Text

Emergency Relief Request to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section Xl, Division 1 for an Elbow
	ML14245A050
Person / Time
Site:	Peach Bottom
Issue date:	08/24/2014
From:	Massaro M; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML14245A050 (28)
	v • d • e

A-"

Exelon Generation 10 CFR 50.55a August 24, 2014 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Emergency Relief Request to Utilize Code Case N-513-3, Evaluatlon Criteria for Temporary Acceptance of Flaws In Moderate Energy Class 2 or 3 Piping Section Xl. Division 1 for an Elbow In accordance with the provisions of 10 CFR 50.55a(a)(3)(fl), Exelon Generation Company, LLC (Exelon) requests an emergency relief request to use Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1

for the evaluation of a through-wall leak Identified in a Class 3 service water piping elbow at Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, PBAPS, Units 2 and 3 was granted a Notice of Enforcement Discretion (NOED) at 1922 on August 23, 2014 for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months until 0100 on August 26, 2014. Exelon is requesting this relief until the conclusion of the fall 2014 refueling outage on PBAPS, Unit 2. The repair will be implemented no later than the completion of the fall 2014 refueling outage or before exceeding the temporary acceptance criteria of Code Case N-513-3 and this relief request, whichever comes first.

Exelon requests approval of the relief prior to the expiration of the NOED which will end at 0100 on August 26,2014.

On August 23, 2014 a pin hole leak was discovered on the Emergency Service Water (ESW) system on an elbow between check valve CHK-2-33-513 and hand valve HV-2 502. Exelon requests the use of Code Case N-513-3 for the analysis of this elbow to alow continued operation. Attached Is the reie request.

If you have any questions, please contact Mr. Thomas R. Loomis (610-765-5510).

Respectfully, Site ViePresident Peach Bottom Atomic Power Station Attachments: 1) Emergency Relief Request

2) Technical Evaluation

Emergency Relief Request Page 2 cc:

Regional Administrator, Region I, USNRC USNRC Senior Resident Inspector, PBAPS Project Manager, USNRC R. I. McLean, State of Maryland R. R. Janati, Commonwealth of Pennsylvania CCN 14-65 Emergency Relief Request Associated with the Deferral of Service Water System Repair in accordance with 10 CFR 50.55a(a)(3)(ii)

(Page 1 of 5)

1.

ASME CODE COMPONENTS AFFECTED:

a)

Section XI, Class 3, 90 degree elbow in Emergency Service Water (ESW) system between check valve CHK-2-33-513 and hand valve HV-2-33-502 b)

Examination Category D-B, Examination Item Number D2.10 c) 6" ferritic steel standard wall 900 elbow 0.280" nominal thickness d)

Design Code ASME B31.1 - 1967 e)

Design pressure 150 psig f)

Design temperature 100°F

2.

APPLICABLE CODE EDITION AND ADDENDA:

The applicable ASME Section XI Code Edition and Addenda for Peach Bottom Atomic Power Station, Units 2 and 3 is the 2001 Edition, through 2003 Addenda.

This fourth inservice inspection interval began November 5, 2008 and will conclude November 4, 2018.

3.

APPLICABLE CODE REQUIREMENT:

In accordance with ASME Code Section Xl, 2001 Edition, through 2003 Addenda, subparagraph IWD-3120(b) requires that existing flaws in ASME Code Class components which are unacceptable for continued service be corrected by repair/replacement activity or supplemental examination and analytical evaluation, to the extent necessary to meet the acceptance standards in ASME Code Section XI, Article IWC-3000. In regard to the flaw analysis, IWD-3500, "Acceptance Standards" for Class 3 components, states that the requirements of IWC-3500, "Acceptance Standards" for Class 2 components, may be used.

Additionally, IWA-4000 describes the repair/replacement activities to correct an unacceptable flaw. Detection of a minimum wall thickness in the structural portion of an ASME Code Class 1, 2, or 3 component is direct evidence of a defect in the component.

The Code does not include analytical evaluation criteria for acceptance of through-wall flaws in pressure retaining base material of ferritic pipe or fittings.

Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1," which has been conditionally approved by the NRC in Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 16, provides analytical evaluation rules for temporary acceptance of flaws in piping.

Code Case N-513-3 however does not apply to through-wall flaws located in the pressure retaining base material of pipe fittings such as elbows.

Attachment I Emergency Relief Request Associated with the Deferral of Service Water System Repair in accordance with 10 CFR 50.55a(a)(3)(ii)

(Page 2 of 5)

Relief is requested so that code repair of the through-wall flaw at this location may be deferred until the conclusion of the PBAPS, Unit 2 refueling outage which is scheduled for this fall, 2014 or before exceeding the temporary acceptance criteria of Code Case N-513-3 and this relief request, whichever comes first.

4.

