RNP-RA/03-0160, Response to RAI for Relief Request Pertaining to Examination Coverage Less than Essentially 100 Percent (Relief Request No. 34)

Response to RAI for Relief Request Pertaining to Examination Coverage Less than Essentially 100 Percent (Relief Request No. 34)

ML040410062
Person / Time
Site:	Robinson
Issue date:	12/30/2003
From:	Baucom C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/03-0160
Download: ML040410062 (185)

Text

Progress Energy 10 CFR 50.55a Serial: RNP-RA/03-0160 DEC 3 2003 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST PERTAINING TO EXAMINATION COVERAGE LESS THAN ESSENTIALLY 100 PERCENT (RELIEF REQUEST NO. 34)

Ladies and Gentlemen:

In accordance with 10 CFR 50.55a(g)(6)(i), Relief Request RR-34 was submitted for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, by letter dated February 11, 2003.

A request for additional information (RAI) was received from the NRC by letter dated November 6, 2003. That RAI requested a reply no later than December 30, 2003.

The response to the RAI is provided in the attachment to this letter.

If you have any questions regarding this matter, please contact me.

Sincerely, 6Q1~ &

C. T. Baucom Supervisor - Licensing/Regulatory Programs CTB/cac Attachment c: Mr. L. A. Reyes, NRC, Region II Mr. C. P. Patel, NRC, NRR NRC Resident Inspector Progress Energy Carolinas. Inc.

AoN7 Robinson Nuclear Plant 3581 West Entranre Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 1 of 184 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RESPONSE TO REQUEST FOR ADDITONAL INFORMATION FOR RELIEF REQUEST PERTAINING TO EXAMINATION COVERAGE LESS THAN ESSENTIALLY 100 PERCENT (RELIEF REQUEST NO. 34)

By NRC letter dated November 6, 2003, the following request for additional information (RAI) was provided:

The licensee has requested relief in accordance with 10 CFR 50.55a(g)(5)(iii) based upon the argument that the Code examinations are impractical at their facility. However, the licensee must present adequate information to support a determination that the required examinations are impractical (not simply inconvenient) to perform to the extent required by the Code. This information should include drawings, or other physical descriptions, of the component examination areas, including examination coverage(s), weld cross-sections, etc.,

necessary to support the request. In addition, the licensee should submit argument(s) as to why the use of other methods would not reasonably increase the examination coverage(s).

In Attachment I for Relief Request 34 of the licensee's submittal (Table 1 on page 2 of 9),

the limitation discussion for Reactor Vessel Upper Shell Welds states that the reduced volumetric coverage (90 percent) is due to "proximity of the inlet nozzle inner radius section." This discussion does not provide an adequate description of the physical limitation or indicate whether other techniques such as different interrogation angles could have practically increased the coverage.

Similar issues exist with the remainder of the components listed in Table 1. The drawings provided by the licensee are inadequate to determine the extent of actual scanning limitations. The licensee should address the following issues in the revised relief request:

• Provide a technical basis for each component listed in Table 1, describing in detail the examination limitation, and discuss whether other examinations may be used to increase or supplement the limited examinations. The technical basis should include a cross-sectional sketch of the weld, indicating ultrasonic coverage(s) and details of the weld and base metal materials. The technical basis should confirm, where applicable, that the examinations that were performed were also qualified under Appendix VIII of ASME Section XI.

• Indicate what degradation mechanism(s) is most likely to occur in this weld and a technical basis for whether the achieved examination coverage could reasonably be expected to detect this degradation.

The following information is provided in response to this RAI:

The submittal dated February 11, 2003, included component and layout drawings. Those drawings have not been repeated in this RAI response.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 2 of 184 In response to the question pertaining to degradation mechanisms, the following information is provided to supplement discussions in the previous submittal and the RAI responses included in this submittal:

The material combinations being inspected include 316 stainless piping welds; CF8 cast pipe to 304 forging; 304 plate to CF8 casting; 316 pipe to carbon steel casting; low alloy steel forgings to alloy steel plate; and, buttered cast low alloy steel to stainless pipe.

The types of degradation that could possibly be seen in the welds inspected include corrosion and fatigue. Corrosion occurs as either intergranular or transgranular cracking and surface pitting or roughening. Fatigue failure in any of the welds will appear in the form of cracking.

However, the probability of these occurring is very low due to the material choices for the environments, and the design of the welds. The welds exposed to primary coolant are produced without backing to preclude crevice effects and are either back-gouged and welded on the ID or clad with stainless to protect low alloy steel components. The low alloy steel exposed to secondary fluid, which is specifically treated to prevent corrosion, has shown no degradation to date.

If degradation has occurred in non-examined areas, it is likely that Code-required pressure testing would detect leakage associated with these systems and components.

