT10N OF EXAM! NATION AREA AND RESULTS Y E L.0 $DIboi~hi00l sxETCH (inaue.oesruenora common.nm..mann on r.) g LEWL h CATE /d-TO 9:I EXAMIN _ -sw M LEVEL CATLO ' 44'9 i EXAMINED EXAMINATION RESULTS ACCEPTABLE EVALUATION REQ'O MEVIEWED MDATE h ( REVIEWED CATE W74Y!C**b0**//eej 5eaa cn boa Y i TTACHED M de d urn,u eal tm. 6a 44 f erc tm / /aela ios,r. M INSTRUMENT DATA INSTRUMENT; MFG /MODEL So usc l.3(c GTE/SN 6TE 2(8 4(.o TRANSOUCER [RT C CRTCIGfTAL [ OlGffAL ONTAL UNEARITY PERFORMED [ Hup nt8l.O PfTCH / CATCH COMP SURFACE TEMP >125' O ves F'S aa- "/^ c^'oueo^Tu "/^ ptsEi ECHO loo" l 3co" l.Soo4 /.Soo" MFO. MSE8 - R6 (o35o I (.o 33 0 ' (o 5 3 o (e#63 me oecmaD SER# C/_oB94 mt t _ ca ma m 9 20-9 6 i 9 70-9 8 i Q 20'9 6 ' 428 9 8 SIZE J M FREQ. N MHz /00 U .Sco" .Soo" (. COO" o230 "'8" ./ cod 3co" l 500 l /. 600 " o 925 COUPLANT errone l ~ MFG. (Jt.7thbtL S = . roo - i 3 0o " i Soo" i. So o" f f io BATCHs 0 9 2 t z. I ENGINEERING EVALUATION N/A ATTACHED SEE EELOW EVALUAT10% COMMENTS ACCEPT REPAJR/ REPLACE Responsible Engineer Cats Page 1 of 1 ES1807.012A Rw.1

SER7 ICE i:ATIR SYs IM CORROSION MONITORING PROGRAM Line No. /602 Weld No, IIO O / I4KEsT CIRC. FROM AIIAL MEASUREMENT QUADRAVT READING MEASUREMENT RIF. PT. FICM WELD CDem LINE O - 90 49" / '/2 ' o 3h % 4 4o~ vz" o e4 = o D/s 3 e" /" o" l'/v" rso,n 4 90-180 .'I6" / '/>

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Service Water System 3 Corrosion Monitoring Program s Line //3d2. Weld No. F/od/ Date /o. 20.p f Show location and thickness of thinnest point in each sector g{ Top Daed Cesser of amertical pipe or i

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m ULTRASONIC THICKNESS EXAMINATION REPORT LOCATION Sw I9;o2.- Fo9o2. SYSTEM $vJ WORK REQUESTiswom 6*o EXAANNATION AREA /RESULTS DESCRIPT1CN OF EXAMINATION AREA AND RESULTS NAleco 6W # 6o 2 - Fo go2_. l SKETCH (Induce oceruceone. componene, mesroons, seg {' LFd_ DATE /d-20 6 EXAMIN LEVELL DATE /8

• b PJ" EXAMIN r^-

EXAMINATION RESULTS AccEPTAsus ALuA11on neo D LEVEL 70 ATE /he' f [ REVIEWED l REVIEWED CATE i memouretse West ACHED INSTRUMENT DATA i INSTRUMENT; MFGAkODEL So o[c / 3(o GTE/SN GT6 '2 6 4 (.o O catcio' tat Oo'c'TAL ptZONTAL UNEARffY PERFORMED (AwprW) PrTCH / CATCH FLS No. A.1/A CAL DUE DATE ^J/4 COMP SURFACE TEMP >% 25* M O YES %LSE / ECHO N o*ess ./oo" !.300" I . 500". /.Soo" MFG. bis 66-f46 ad "0-0330 I (,33 o I (,3 3 O ' Gt B $ N8 D**eo SER# C/o G 9t/ ca m one 97048 i *r -7o 4 6 i 9 70 -9 B 9-2I-48 SIZE $ FREQ. '-/ MHz . Ico " l .3cC" 506" / Soo' / Z CO j sa== .so o " l 3co" l, 500 " i i, Sco" fq 4/o OUPWT mecx

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i ~ Service Water System q. Corrosion Monitoring Program s l Line /Fo2. Weld No. (ofd2 Date /d-20-9s' i. Show location and thickness of thinnest point in each sector a g{ Top Dead Caser of non unical pipe or i in Eas wish estrados of anansa show (for / aakai rire) j x Y l C8l O 1 8 f m h lE c. f 'l# O&3g 'N 4 h ,mw i' 39 gr 4 2 y =:;. =r m = - .,: p g ms.mgy g n:: - = y ;.- 3 2 - +.xa. ::Xfh St+i-h %,,. W A e* *