REASON FOR REQUEST:

In accordance with the provisions of 10 CFR 50.55a(a)(3)(ii), Exelon Generation Company, LLC (Exelon) requests the use of Code Case N-513-3, "Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1" for the evaluation of a through-wall leak identified in a Class 3 ESW piping elbow at Peach Bottom Atomic Power Station (PBAPS),

Units 2 and 3. Exelon is requesting this relief until the conclusion of the fall 2014 refueling outage on PBAPS, Unit 2 or before exceeding the temporary acceptance criteria of Code Case N-513-3 and this relief request, whichever comes first. Application of the Code Case with additional criteria of this relief request assures that the elbow degraded area will retain structural and leakage integrity until a permanent Code repair is completed. The repair will be implemented no later than the end of the fall 2014 Unit 2 refueling outage.

Unit 2 and 3 Technical Specification 3.7.2, "Emergency Service Water (ESW)

System and Normal Heat Sink," Limiting Condition for Operation, requires "two ESW subsystems and normal heat sink shall be OPERABLE." At 1300 on Saturday, August 23, 2014, both ESW subsystems were declared inoperable, which required both units to be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and Mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

At 1922 on Saturday, August 23, 2014 a NOED was granted extending the time for both units to be in Mode 3 to 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months , which expires at 0100 on Tuesday August 26, 2014.

Without approval of this relief request, both units will be required to enter Mode 3 resulting in undue hardship without a compensating increase in safety. Moving both units to shutdown condition unnecessarily cycles the units and increases the potential of an unnecessary transient which can be avoided through the use of the N-513-3 analysis. No compensating increase in the level of quality and safety would be gained by immediate repair of the flaw. The ESW system continues to be capable of performing its required safety functions and is not susceptible to sudden or catastrophic failure.

Exelon proposes an alternative to the paragraph 1(c) provision of Code Case N-513-3 that prohibits its application to pipe fittings such as moderate energy Class 3 elbows. All other provisions of Code Case N-513-3, including scope expansion and walk downs, will be followed.

The ESW system is a Technical Specification required system that is designed to provide a reliable supply of cooling water to diesel generator coolers, Emergency Core Cooling Systems (ECCS) and Reactor Core Isolation Cooling (RCIC) compartment air coolers, Core Spray Pump Motor Oil Coolers and other selected equipment during design basis accident conditions or a loss of normal station Emergency Relief Request Associated with the Deferral of Service Water System Repair in accordance with 10 CFR 50.55a(a)(3)(ii)

(Page 3 of 5) service water due to the design flood condition or the loss of the Conowingo Pond. The system is designed to seismic Class I criteria. The ESW system has sufficient capacity and redundancy so that no single active component failure can prevent the system from achieving its safety objective. The ESW system is common to Unit 2 and Unit 3.

The ESW system consists of two full-capacity pumps installed in parallel and associated equipment coolers, valves, and controls. Normal water supply to the suction of the ESW system pumps is from the Conowingo Pond. Each pump has an independent discharge header, which supplies water to the coolers on all four Emergency Diesel Generators. These two independent headers combine upstream of each of the Emergency Diesel Generator (EDG) coolers. Discharge from the coolers feeds a common header and is normally routed to the discharge pond.

The ESW system may also be operated in conjunction with the emergency heat sink. This configuration (closed loop) is the preferred system alignment during the design flood condition or loss of Conowingo Pond.

Figure 1 - ESW Simplified Flow Diagram Excerpt (AO 33.6-0, Rev. 2, Page 4)

Emergency Relief Request Associated with the Deferral of Service Water System Repair in accordance with 10 CFR 50.55a(a)(3)(ii)

(Page 4 of 5)

Class:

The ESW piping is classified as safety related, ASME Code Class 3, and of moderate energy (piping design rating of 150 psig @ 100°F).

Flaw Characterization and Root Cause Determination:

An isolated, through-wall nonplanar flaw was found in the mid-extrados of the elbow between ESW hand valve HV-2-33-502 and check valve CHK-2-33-513 (IR 01695675) in the Reactor Building Closed Cooling Water room in a 6 inch header at floor elevation 116'. The nominal pipe thickness is 0.280 inch. This flaw was identified in a field walk down. The flaw leakage was measured to be approximately 3 mL/min. There are no electrical components in the general area that would be impacted by spray concerns. This is normally an insulated dead leg of piping with no known cavitation issues.

The flaw is characterized as approximately 0.6 inches in diameter (below Code minimum thickness) with a pinhole extending through the pipe wall but not beyond the extrados of the elbow. There are no other nonplanar flaws requiring group evaluations per N-513-3, Section 3.2. The remaining piping beyond the flaw is sufficient to maintain a pressure-retaining boundary and postulated leakage does not exceed operability margins. The nonplanar indication is the result of isolated pitting of carbon steel materials resulting from under deposit corrosion influenced by microbial activity and intermittent flow in raw water piping. Such corrosion indications are limited to localized areas under PBAPS' conditions and do not manifest in general thinning, cracking, or other prompt structural failure precursors. This isolated corrosion area can be reliably monitored to ensure flow and structural integrity are maintained.

5.