AUTOMATED CATEGORY B-A EXAMINATIONS Component(s) for Which Relief is Requested The components applicable to this relief request are the H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2, reactor pressure vessel (RPV) nozzle-to-vessel welds with identification numbers 101/03, 101/06, 101/07, 101/22, 101/23, 101/24, 101/25, 101/26, 101/27, and 101/28.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Category B-A, Item Numbers B1.11, B1.12, B1.21, B1.22, and B1.30. The applicable Code examination requirements, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 3 of 184 Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Category B-A, Item Numbers BI.1 1, B1.12, B1.21, B1.22, and B1.30, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e.,

coverage is greater than 90%). The examination coverage achieved for the components listed in Table 1 are the maximum extent practical for these components. Table 1 lists the coverage that was achieved and the reason for the limitation. Table 2 identifies the material associated with these welds, and Table 3 is an excerpt from the ISwT Reactor Vessel Scan Plan.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Automated ultrasonic examinations were performed on the HBRSEP, Unit No. 2, reactor vessel in accordance with the requirements of 10 CFR 50.55a, the Technical Specifications, and the 1986 Edition of the ASME Section XI Code. These examinations had ten B-A welds that could not achieve the required 100% (>90%) coverage. The following descriptions, coupled with the tables and figures, are the requested details of the examination limitations. The accompanying figures graphically depict the extent of the limitations. The table quantifies the extent of Code-required volume that was examined.

During the review process it was determined that welds 101/14, 101/15, and 101/16 had coverage in excess of the required 90% and these welds are not included in this submittal.

RPV Lower Head Meridional Welds Automated scanning of the RPV lower head meridional welds (101/23, 101/24, 101/25, 101/26, 101/27, and 101/28) was limited due to interference from the instrumentation tubes and the core support lugs. Figure is a roll-out inside view of the reactor pressure vessel showing the scan limitations. Figure 2 provides a side section view of the meridional welds showing the limited scanning areas.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 4 of 184 RPV Circumferential Lower Head Welds The automated scanning of the lower head ring-to-lower head weld (101/07) was limited due to interference from the lower head bottom-mounted instrumentation (BMI) tubes. Figure 1 is a roll-out inside view of the reactor pressure vessel showing the scan limitations. Figure 3 shows a top view of the parallel scanning limitation and a side view of the transverse scanning limitations.

Examination of the lower head-to-lower shell weld (101/06) was limited due to interference from the core support lugs. Figure 1 shows the inside roll-out view and Figure 4 shows a side view of the limited area.

RPV Longitudinal Lower Shell Weld Examination of the lower shell longitudinal weld (101/22) was limited due to interference from the core support lug at 00. Figure 1 is a roll-out inside view showing scan limitations. Figure 6 shows the side view of the limited area.

RPV Upper Shell-to-Flange Weld The transverse examination of the upper shell-to-flange weld (101/03) was limited due to the flange configuration. The tapered surface on the flange side did not allow transverse scanning.

Figure is a roll-out inside view showing scan limitations. Figure 5 shows a side view of the limited area.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 5 of 184 TABLE 1 REACTOR VESSEL COVERAGE AND LIMITATIONS Weld Item Description Coverage Limitation 101/03 B 1.30 Upper Shell to Flange 73% Limited examination due to I_________

________ ____________ proximity of flange taper.

101/06 B1.11 Lower Head to Lower Shell 82% Limited due to proximity of Weld core support lugs.

101/07 B 1.21 Lower Head Ring to Lower 5% Limited due to proximity of Head lower head bottom-mounted instrumentation (BMI) tubes.

101/22 B1.12 Lower Shell Longitudinal 73% Limited due to proximity of Weld @ O° core support lug.

101/23 B 1.22 Lower Head Meridional 63% Limited due to proximity of lower head BMI tubes.

101/24 B 1.22 Lower Head Meridional 44% Limited due to proximity of lower head BMI tubes and core support lug at 00.

101/25 B 1.22 Lower Head Meridional 66% Limited due to proximity of lower head BMI tubes.

101/26 B 1.22 Lower Head Meridional 56% Limited due to proximity of lower head BMI tubes.

101/27 B 1.22 Lower Head Meridional 44% Limited due to proximity of lower head BMI tubes and core support lug at 270°.

101/28 B 1.22 Lower Head Meridional Limited due to proximity of 69% lower head BMI tubes.

United States Nuclear Regulatory Commission Attachmcnt to Serial: RNP-RA/03-0160 Page 6 of 184 TABLE 2 REACTOR VESSEL MATERIAL AND WELD IDENTIFICATION WELD CODE CODE DESCRIPTION MATERIAL 1 WELD MATERIAL 2 ID CATEGORY ITEM #

101/03 B-A B 1.30 REACTOR VESSEL SHELL TO FLANGE FLANGE RACO3 + Ni200 SAW UPPER SHELL SA-336 SA-302 GR B 101/06 B-A Bl.1 I REACTOR VESSEL LOWER SHELL TO LOWER LOWER SHELL RAC03 + Ni200 SAW LOWER HEAD HEAD SA-302 GR A SA-302 GR B 101/07 B-A B1.21 REACTOR VESSEL LOWER HEAD TO LOWER LOWER HEAD RACO3 (SAW) & LOWER HEAD HEAD RING WELD SA-302 GR B E8018 DOME SA-302 GR B 101/22 B-A Bl.12 REACTOR VESSEL LOWER SHELL UPPER SHELL RACO3 (SAW) & UPPER SHELL LONGITUDINAL WELD @ 00 SA-302 GR B E8018 SA-302 GR B 101/23 B-A B 1.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD WELD @ 30° SA-302 GR B E8018 SA-302 GR B 101/24 B-A B1.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD WELD @ 900 SA-302 GR B E8018 SA-302 GR B 101/25 B-A B 1.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD WELD @ 150 SA-302 GR B E8018 SA-302 GR B 101/26 B-A Bl.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD WELD @ 210° SA-302 GR B E8018 SA-302 GR B 101/27 B-A B 1.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD WELD @ 270° SA-302 GR B E8018 SA-302 GR B 101128 B-A B 1.22 REACTOR VESSEL LOWER HEAD MERIDIONAL LOWER HEAD RACO3 (SAW) & LOWER HEAD