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s e ULTRASONIC THICKNESS EXAMINATION REPORT LOCATION et> /P/7_- #/6d 2 SYSTEM & WORK REQUEST 96weofA 1 EXAMINATION AREA #tESULTS DESCRIFUON OF EXAMINATION AREA AND RESULTS IJE%b 54)IEL L - fico 2 saTcw anauce oosruceans. oornoonene. mensons. era EXAMINED LEVEL CATE /f's h[ LEWLh CATE /0/rOh[ EXAMIN y'\\ Q EXAMINATION FIESULTS ACCEPTABLE EVALUATION REQ'O LEWL COATE /4d/ f REviEwso -( REVIEWED OATE memouronne Engeser TTACHED I INSTRUMENT DATA INSTRUMENT; MFG /hh00EL MA/iG / 36' GTE/SN 26/6 QcwT O caTaarr^' O o orrAt (HORLZONTAL UNEARffY PERFORMED hW/r#44) O erres iCATCH coup SURFACE TEMP >12S' @ OYES FLS No. M/A CAL DUE DATE A>/4 @[LSE/ ECHO /. 6 0 0 MFG. Mscn - kB noanne > /00 f,300 I.500 r &Yp na m 6330 l (s 4 to ! C.3.30 ' & / 53 mem SERN CdA94 V/2cip[ l Y/tc/ff n yk-bf 9/2//f[ SlZE. 5 FREQ. k MHz ca me one , /oc I , Mo , &cV /, <bo 19d I i COUPLANT w

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p' SERVICE WATER SYSTEM e CORROSION MONITORING PROGRAM Line No. I Weld No. F/ O o 2. LOWEST CIRC. FROM AXIAL MEASUREMENT QUADRANT READING MEASUREMENT REF. PT. FROM WELD CENTER LINE O - 90 b$ th ,500" . 7S fo ' c,a a:vs "'m D/S ,280" 3,7i' O* f/f 90-180 U/S e (s 20 ' /0,5' /20' /" 3go' 5,25" yo' brsM D/S 326 ll, { lE0 S o 180-270 J // e - // i380 ) 2 70 b U/S L/56 { '& 270* b5 SM g D/S 2co' 4 %' 2 70 ' W" Fi2 m q 270-0 i U/S /$00" lC 0 lj ' " j WELD e3 $0 ?r 0o j i D/S 260 2# 2 ?6 o NOTE l (i;cj2 (j,bT4

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Service Water System Corrosion Monitoring Program s Line jqt z Weld No. F 100 Z-Date /c-/E-9f Show location and thickness of thinnest point in each sector TDC T vertical pipe) '/ la line with extrados of nearest elbow (fot h l ?s t'C o'l i suffreT l* ~%ffed ?sPG lg E E' O!'" iE C . iro l .A AU' Y.no 2Y , uc = y J (1 5 V 5'A T 'p ' ,'{ D .,w . 3cc de V ,5y C ,5co m ,7ec A- ,0c 4 K l' j lo, l Vf 10 %,, y g O l 5 i l ?J i N 5 -~ ' Y 180 270 0 90 180 The location of the /Y/A Lowest (thinnest) reading does I does not R coincide with previous lowest reading (within 1") a Recorded by: m h_ Level % Date f o-/2-ff Reviewed by: // Date a/g//f ES1807.013 A Page I of 2 Rev. 01 Chg. 01 ff.f eb

) ULTRASONIC THICKNESS EXAMINATION REPORT f LOCATION SW # 007 - 6070 8 SYSTEM SW WORK REQUEST 95wooo S'/<o EXAMINATION AREA /RESULTS + f CESCRIPTION OF EXAMINATION AREA AND RESULTS J l \\bcLD 6 k3 I % 0 L - l~O ] O l 1 I I sxETCH onaues coeruconna corroonene. menneens, ec) a - LEVEL h CATE(0//o/9[ f EXAMINE < LB d CATE /d #/ 7 EXAMINE. u 7 EXAMINATION RESULTS ACCaPTABLE AWAT10N R9Q'O { ssi (/ LENEL [ CATE [ EVIEWE REVIEWED CATE Aescowene Emrear i ACHED .f uvM:.s i INSTRUMENT DATA INSTRUMENTi MFGMODEL S o o t c. /,$(o GTE/SN 6TE 264(.o gm OcaTaort^' O ciorr^' FoatzoNTn. uNEARrrY pERFcRuEo (A como O em== A/!A CAL QUE DATE ^!/A M O YES COMP SURF CE TE)'? >125-FLS No. %LSE / ECHO . /oo " l.3co" l. 5~oo " i /.500" MFG. M566-#6 _"<w, = 0350 l G330 l(o330 l Gio h me esecno SERA 06 99'l m~ caoa A 4 7o 90 l 97098I 9 20 fb' 9'11-98 StZE $ FREQ. 9 MHz ./00" 300" .icc* /5DCa l750 muu f oO " 3oo" l ..foo " i f Soo" /W O cuj MM l. goo' l. goon y goo - gy $o samm

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