PROPOSED ALTERNATIVE AND BASIS FOR USE:

Exelon is requesting this relief until the conclusion of the fall 2014 PBAPS, Unit 2 refueling outage. The repair will be implemented no later than the completion of the fall 2014 Unit 2 refueling outage or before exceeding the temporary acceptance criteria of Code Case N-513-3 and this relief request, whichever comes first.

Exelon is proposing an alternative to the flaw evaluation methodology of Code Case N-513-3. The Code Case N-513-3 flaw evaluation methodology is applicable to straight pipe. The Exelon proposed alternative methodology is based upon and consistent with a pending revision to Code Case N-513-3 and is used to evaluate the flaw in the ESW elbow. The evaluation criteria provided in Code Case N-513-3 are only for straight pipe since the technical approach relies on ASME Section Xl, Appendix C methods. The pending revision of Code Case N-513-3 referenced above includes rules for the evaluation of pipe fittings such as elbows, branch tees, and reducers. Flaws in these fittings may be evaluated as if in straight pipe provided the stresses used in the evaluation are adjusted to Emergency Relief Request Associated with the Deferral of Service Water System Repair in accordance with 10 CFR 50.55a(a)(3)(ii)

(Page 5 of 5) account for geometric differences. For elbows, hoop stress is adjusted by considering flaw location and primary stress due to elbow ovalization from axial loads. For axial stresses, the stress scaling follows the same approach given in ASME Section III, ND-3600 design by rule using stress indices and stress intensification factors for the adjustment. Details are provided in the pending revision to Code Case N-513-3 for determining these adjusted stresses.

The approach to the evaluation methodology included in N-513-3 is to compute a static fracture toughness factor, Kic for the circumferential and axial flaw evaluations. For this evaluation, as shown in Attachment 2 of Technical Evaluation (TE) 1695675-03, the value of Kic is 94.780 ksi*in 0.5 This value is based on data extracted from the NRC Pipe Fracture Encyclopedia. The minimum value of 293 in-lb/in 2 for J1c from the encyclopedia was used in this evaluation. The evaluation then computes the stress intensification factors, K, for the circumferential and axial flaws for the various design modes (normal/upset and emergency/faulted) and then compares these values to the previously calculated value for Kic. If K, is less than or equal to Kic then the acceptability of the through-wall flaw is demonstrated. As shown in Attachment 2, the TE provides acceptable results.

Additionally, as required by N-513-3, the subject location was evaluated for the effect of thin wall on the normal piping stress and compared to the established design allowable stress for the piping. In this comparison, the allowable stress of 15,000 psi for the fitting material (A-234, Grade WPB) was used per the original design code. The results of this portion of the analysis, shown in the TE, demonstrate that a uniform pipe wall thickness of 0.100 inch is acceptable to provide adequate structural integrity for the design basis loadings.

Therefore, the attached TE provides the justification that the size of the flaw and the surrounding wall thickness is acceptable for continued operation within the requirements of the ASME Code Case N-513-3 and provides an acceptable level of quality and safety.

6.

DURATION OF PROPOSED ALTERNATIVE:

Exelon requests approval of this relief request prior to the expiration of the NOED which will end at 0100 on August 26, 2014.

This relief will be applicable until the repair is complete. The repair will be implemented no later than the completion of the fall 2014 refueling outage or before exceeding the temporary acceptance criteria of Code Case N-513-3 and this relief request, whichever comes first.

Technical Evaluation See attached Technical Evaluation 1 of 21

Title:

Evaluation of a through wall leak downstream of Unit 2 ESW check valve CHK-2-33-513.

ADMINISTRATIVE:

This evaluation was prepared in accordance with Exelon procedure CC-AA-309-l01, revision 14, Engineering Technical Evaluations.

A technical task risk/rigor assessment was performed for this activity in accordance with HU-AA-1212, revision 4. Risk rank was determined to be '1' with a medium consequence (C.6, Safety System Loss), 1 human performance risk factor (H. 11, Workload), and 1 process risk factor (P.3, Fast Track). Therefore, per table 5.1 of attachment 5 to HU-AA-1212 existing process reviews are adequate.

This conclusion was discussed with Jeff Chizever, Manager PEDM on 08/24/2014.

An impact review per CC-AA-102, revision 27 was performed and it was concluded that procedure revisions are not required. However, the Raw Water Program is impacted by this evaluation.

REASON FOR EVALUATION/SCOPE:

A 10 dpm leak was observed on the 6-inch diameter Emergency Service Water (ESW) piping on an elbow in the Reactor Building Closed Cooling Water (RBCCW) room between hand valve HV-2-33-502 (ESW to Unit 2 Safeguards Inlet Isolation Valve) and check valve CHK-2-33-513 (ESW to Unit 2 Safeguards Inlet Check Valve). The piping was covered with anti-sweat insulation at the time of discovery. The insulation was removed and a pin-hole leak was discovered on the extrados of the affected elbow (see photo, attachment page 16).

The presence of this through wall leak on an elbow warrants an evaluation in accordance with ASME Code Case N-513-4 (Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping, Mandatory Appendix I) in order to allow the associated piping to remain operable until a permanent repair is completed.