._______ ______~WELD@ 330° SA-302 GR B E8018 SA-302 GR B

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 7 of 184 TABLE 3 REACTOR VESSEL SCAN PLAN WELD EXAM AREA EXAM BEAM EXAM BEAM DIRECTIONS CODE LIMITATIONS NUMBER IDENTIFICATION VOLUME FIGURE ANGLE(S) TYPE COVERAGE

__________________ _________ ~~~~~~~~~~~~~~(CRV) 101/03 REACTOR VESSEL A 4 SLIC 40 PARALLEL 2 DIRECTIONS 92% Limited examination due to the FLANGE TO UPPER SHELL B 550 PARALLEL 2 DIRECTIONS 92% proximity of the flange taper and the A SLIC 40 TRANSVERSE 2 DIRECTIONS 53% outlet nozzle integral extension.

B 55° TRANSVERSE 2 DIRECTIONS 53%

_ __ _ _ _ _ __ __ __ _ __ _ _ _ __ __ __ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _73% CR 101/06 REACTOR VESSEL LOWER A 2 SLIC 40 PARALLEL 2 DIRECTIONS 87% Limited examination due to the HEAD TO LOWER SHELL B 550 PARALLEL 2 DIRECTIONS 87% proximity of the core barrel A SLIC 40 TRANSVERSE 2 DIRECTIONS 77% stabilizing lugs.

B 550 TRANSVERSE 2 DIRECTIONS 77%

_ __ _ _ _ _ _ _ __ __ _ __ __ __ _ __ __ __ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _82% C RV 101/07 REACTOR VESSEL LOWER A I SLIC 40 PARALLEL 2 DIRECTIONS 5% Limited examination due to the HEAD RING TO LOWER B 550 PARALLEL 2 DIRECTIONS 5% proximity of the lower head bottom-HEAD A SLIC 40 TRANSVERSE* 2 DIRECTIONS 5% mounted instrumentation (MI)

B 550 TRANSVERSE 2 DIRECTIONS 5% tubes.

__________ ~~~~~~~5%

CRV 101/22 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 74% Limited examination due to the core SHELL LONGITUDINAL B 550 PARALLEL 2 DIRECTIONS 74% barrel stabilizing lug @00.

WELD @ 00 A SLIC 40 TRANSVERSE 2 DIRECTIONS 71%

B 550 TRANSVERSE 2 DIRECTIONS 71%

73%o CRV 101/23 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 64% Limited examination due to the HEAD MERIDIONAL B 450 &550 PARALLEL 2 DIRECTIONS 64% proximity of the lower head BMI WELD @ 300 A SLIC40 TRANSVERSE 2 DIRECTIONS 61% tubes.

B 550 TRANSVERSE 2 DIRECTIONS 61%

__ __ __ _ __ _ __ _ _ __ __ __ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 63_3 % CRV_ _ _ _ __6 _ _ _ _ _ _ _

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 8 of 184 TABLE 3 REACTOR VESSEL SCAN PLAN (Continued)

WELD EXAM AREA EXAM BEAM EXAM BEAM DIRECTIONS CODE LIMITATIONS NUMBER IDENTIFICATION ANGLE(S) TYPE COVERAGE (CRV) 101/24 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 48% Limited examination due to the HEAD MERIDIONAL B 45° &550 PARALLEL 2 DIRECTIONS 48% proximity of the lower head BMI WELD @90° A SLIC 40 TRANSVERSE 2 DIRECTIONS 39% tubes and core barrel stabilizing lug B 550 TRANSVERSE 2 DIRECTIONS 39% @ 900.

_ _ _ _ _ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ __________ ~~~~~~~~~44%

CRV 101125 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 72% Limited examination due to the HEAD MERIDIONAL B 550 PARALLEL 2 DIRECTIONS 72% proximity of the lower head BMI WELD @ 1500 A SLIC 40 TRANSVERSE 2 DIRECTIONS 60% tubes.

B 55° TRANSVERSE 2 DIRECTIONS 60%

.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 66% C RV 101(26 REACTIOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 56% Limited examination due to the HEAD MERIDIONAL B 450 &550 PARALLEL 2 DIRECTIONS 56% proximity of the lower head BMI WELD @210° A SLIC 40 TRANSVERSE 2 DIRECTIONS 56% tubes.

B 55° TRANSVERSE 2 DIRECTIONS 56%

___________ ~~~~~~~56%

CRV 101/27 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 42% Limited examination due to the HEAD MERIDIONAL B 450 &550 PARALLEL 2 DIRECTIONS 42% proximity of the lower head BMI WELD @2700 A SLIC 40 TRANSVERSE 2 DIRECTIONS 46% tubes and core barrel stabilizing lug B 55° TRANSVERSE 2 DIRECTIONS 46% @270.

_________ ________ ___________ ~~~ ~~~~~~~~~44%

CRV 101/28 REACTOR VESSEL LOWER A 3 SLIC 40 PARALLEL 2 DIRECTIONS 65% Limited examination due to the HEAD MERIDIONAL B 55° PARALLEL 2 DIRECTIONS 65% proximity of the lower head DMI WELD @3300 A SLIC 40 TRANSVERSE 2 DIRECTIONS 73% tubes.