ASME Code Case N-513-4 is approved by ASME and is pending publication, but it has not been generically reviewed or approved by the NRC. A relief request has been prepared to allow the evaluation of the discovered through wall leak in accordance with ASME Code Case N-513-3 using the additional requirements form Code Case N-513-4 for the evaluation of through wall flaws in elbows.

DETAILED EVALUATION:

Engineering has performed an analysis of the degraded areas in accordance with ASME Code Case N-513-3 using the additional requirements of CC N-513-4 for evaluation of flaws in elbows. The affected elbow is 6-inch, schedule 40 carbon steel elbow (0.280 inch nominal thickness), SA-234 Grade WPB per Peach Bottom specification M-300 (Piping Materials) and P&ID M-315, sheet 5. The design pressure is 150 psig and the design temperature is 100 deg. F.

2 of 21

As shown on attached page 14, the area found to be less than the minimum wall thickness value of 0.100 inch is approximately 0.6 inch in the axial direction and 0.6 inch in the circumferential direction. Also, the surrounding area was examined by ultrasonic testing for information only to determine extent of the area with less than 87.5% of nominal wall thickness (i.e. 0.245 inch thick). As shown on attached page 14, the area below 87.5% of nominal thickness is approximately 2.9 inches axial by 3.6 inches circumferential.

In accordance with CC N-513-3, the pipe circumference at the location of the flaw was examined volumetrically to characterize the length and depth of all flaws in the pipe section. The results of the circumferential examination show that there are no other flaws in the area that are below the minimum wall thickness and need to be considered in this evaluation.

Forces, moments, and stresses for the subject piping were extracted from reference 5 at node point 151 and they are shown on pages 9 to 12 of the attachment.

The approach to the evaluation methodology included in CC N-513-3 is to compute a static fracture toughness factor, Kic for the circumferential and axial flaw evaluations. For this evaluation, as shown on attached page 2 of 16, the value of KIc is 94.780 ksi*in 0.5 This value is based on data extracted from the NRC Pipe Fracture Encyclopedia (reference 8). The minimum value of 293 in-lb/in2 for Jic from reference 8 was used in this evaluation. The evaluation then computes the stress intensification factors, K, for the circumferential and axial flaws for the various design modes (normal/upset and emergency/faulted) and then compares these values to the previously calculated value for Kic. If K, is less than or equal to Kic then the acceptability of the through wall flaw is demonstrated. The following is a summary of the results of the attached CC N-513-3 evaluation.

Kic = 94.780 ksi*in 0.5 K, Circ. Normal/Upset = 31.080 ksi*in°'S < 94.780 ksi*inO's, therefore acceptable.

K, Circ. Emer./Fault = 35.414 ksi*in°'S < 94.780 ksi*in°'s, therefore acceptable K, Axial (resultant moments and safety factors from faulted condition) = 50.862 ksi* in0.5 <

94.780 ksi*in°'s, therefore acceptable.

Alteration to CC N-513-3 evaluation methods required by CC N-513-4:

The hoop stress value (Gh) used in the axial through wall evaluation uses the equation 9 from CC N-513-4:

Uh = (pDo/2t)*(2Rbend +R& sino/2 (Rbend +Ro sin4)) + (1.95/h1 3 )*(RoMb/I) where:

p = maximum operating pressure at the flaw location. This computation conservatively uses the design pressure of 150 psi because maximum operating pressure has not been formally documented at this location (the max operating pressure is believed to be less than 100 psig).

3 of 21

Do = outside diameter = 6.625 inches t = thickness = 0.100 inch Rbend = elbow bend radius = 1.5

6-inches = 9 inches Ro = outside radius = 3.313 inches

= 90 degrees per CC N-513-4, figure 7 (sin90 = 1.0) h = flexibility characteristic per reference 2 = tn*Rbend/rmean 2 = 0.280*9/((6.625-0.28)2)2 = 0.25 which is > 0.1 as required by CC N-513-4, section 3.3.

Mb = resultant primary bending moment = SRSS of resultant moments from deadweight and SSE earthquake (attached page 8) = 21129.12 in-lbf 1= moment of inertia at t = 0.100 inch= 0.0491(Do4 -Dinside4) = 10.915 in4 Therefore, ah is computed as:

Gh = 4968.75 psi*(0.865) + 4.937*(6413.264 psi) = 35960.252 psi The circumferential flaw evaluation uses the P2 primary stress index from ASME Section III, subsection NB-3683.7 as required by CC N-513-4, section 3.3. P2 is computed as 1.30/h 213 = 1.30/0.395 = 3.291 and inserted into the calculation for Krb.

Additionally, as required by CC N-513, the subject location was evaluated for the effect of thin wall on the normal piping stress and compared to the established design allowable stress for the piping. In this comparison, the allowable stress of 15,000 psi for the fitting material (A-234, Grade WPB) was used per the original design code (reference 2). The results of this portion of the analysis, shown on attached pages 1 through 8, demonstrate that a uniform pipe wall thickness of 0.100 inch is acceptable to provide adequate structural integrity for the design basis loadings.