B 550 TRANSVERSE 2 DIRECTIONS 73%

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 12 of 184 I l I1 Limited area.

beneath tugs 0 900, 180 & 27 Weld 101/06 Figure 4

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 13 of 184 Ip Parallel area limitation Transverse area limitation Figure 5

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 14 of 184 I

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 15 of 184 AUTOMATED CATEGORY B-D EXAMINATIONS Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, reactor coolant system loop piping weld numbers 101A/29, 101A/31, and 101A/33.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Category B-D, Item Number B3.90. The applicable Code examination requirements, as interpreted by Code Case N-460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Category B-D, Item Number B3.90, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90%). The examination coverage achieved for the components listed in Table I are the maximum extent practical for these components.

Table 1 lists the coverage that was achieved and the reason for the limitation. Table 2 identifies the material associated with these welds, and Table 3 is an excerpt from the ISwT Reactor Vessel Scan Plan.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Automated ultrasonic examinations were performed on the RPV in accordance with the requirements of 10 CFR 50.55(a), the Technical Specifications, and the 1986 Edition of the ASME Section XI Code. These examinations included three B-D weld examinations that did not achieve the required 100% (>90%) coverage. The following descriptions, coupled with the tables and figures, are details of the examination limitations. The

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 16 of 184 accompanying figures depict the extent of the limitations. Table 1 provides the estimated required volume that was covered.

During the review process it was determined that welds 101A/30 and 101A/32 had coverage in excess of the required 90% and these welds are not included in this submittal.

RPV Outlet Nozzle to Shell Welds Automated scanning (transverse examination only) of the outlet nozzle to shell welds (101A/29, 101A/31, and 101A/33) was limited due to interference from the nozzle integral extension. Figure 1 provides a side section view of the outlet nozzle to shell welds showing the limited scanning areas.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 17 of 184 TABLE 1 REACTOR VESSEL COVERAGE AND LIMITATIONS Weld Item Description Coverage Limitation 101A/29 B3.90 Outlet Nozzle to Shell Weld 55% Limited due to proximity of

@ 100 nozzle integral extension.

101A/31 B3.90 Outlet Nozzle to Shell Weld 55% Limited due to proximity of

@ 130° nozzle integral extension.

101A/33 B3.90 Outlet Nozzle to Shell Weld 55% Limited due to proximity of

@ 250° nozzle integral extension.

TABLE 2 REACTOR VESSEL MATERIAL AND WELD IDENTIFICATION WELD CODE CODE DESCRIPTION MATERIAL WELD MATERIAL 2 ID CATEGORY ITENM #

101A/29 B-D B3.90 REACTOR VESSEL HOT LEG LOOP "B" NOZZLE NOZZLE MIL B-4 MOD (SAW) UPPER SHELL WELD @ 10° SA-336 & 8018 SA-302 GR B 101A/31 B-D B3.90 REACTOR VESSEL HOT LEG LOOP "A" NOZZLE NOZZLE MIL B-4 MOD (SAW) UPPER SHELL WELD @ 130° SA-336 & 8018 SA-302 GR B 101A/33 B-D B3.90 REACTOR VESSEL HOT LEG LOOP "C" NOZZLE NOZZLE MIL B-4 MOD (SAW) UPPER SHELL I _______ ______________ _________ W ELD @ 2500 SA-336 & 8018 SA-302 GR B

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 18 of 184 TABLE 3 REACTOR VESSEL SCAN PLAN WELlD EXAM AREA EXAMI BEAM EXAM BEAM I)IRECTIONS CODE LIMITATIONS NUMBER IDENTIFICATION VOLUME FIGURE ANGLE(S) TYPE COVERAGE

_ __ _ _ _ __ _ _ _ __ __ _ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~RV~(C) _ _ _ _ _ _ _ _ _ _ _

101A/29 REACTOR VESSEL HOT A &B 5 SLIC 40 &20 PARALLEL 2 DIRECTIONS 100% Limited examination due to the LEG LOOP "B" NOZZLE A &B SLIC 40 &20 PARALLEL 2 DIRECTIONS 100% proximity of the integral extension.

WELD @ 100 A SLIC 40 TRANSVERSE 2 DIRECTIONS 10%

B 550 TRANSVERSE 2 DIRECTIONS 10%

_________ ~~~~~~~~

CRV ~~~~~~~~~~~~~~55%

101A31 REACTOR VESSEL HOT A &B 5 SLIC 40 &20 PARALLEL 2 DIRECTIONS 100% Limited examination due to the LEG LOOP "A"NOZZLE A &B SLIC 40 &20 PARALLEL 2 DIRECTIONS 100% proximity of the integral extension.

WELD @ 130° A SLIC40 TRANSVERSE 2 DIRECTIONS 10%

B 550 TRANSVERSE 2 DIRECTIONS 10%

.________________ 55% CRV 101A/33 REACTOR VESSEL HOT A&B 5 SLIC 40 & 20 PARALLEL 2 DIRECTIONS 100% Limited examination due to the LEG LOOP "A" NOZZLE A &B SLIC 40 & 20 PARALLEL 2 DIRECTIONS 100% proximity of the integral extension.

WELD @ 2500 A SLIC 40 TRANSVERSE 2 DIRECTIONS 10%

B 550 TRANSVERSE 2 DIRECTIONS 10%

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 20 of 184 MANUAL CATEGORY B-A EXAMINATIONS Component(s) for Which Relief is Requested The component applicable to this relief request is the HBRSEP, Unit No. 2, reactor vessel closure head meridional weld with identification number 101/08.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Category B-A, Item Number B1.22. The applicable Code examination requirements, as interpreted by Code Case N460, "Alternative Examination Requirements for Class I and Class 2 Welds,Section XI, Division 1," for the component listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Category B-A, Item Number B 1.22, as interpreted by Code Case N460, "Alternative Examination Requirements for Class I and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90%). The examination coverage achieved for the components listed in Table 1 are the maximum extent practical for these components.

Table 1 lists the coverage that was achieved and the reason for the limitation.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Table I quantifies the extent of required volume that was covered, and Table 2 identifies the materials joined. Performance Demonstration Initiative (PDI) qualified personnel were used at the time of the examination. The PDI procedure in effect at the time of the examination was qualified for a thickness range of up to 7.63 inches. The RPV head thickness is 7.75 inches, which prompted Relief Request RR-3 1, which was approved under TAC No. MB1 140, dated March 9, 2001. The relief allowed the utilization of previous examination techniques for the examination of the meridional weld (Reg. Guide 1.150).

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 21 of 184 Ultrasonic examination techniques utilized during the Third Ten-Year Interval on the loop piping welds were consistent with industry standards during the time frame the examination occurred. The weld profiles provided show the configurations as well as the scans performed inclusive of beam path coverage. Beam path coverage does not account for beam spread, which would increase the effective coverage of each weld.

Scan directions utilized are as follows:

Scan 1 With flow Scan 2 Against flow Scan 3 Clockwise, looking in the direction of flow Scan 4 Counterclockwise, looking in the direction of flow Each scan direction was assigned a value of 100% of the required scan volume for each direction. Each scan percentage was compiled and divided by the four directions to arrive at a cumulative examination coverage percentage.

Additional information included in support of this relief request are an Inservice Inspection Determination of Percent Coverage Worksheet, Limited Exam Data Sheets for weld 101/08, and a cross-sectional view of weld 101/08.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 22 of 184 TABLE 1 MERIDIONAL WELD COVERAGE AND LIMITATIONS Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Technique Component Coverage (PDI) 101/08 Reactor Vessel B-A B 1.22 VOL 49% SCAN LIMITED DUE TO NO Closure Head COMPONENT CONFIGURATION, Meridional Weld HEAD FLANGE AND CRDM

___ ___ I__I___ _ ____

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PENETRATIONS. I TABLE 2 MERIDIONAL WELD MATERIAL AND WELD IDENTIFICATION WELD ID CODE CODE DESCRIPTION MATERIAL 1 WELD MATERIAL 2 CATEGORY ITEM #

101/08 B-A B 1.22 Reactor Vessel Closure Head Meridional Weld SA-302 GR B RAC03 (SAW) SA-302 GR B

&E8018

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 23 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 101/08 ASME CATEGORY: B-A ASME CODE FIGURE: IWB-2500-3 ASME ITEM NUMBER: B 1.22 CONFIGURATION: REACTOR VESSEL HEAD  % CRV ACHIEVED: 49%

MERIDIONAL WELD PDI TECHNIQUE NO EXAM DATE: 4/16/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 47% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

2 47% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

3 51% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

4 51% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 47% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

2 47% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

3 51% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

4 51% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

0° SCAN SCAN  % VOLUME LIMITATION ACHIEVED LONGITUDINAL 47% SCAN LIMITED DUE TO COMPONENT CONFIGURATION AND CRDM PENETRATIONS.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 24 of 184 I@ Washington Page 4 of 6 I IJmiktd [iam Data Sheet

[ST Weld Number. 101AM IS! Compont NUM14erF Rzator Vssel lad W&I /2005 RC Sketch{s) Attached? iME ST-JgomctdrkNumber. IM1R2-100811ev2 Si Overall Weld Leimth. 49 ncs Thikne,,: 8.40 nchies Weld Width: 3.0 Inches Cas,: I`WB Base Metal Width 8.4 Ics Total Cr Ot'Sectimal Arra 95.76 Inches Total Cu ble volume 4692.24 lixelie Rxate Mietal Cakuhton:

sale Ml tal Cuble Volume 31457.44 Incs Weld Metal Clculation: 0 Weld Me t1At Cubk Volume 123-4.8 Incbes SCANS 'Tgtxt Cvi Volutm Scsnzxd flnlks) TOWa Cut'ic,Vatumex ft It 3457.44 3457.44 3457.44 I' *1457.44 Ir 23 X 134 X 1.4 111.3 3457.44 4rt v~~ 34 x 3-4 4ItJI1 43'b 23 ax 4 it 3.4 a 0.5 34571.44 1 17l 3457.44 3457.44 3437,44 31116.96 Total Cubic Volum Scanned 15' -3.62 Artrm-pic Covmgc 49%

ToW CP"C V'lunF 31116.96 zl~ /72 2z Exxmix= Lesd: .. 2lr 7 Date . .- o E xminer __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ L vel: A1 4 Date: _ A_ _ _ _ _ _

Revicewct (W a gton): S O a.fate: D4..~~~ & 4.D7 clt lc%~cr (Client): CfiDi.Nk 5.L.

C-A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _D ate:- / ( I ~

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 25 of 184 r

I 1AQWashington Umited Exan Data Sheet Pas S or- 6 ISI Weld Number. Ia)

ISI Component Numb Reactor Vc= cted Weld / 200S Re S etch(t) Attached ?