CONCLUSIONS/FINDINGS:

This evaluation of the discovered pin-hole leak provides the justification that the size of the flaw and.the surrounding wall thickness is acceptable for continued operation within the requirements of ASME Code Case N-513-3.

REFERENCES:

1. ASME Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping

2. ASME B31.1, Power Piping, 1967and 1973 Editions

3. ASME Section XI, Rules for In-Service Inspection of Nuclear Power Plant Components, 2001 Edition plus addenda through and including 2003

4. Crane Technical Paper 410, Flow of Fluids

5. PBAPS Calculation 33-32, PIPE STRESS ANALYSIS - ESW SYSTEM UNIT 2 RBCCW ROOM, revision lb

6. IR 1695675, LEAK THROUGH INSULATION ON ESW PIPING

7. Isometric ISO-2-33-17, revision 5

8. Pipe Fracture Encyclopedia, NRC, Volume 1, 1997

9. ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of 4 of 21

Flaws in Moderate Energy Class 2 or 3 Piping ATTACHMENTS:

Pages 1-8:

Pages 9-12:

Pages 13-15:

Page 16:

Approvals:

Prepared By:

Reviewed By:

ASME Code Case N-513-3 Evaluation Excerpts from calculation 33-32 NDE Report Photo of the Leak Ken Hudson 08/24/2014 08/24/2014 Mohamed Kazoun Independent Design Review Comments:

This Technical Evaluation conforms with applicable design & configuration control requirements. The inputs, references and computations were reviewed and found to be correct.

Computations that were performed by Excel were confirmed by hand computations. The method used for this evaluation is based on an ASME Code Case that is approved by ASME and pending publication by the NRC. Design considerations were identified and were adequately addressed.

I concur with the conclusions/findings that are stated in this technical evaluation.

Approved By:

Jeff Chizever, Manager PEDM 08/24/2014 5 of 21

Technical Evaluation 1695675-03 Attachment of' I6 MraWil SI Elbow IlYs from CHlK-2-33.S13*

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I 6 of 21

Technical Evaluation 169567S.03 Attachment 2 of /6L I

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Technical Evaluation 1695675-03 Attachment

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END OF ASME CODE CASE N-413.4 EVALUATION 9 of 21

Technical Evaluation 1695673-03 Attachment 5

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4

.9

.9-6 I

A I.

I 12 of 21

Technical Evaluation 1695675-03 Attachment

? of 1 Evaluation Input Data From Calculation 33.32 evl.Node Pl~~

Fa Fb Fc Ma Mb MO Mr PSI a Weight 80 99 16 32 58 93 114.18 262 Thermal 0

0 0

0 0.00 C

OBE 258 449 127 394 293 479 685.95 158C SSE 619 1076 304 947 703 1149 1646.58 3792 a

Allowable a Preour a 776 Equ. 11 a 1039 15,000 Equ. 12b a 2619 18,000 Equ. 12d a 4831 36,0001 Equ. 13 a N/A I

13 of 21

Al-l,% W El I fl T 86 TNGT 126 126 TNGT 131 131 HV-2-33-502 141 141 BEND 151 N 151 M BEND 156 156 CHK-2-33-513 161 161 TNGT 171 171 TNGT 176 176 TNGT 181 181 mo-2972 186 181 TNGT 191 191 TNGT 198 1

ELEMENT TYPE/rTULE FROM TO

-21 20

-14 14

-1O U0 141 16 97

-16

-97 16 88

-16 9

16

-9

-16 107

-14

-80 99 80

-99 14 146

-14 234 14

-234

-14 321 14

-345 L14

-56 029 56 S54

-56 S54 S6 0

190 0

-190 164

-56 164 56 089

-56

-I 355 56 LOCAL FORCES (LB)

FA FB 14 14 14 14 14 14 16 16 16 16 16 16 16 16 56 56 56 56 0

0 56 56 56 56 0:

21

-21 21

-21 21 32

-32 60

-60 60

-60 60 70

-70 70

-70 0

0 70

-70 70

-70 LOCAL IPA 70

-70 70

-70 70 7

-7 31

-31 31

-333 333 90

-90

-159 145

-148 145

-145 126

-72 58

-5&

10 10 9

-9 20 16

-63 569

-523 0

0 523

-478 478

-459 MOMENTS MB 459

-346 346

-115

-us 72

-72

-13

-13 333 31 51

-44 290

-10

-97 97

-93 93

-72

-126 93

-93 17 17 255

-255 495

-615 569 63

-109 713 0

-604 557

-557 539 (FT-LB)

"C

-539 424

-424 190 190 21

-21 301 301 326

-326 212 121

-355 185.

184.

362.

235.

125.

109.

338.

262.

146.

47.

195.

356.

822.

269.

153.

82.

76.

0.

113.

104.

196.

189.

STRESS (PSI

.751H/z 1.843 2.000 2.000 1.000 1.000 1.000 2.266 2.266 2.266 2.266 1.000 1.000 1.000 2.172 2.172 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 STRESS INT. FAC.

(I) 1.000 1.000 1.000 1.000 2.862 2.862 2.562 2.562 1.000 1.000 1.000 1.000 2.172 1.000 1.000 1.000 1.000 1.000 1.000 1.000 6.590 6.590 6.590 6.590 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 FLEX.

IN PLANE 1.000 1.000 1.000 1.000 9.359 9.359 9.359 9.359 1.000 1.000 1.000 1.000 1.000 1.000 1.000 831573 1.000 1.000 B31s73 1.000 1.000 B31573 1.000 6.590 831573 6.590 6.590 B31573 6.590 1.000 s31573 1.000 1.000 B31S73 1.000 1.000 B31S73 1.000 1.000 B31S73 1.000 1.000 B31S73 1.000 1.000 B31S73 1.000 1.000 B31S73 1.000 FLEX.

CODE OUT AND PLANE CLASS 1.000 B31S73 1.000 1.000 B331S73 1.000 9.359 B31S73 9.359 9.359 B31573 9.359 1.000 a3lS73 1.000 1.000 B31573 1.000 1.000 B31S73 1.000

)

198 201 201 206 s 206 s 206 M 206 1 206 E 206 E 207 207 208 171 209 TNGT TNGT BEND

-1055 848

-848 424

-424 175

-175

-56 56

-56 402

-484

-2459 2807

-56

-56 56 56

-56

-56 56 56 56 56

-255

-56 255 56

-184

-56

-184

-56

-402 56

-56

-56 56 56

-69

-72 69 72 189.

147.

62.

133.

43.

173.

80.

124.

181.

156.

68.

125.

(A)

-4" TNGT Page 4

0E3EIM1, 84 TNGT 66 o

86 TNGT 391 130 959 109 130 959 109 1097 477 169 1097 477 169 LOCAL FORCES (LB) 521 107 521 153 280 463 280 401 LOCAL MOMENTS o1 0*

1 ELEMENT TYPE/TITLE FROM TO 91 HV-2-33-503 101 101 TNGT 106 106 TNGT 111 111 TNGT 112 1m1 TNGT 113 86 TNGT 126 126 TNGT 131 131 HV-2-33-502 141 141 BEND 151 m 151 M BEND 156 156 CHK-2-33-S13 161 161 TNGT 171 171 TNGT 176 176 TNGT 181 181 mO-2972 186 181 TNGT 191 191 TNGT 198 FA 1104 1104 1118 486 488 488 0

0 0

0 325 325 325 325 324 324 323 258 258 404 386 386 370 370 123 123 122 122 37 37 109 109 109 109 FB 475 475 475 267 551 551 0

0 0

0 132 132 131 131 129 129 404 449 449 323 322 322 322 322 123 123 74 74 113 113 90 90 149 149 FC 173 173 179 548 267 267 0

0 0

0 437 437 434 434 422 422 127 127 127 127 123 123 118 118 108 108 115 us 173 173 144 144 111 111 MA 280 280 280 768 768 768 0

0 0

0 491 491 491 491 491 491 491 394 394 155 155 155 155 155 548 548 548 548 0

0 469 469 469 469 MB 401 325 325 1131 133 240 0

0 0

0 872 529 529 433 433 297 88 293 293 428 428 361 361 334 1116 1145 941 919 650 0

919 866 866 841 1716 2355 1861 1598 CFT-LB)

PC 1598 973 973 133 1131 1673 0

0 0

0 296 192 192 162 162 88 297 479 479 637 637 900 900 1094 967 941 1145 1115 425 0

1188 1122 1122 1073 1237.

2299.

3155.

2266.

STRESS (PSI 1240.

789.

1019.

1861.

3577.

0.

993.

771.

1518.

915.

501.

431.

1338.

1580.

1802.

580.

728.

1330.

1904.

683.

420.

224.

219.

0.

223.

211.

397.

384.

1.000 1.000 1.000 1.000 1.000 2.538 2.538 1.000 2.538 1.000 1.843 2.000 2.000 1.000 1.000 1.000 2.266 2.266 2.266 2.266 1.000 1.000 1.000 2.172 2.172 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 6.590 6.590 6.590 6.590 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.063 1.000 1.843 1.000 1.843 1.000 1.000 1.000

)

STRESS FLEX.

INT.FAC.

IN (I)

PLANE 1.000 B31573 1.000 1.000 B31573 1.000 FLEX.