[l YES f.onetric Number: 1MR2-1068Rc%.2 Shl 30 INO Overall Weld LUngth: 49 IhsC Thiknecss: 8,40 oct Weld Width: 3.0lncCS Cla: IWBI Base bletal W1Jlh 8.4 Icbes Total Cri ms Sectional Area 95.76 Inchks Totol Ci1bkcVolume 4692.24 Inches Bxse Metal Cakulation:

El DsC NIIMtatCubk Volume 34S7.44 Inches Weld JMletal CAkulatkm:

Wel he tal Cubic Volumie 1234 .8 locks SCANS Total Cul&i Volumi Scamicd (Inches) Total Cubk Vol-tnm U I l234.8 1Ž34.3 1234.8 4$o1 23 a 3 x 1.41 C 4511 92 x 30 x 1.4 D.

4rb ~ 21 s 30  % 3.4 C 5719.6 12314.t 1234,8 12,141.

1tt1t3-.2 Total Cubic Volume Scanned 5437.72 Aggrcgatc Cavare~ 49tl Total Cub olume 11113.2 112mincr.P tJo f he @!'$ - V_ -

DAIe: L4.37701 Rc~icr Wash~ington):

I~ ~ ~ -(et a Datc: Z-D jncicsvcr (lANT): Date: 1(t .I.,'

• I - - -, I GI

) CRDM upport Mech 7s

)

°  :

" S 0I- CD 41 Cn Z CD C M. _.

M DOLAL \VClD Exit Point P CD r

Weld 11/0

dx 44Q en Scan Path equals 11.08 + 23.05 0 23.05" for a total of 34.13" 23.05" _ 0 17.47" En

/~~ TYP 0.

24.99" 54"

< / CROSS SECTIC)NAL VIEW OF KERIDONAL WELD Page 6 of v~~g W 8 C~~X=72

,I C#e .. -

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 27 of 184 MANUAL CATEGORIES B-F AND B-J EXAMINATIONS Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, reactor coolant system piping associated with loop welds identified in Table 1.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Categories B-F and B-J, Item Numbers B5.70 and B9.1 1, respectively. The applicable Code examination requirements, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Categories B-F and B-J, Item Numbers B5.70 and B9.1 1, respectively, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90%). The examination coverage achieved for the components listed in Table I are the maximum extent practical for these components. Table 1 lists the coverage that was achieved and the reason for the limitation.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

During the review process performed on the subject welds, it was identified that the ISI Program description included steam generator nozzle safe end welds. After further review, it appears that the steam generators were provided with a stainless steel build-up on the hot leg and cold leg nozzles and that there is no weld in this location. Therefore, these welds are not included in this RAI response and have been deleted from the ISI Program description.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 28 of 184 Table 1 quantifies the extent of required volume that was covered, and Table 2 identifies the materials joined.

Ultrasonic examination techniques utilized during the Third Ten-Year Interval on the loop piping welds were consistent with industry standards during the time frame the examination occurred. The weld profiles provided depict the configurations as well as the scans performed inclusive of beam path coverage. Beam path coverage does not account for beam spread, which would increase the actual coverage for each weld.

Scan directions utilized are as follows:

Scan 1 With flow Scan 2 Against flow Scan 3 Clockwise, looking in the direction of flow Scan 4 Counterclockwise, looking in the direction of flow Each scan direction was assigned a value of 100% of the required scan volume for each direction. Each scan percentage was compiled and divided by the four directions to arrive at a cumulative coverage percentage.

Additional information included in support of this relief request are Inservice Inspection Determination of Percent Coverage Worksheets and associated weld coverage plots for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 29 of 184 TABLE 1 LOOP PIPING COVERAGE AND LIMITATIONS Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Technique Component Coverage 107/04DM Hot Leg Loop "A" B-F B5.70 VOL 61% Centrifugally cast stainless steel Standard ASME Code Elbow to Hot Leg elbow to carbon steel cast nozzle. manual ultrasonic Nozzle examination 107/05DM Crossover Leg Loop B-F B5.70 VOL 61.75% Carbon cast nozzle to centrifugally Standard ASME Code "A" SIG Nozzle to cast stainless steel elbow. manual ultrasonic Elbow examination 107A/04DM Hot Leg Loop "B" B-F B5.70 VOL 60.35% Centrifugally cast stainless steel WCAP-1 1778 Elbow to Hot Leg elbow to carbon steel cast nozzle.

Nozzle 107A/05DM Crossover Leg Loop B-F B5.70 VOL 60.52% Carbon cast nozzle to centrifugally WCAP-1 1778 "B" SIG Nozzle to cast stainless steel elbow.

Elbow 107B/04DM Hot Leg Loop "C" B-F B5.70 VOL 51.50% Centrifugally cast stainless steel PDI Elbow to Hot Leg elbow to carbon steel cast nozzle.

Nozzle 107B/05DM Crossover Leg Loop B-F B5.70 VOL 55.75% Carbon cast nozzle to centrifugally PDI "C" S/G Nozzle to cast stainless steel elbow Elbow 107A/07 Crossover Leg Loop B-J B9.11 VOL 84% Wrought stainless steel pipe to WCAP-1 1778 "B" Pipe to Elbow centrifugally cast stainless steel elbow.