CODE OUT AND PLANE CLASS 1.000 B31S73 1.000 1.000 B31S73 1.000 1.000 B33173 1.000 1.000 B31s73 1.000 1.000 B31573 1.000 1.000 B31573 1.000 1.000 s31s73 1.000 1.000 631573 1.000 6.590 B33173 6.590 6.590 s31s73 6.590 1.000 B3UM73 1.000 1.000 531573 1.000 1.000 B31S73 1.000 1.000 B31573 1.000 1.000 031s73 1.000 1.000 B31s73 1.000 1.000o B3373 1.000 3 0 A1

'--% D 1

Page 13

e-elw rý Z>-'-Yt

SEISMK, w

(V 0

68 68 TNGT 71 71 TNGT 76 a 76 B BEND 76 m 76 m BEND 76 E 76 E TNGT 813B 81 3 BEND 81 N 81 N BEND 83 83 TNGT 84 84 TNGT 86 86 TNGT 91 ELEMENT TYPE/TITLE FROM TO 91 Hv-2-33-503 101 101 TNGT 106 106 TNGT 111 111 TNGT 112 111 TNGT 113 86 TNGT 126 126 TNGT 131 131 HV-2-33-502 141 141 BEND 151 M 894 334 902 333 902 333 910 333 2217 558 2230 247 2147 652 2147 652 1738 1419 1748 559 1748 559 1765 560 1641 859 1641 859 560 1765 319 2290 319 2290 313 2301 313 2301 2633 1144 2633 1144 LOCAL FORCES FA FS 2649 1141 2649 1141 2682 1140 1166 641 1171 1323 1171 1323 0

0 0

0 781 317 781 317 780 316 780 316 778 311 778 311 776 969 619 1076 506 507 507 510 246 559 559 559 559 1427 1427 1440 1440 1440 1440 259 259 262 262 406 406 (LB)

FC 414 414 429 1315 642 642 0

0 0

0 1048 1048 1041 1041 1012 1012 304 304 139 139 139 139 72 72 646 646 1213 1213 1213 1213 1142 1142 1251 1251 1251 1251 1251 6nl 672 LOCAL MA 672 672 672 1844 1844 1844 0

0 2168 2168 1657 1657 1315 1430 1506 1506 1354 831 348 348 209 209 269 435 258 258 367 1111 963 MOMENTS "a

963 779 779 2713 320 576 0

0 671 671 520 520 1430 1315 1228 1228 831 1354 1574 1574 1S45 1454 430 249 4119 4119 5651 4467 3836 (FT-LB)

MC 3836 2336 2336 320 2713 4016 0

0 0

0 710 461 461 390 390 211 713 1149 1565.

1565.

1199.

1338.

2447.

2578.

2517.

1376.

1389.

2540.

2342.

1699.

927.

2968.

5517.

7578.

5437.

STRESS (PSI 2976.

1893.

2445.

4467.

8584.

0.

2383.

1850.

3644.

2195.

1201.

1034.

3212.

3792.

1.000 1.000 1.000 1.000 1.000 2.439 2.439 2.439 2.439 1.000 1.000 2.439 2.439 2.439 2.439 1.000 1.063 1.063 1.843 1.843 1.000

)

STRESS INT. FAC.

(W) 1.000 1.000 1.000 1.000 1.000 2.538 2.538 1.000 2.538 1.000 1.843 2.000 2.000 1.000 1.000 1.000 2.266 2.266 1.000 1.000 1.000 1.000 1.000 7.360 7.360 7.360 7.360 1.000 1.000 7.360 7.360 7.360 7.360 1.000 1.000 1.000 1.000 1.000 1.000 FLEX.

IN PLANE 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000 6.590 6.590 1.000 1.000 B31s73 1.000 1.000 B31S73 1.000 7.360 531573 7.360 7.360 B31s73 7.360 1.000 831S73 1.000 7.360 B31573 7.360 7.360 B31S73 7.360 1.000 B31573 1.000 1.000 B31573 1.000 1.000 B31s73 1.000 FLEX.

CODE OUT AN PLANE CLASS 1.000 B31S73 1.000 1.000 B31573 1.000 1.000 B31573 1.000 1.000 B31573 1.000 1.000 B31573 1.000 1.000 331573 1.000 1.000 331573 1.000 1.000 331s73 1.000 6.590 831573 6.590 0

0 0

0 1180 2093 1180 1268 1180 1268 1180 1039 1180 1039 1180 713 1180 211 947 703 Page 22

5UfL1(fARlf/

ELEMENT FROM TYPE TO TITLE 141 BEND 151 N 151 N BEND 156 156 TNGT 161 CHK-2-33-513 161 TNGT 171 171 TNGT 176 176 TNGT 181 181 CWPT 186 MO-2972 181 TNGT 191 191 TNGT 198 198 TNGT 201 201 TNGT 206 a 206 a BEND 206 m 206 M BEND 206 E 206 E TNGT 207 207 TNGT 208 SUSTAINED LOAD EQN 11 PD/4T CALC ALLOW PSI PSI PSI 776 1115 15000 1039 15000 776 1039 15000 922 15000 335 382 15000 529 15000 776 1132 15000 1599 15000 1164 1432 15000 1317 15000 527 609 15000 604 15000 0

0 15000 0

15000 527 641 15000 632 15000 1164 1360 15000 1353 15000 1164 1353 15000 1311 15000 1164 1311 150o0 1226 15000 1164 1297 15000 1207 15000 1164 1207 15000 1336 15000 1164 1244 15000 1288 15000 993 1174 15000 1150 15OOO LEVEL B EQN 12 PD/4T CALC ALl PSI PSI 1

776 2453 183 2619 18 776 2619 18(

2725 18(

335 962 18(

1257 18(

776 2463 18(

3503 18(

1164 2.15 18(

1737 18(

527 832 18(

822 184 0

0 18(

527 863 18(

543 18(

1164 1757 184 1736 18 1164 1736 18C 1607 184 1164 1607 18(

1413 18(

1164 1699 184 1638 18 1164 1638 184 1751 18(

U"64 1437 18(

1646 154 993 1696 184 1749 184 OCCASIONAL LOAD LEVEL C EQN 12 LOW CALC ALLOW PSI PSI PSI

)00 0

0 300 0

0 D00 0

0 300 0

0 00D 0

0

)0O 0

0 D00 0

0 300 0

0 D00 0

0 o00 0

0 W00 0

0 300 0

0 100 0

0 300 0

0 3O0 0

0 D00 0

0 300 0

0 000 0

0 D00 0

0 300 0

0 OD0 0

0 LEVEL D EQN 12 CALC ALLOW PSI PSI 4327 36000 4831 36000 4831 36000 5248 36000 1775 36000 2276 36000 4325 36000 6169 36000 3071 36000 2326 36000 1145 36000 1128 36000 0

36000 0

36000 1175 36000 1138 36000 2313 36000 2274 36000 2274 36000 2021 36000 2021 36000 1675 36000 2262 36000 2241 36000 2241 36000 2331 36000 1707 36000 2147 36000 2427 36000 2587 36000 PSI 0

0 0

0 00 0

0 0

0 PSI 0

0 0

0 EXPANSION EQNS 13/14 CALC ALLOW

"-,I ANCHOR NOV EQN ***

CALC ALLOW PSI PSI 0

0 0

0 o

0 0

0 MON-REPEATED CALC ALLOW EXCEEDED ALLOWABLE IN EQUATION 13, EQUATION 14 USED EXCEEDED ALLOWABLE 1

CODE B31S73 ELEMENT FROM TYPE TO TITLE SUSTAINED LOAD OCCASIONAL LOAD LEVEL B LEVEL C EQN11 F.QU J2.

F.

12 PD/4T CALC ALLOW PD/4T CALC ALLOW CALC ALLOW Page 33 THERMAL EXPANSION LEVEL D EQN 12 E(ws 13/14 CALC ALLOW CALC ALLOW

"7E 16J5615t-03 A-TTAC,4M6Jr PA 4q E 13 OPF146 RAW WATER CORROSION

--ExelonGeneration.

ULTRASONIC EXAMINATION REPORT FORM NDE SUPPORT GROUP WORK ORDER # C0253806-04 STATION I UNIT I

PBAPS UNIT 2 EXAM AREA WELD STRAIGHT (X-ONE)

I I

I X I EXAM LOCATION =

I HV-2-33-502 U/S PIPE NOMINAL WALL

.280" EXAM POSITION HORIZ VERT PIPE MINIMUM WALL

.100" (X-ONE)

[

I

[ X I

PIPE D."

ELEV.

116' AREA U 2OOM uORBCCW INSTRUMENT:

figr.

Olympus Model:

37DL Plus Se i 14 SPECIAL GRIDING: NIA SEARCH UNIT:

Mfgr, Panametrics S/N:

810577 Make:

D798 Size:

.283" Frequency:

7.5 Mhz Couprent Humex /04165 Reference Block 2878320 CALIBRATION TIMES:

Initial:

15:00 Final:

19:00 Other N/A THERMOMETER:

0002630031 Due 102W114 CAL TEmp 70° comp,p 785 DRAWING (11 Applicable)

HV-2-33-602 UIS Elbow Sao UT Data Shoot For Readings COMMENTS:

Thru Wall leak was identied on extredose of ebow.

Callbration Reference Procedures ER-AA-335-004 REV. 7 & Mag-CG-409 REV.3 Actual Meas.

Reference Acceptance Criteria per Min-Wall and Eraneering Direction AR A1966M3 E03

.600"

.600" Surface Condition a Propped, Paint Removed. Mluteira: Carbon Steel.

.400(

.400"

.300"

.300" Jinue Martin II

/

8/23/14

.200"

.200" NAME I LEVEL DATE NAME I LEVEL DATE

.100"

.100" Page 1 of 3 18 of 21

TEI6'r'5415-o3 A FAei"AMwr

(>A & 14 OF16 HV-2-33-502 UIS Elbow IEngmwt r1w I

AXIAL

.600"

.A00" Lm(m)-.600" Lm(o).600" Isobar otA to 87.5% d Noinil Wag Thickness vdch i.245" Notural Wall Tluc 13.2W.

II Page 2 of 3 19 of 21

me I6165 604 WATER CORROSION, ULTRASONIC EXAMINATION REPORT FORM WORK ORDER # C0253800-04 NDE SUPPORT GROUP HV-2-33-502 UIS Elbow Jsm. mat 11 18/23114 1

NAME I LEVEL DATE NAME I LEVEL DATE Page 3 of 3 20 0o" 21

A1TTAC REWr mq C.- l(p o r-

ML14245A050

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