107B/1 Cold Leg Loop "C" B-J B9.11 VOL 57% Centrifugally cast stainless steel PDI RCP to Pipe elbow to wrought stainless steel pipe.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 30 of 184 TABLE 2 MATERIAL IDENTIFICATION WVELD ID CODE CODE DESCRIPTION MATERIAL 1 MATERIAL 2 CATEGORY ITEM #

107/04DM B-F B5.70 Hot Leg Loop "A" Elbow to Hot Leg Nozzle Elbow Nozzle A376 TP 316 SA-216 GR WCC 107/05DM B-F B5.70 Crossover Leg Loop "A" S/G Nozzle to Elbow Nozzle Elbow SA-216 GR WCC A376 TP 316 107A/04DM B-F B5.70 Hot Leg Loop "B" Elbow to Hot Leg Nozzle Elbow Nozzle A376 TP 316 SA-216 GR WCC 107A/05DM B-F B5.70 Crossover Leg Loop "B" S/G Nozzle to Elbow Nozzle Elbow

_______ __________________________________ SA-216 GR WCC A376 TP 316 107B/04DM B-F B5.70 Hot Leg Loop "C" Elbow to Hot Leg Nozzle Elbow Nozzle A376 TP 316 SA-216 GR

._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _W C 107B/O5DM B-F B5.70 Crossover Leg Loop "C" SIG Nozzle to Elbow Nozzle Elbow SA-216 GR WCC A376 TP 316 107A/07 B-J B9.11 Crossover Leg Loop "B" Pipe to Elbow Pipe Elbow A376 TP 316 A376 TP 316 107B/1 I B-J B9.11 Cold Leg Loop "C" RCP to Pipe Pump Pipe

._ __ _ _ _ _ _ _ _ __I A376 TP316 A376 TP 316

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 31 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107/04DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION ELBOW TO NOZZLE  % CRV ACHIEVED: 61%

PDI TECHNIQUE NO EXAM DATE: 10/3/93 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

3 72% 1/2V SINGLE SIDED EXAM DUE CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 72% 1/2V SINGLE SIDED EXAM DUE CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

a > =w-oc,-

_ 0

' 7C C-f-Zo~~~~lt-3:5000 ~ ~ p.

2. _

007 CD

. S 0Q W()

Of 9 I . _.

I 44 iWA,--jmf£r> Am 07o XI AS-CSMW 100*7o r_07 ~re~ACemt-,

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C.4rC 4CAJJ5 COVORAL.&cxOm P-e 154GAt 0O i tO n%% I Pr-tor>1 %&-eo Abade opM

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 33 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107/05DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION NOZZLE TO ELBOW  % CRV ACHIEVED: 61.75%

PDI TECHNIQUE NO EXAM DATE: 10/4/93 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

2 99% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

3 74% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 74% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

',e9-

• 7/ O 5Cf CDC Frt-o Vl 0 0r o C-

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.k o 7 AACe 43 EA IT Cj>t rZED 99 70 Av.t a CAC6A F.3, rF.-ow z3Y C.irEC SCAJ:

4 S A

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Co1E9RzA&e PL~ 004E C> o ORIGtNKL_ OaRou A Ot are .51 So -'Aner I,

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 35 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107A/04DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION ELBOWTO NOZZLE  % CRV ACHIEVED: 60.35%

PDI TECHNIQUE NO - WESTINGHOUSE EXAM DATE: 3/18/98 USED: TECHNIQUE PER WCAP 11778 UTILIZED 450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

3 70.7% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 70.7% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

SAA5L' S , W7 O

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 37 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107A/05DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION NOZZLE TO ELBOW  % CRV ACHIEVED: 60.52%

PDI TECHNIQUE NO - WESTINGHOUSE EXAM DATE: 3/18/98 USED: TECHNIQUE PER WCAP 11778 UTILIZED 450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

2 100% NONE 3 71% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 71% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 39 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107B/04DM ASME CATEGORY: B-F ASME CODE FIGURE: IVB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION ELBOW TO NOZZLE  % CRV ACHIEVED: 51.50%

PDI TECHNIQUE YES EXAM DATE: 5/25/01 USED:

410 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 84% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

2 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

3 61% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 61% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

-0 > C were, u to7 d/4 DY O CD En

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1. a._J 00DCD pQKr Gel-' E%-Xr Eot'J cn "CD p CD 0

CD 6o 0 3 ArzSA *aOrCDoe~eC> CY A,eA N-or -oltzd; Po8SC^ cool FDVJ 41' majoorez Aoc-J-

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 41 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 107B/05DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.70 CONFIGURATION NOZZLE TO ELBOW  % CRV ACHIEVED: 55.75%

PDI TECHNIQUE YES EXAM DATE: 4/20/01 USED:

410 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

2 93% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

3 65% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

4 65% 1/2V SINGLE SIDED EXAM DUE TO CAST STAINLESS STEEL ELBOW TO CARBON CAST NOZZLE CONFIGURATION.

• See attached CRV plot for examination coverage.

I >-

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C & Ai. - Pd- ILS 6 4BJePC)Qa OLR-D

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 43 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSIIEET (UT)

COMPONENT ID: 107A/07 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9. 11 CONFIGURATION: PIPE TO ELBOW  % CRV ACHIEVED: 84%

PDI TECHNIQUE NO - WESTINGHOUSE EXAM DATE: 3/19/98 USED: TECHNIQUE PER WCAP-1 1778 UTILIZED 410 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 36% 1/2V SINGLE SIDED EXAM DUE TO PIPE TO CAST STAINLESS STEEL ELBOW CONFIGURATION.

3 100% NONE 4 100% NONE

• See attached CRV plot for examination coverage.

at > C

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 45 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WN'ORKSHEET (UT)

COMPONENT ID: 107B/1 ASME CATEGORY: B-J ASME CODE FIGURE: InvB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: RC PUMP TO PIPE  % CRV ACHIEVED: 57%

PDI TECHNIQUE YES EXAM DATE: 4/20/01 USED:

410 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO REACTOR COOLANT PUMP NOZZLE TO PIPE CONFIGURATION.

2 100% NONE 3 64% 112V EXAM DUE TO REACTOR COOLANT PUMP NOZZLE TO PIPE CONFIGURATION.

4 64% 1/2V EXAM DUE TO REACTOR COOLANT PUMP NOZZLE TO PIPE CONFIGURATION.

• See attached CRV plot for examination coverage.

70awso UtT i; WSWg-t> -x 0e/lt 0 C CD RLoW V vCD r-r CD

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-D CD 41 4 me-, zw R k t 074 AeAt- ci s.3.

%oo70 A-At~4.. (w ACof. A6As#r4 ts" CA *7, c.,fzc. do~f.-&-

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enov Ce&.J) a> z<.m

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 47 of 184 CATEGORIES B-F, B-J, AND C-B NOZZLE EXAMINATIONS Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, limited examination of component nozzle configurations identified in Table 1.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Categories B-F, B-J, and C-B, Item Numbers B5.40, B9.31, and C2.21, respectively. The applicable Code examination requirements, as interpreted by Code Case N-460, "Alternative Examination Requirements for Class I and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100%

of the subject weld or component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Categories B-F, B-J, and C-B, Item Numbers B5.40, B9.31, and C2.21, respectively, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90%).

The examination coverage achieved for the components listed in Table 1 are the maximum extent practical for these components. Table I lists the coverage that was achieved and the reason for the limitation.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Ultrasonic examination techniques utilized during the Third Ten-Year Interval on the nozzle configurations were consistent with industry standards during the time frame the examination occurred. The weld profiles provided show the configurations as well as the scans performed inclusive of beam path coverage. Beam path coverage does not account for beam spread, which would increase the identified coverage for each weld.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 48 of 184 Typically, a branch connection only allows for axial scanning from one side, and circumferential scans do not allow complete coverage of the Code-required volume due to the nozzle connection design configuration. Table 1 quantifies the extent of required volume that was covered, and Table 2 identifies the materials joined.

Scan directions utilized are as follows:

Scan 1 With flow Scan 2 Against flow Scan 3 Clockwise, looking in the direction of flow Scan 4 Counterclockwise, looking in the direction of flow Each scan direction was assigned a value of 100% of the required scan volume for each direction. Each scan percentage was compiled and divided by the four directions to arrive at a cumulative coverage percentage.

Additional information included in support of this relief request are Inservice Inspection Determination of Percent Coverage Worksheets, associated weld coverage plots for examination coverage, and, where available, weld scan limitation details.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 49 of 184 TABLE 1 NOZZLE COVERAGE AND LIMITATIONS Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Technique Component Coverage 117/01DM Pressurizer Relief B-F B5.40 VOL 74.80% Nozzle configuration. PDI Nozzle to Safe-End 118/01DM Pressurizer Safety B-F B5.40 VOL 88.25% Nozzle configuration. PDI Nozzle to Safe-End 108/OIBC Loop Pipe to 12" B-J B9.31 VOL 62% Nozzle configuration. PDI Branch Connection 112/OlBC Loop Pipe to 10" B-J B9.31 VOL 60% Nozzle configuration. PDI Branch Connection 202/03 Boron Injection C-B C2.21 VOL 74.25% Vessel weld/nozzle configuration. Standard ASME Code Tank Lower Head to manual ultrasonic Nozzle Weld examination.

202/04 Boron Injection C-B C2.21 VOL 84% Vessel weld/nozzle configuration. Standard ASME Code Tank Upper Head to manual ultrasonic Nozzle Weld examination.

205/08 Steam Generator C-B C2.21 VOL 53% Nozzle configuration. Standard ASME Code "A" Upper Shell to manual ultrasonic Feedwater Nozzle examination.

205A/07 Steam Generator C-B C2.21 VOL 44% Nozzle configuration. Standard ASME Code "B" Upper Head to manual ultrasonic Steam Nozzle examination.

205A/08 Steam Generator C-B C2.21 VOL 56% Nozzle configuration. Standard ASME Code "B" Upper Shell to manual ultrasonic Feedwater Nozzle examination.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 50 of 184 TABLE 2 NOZZLE MATERIAL IDENTIFICATION WELD ID CODE CODE 1)ESCRIPTION MATERIAL I MATERIAL 2 CATEGORY ITEM #

117/01DM B-F B5.40 Pressurizer Relief Nozzle to Safe-End Nozzle SA-216 Safe-End GR WCC SA-182 TP-316 118/01DM B-F B5.40 Pressurizer Safety Nozzle to Safe-End Nozzle SA-216 Safe-End GR WCC SA-182TP-316 108/O1BC B-J B9.31 Loop Pipe to 12" Branch Connection Loop Pipe Branch A376 TP316 A-182 F-316 112/OBC B-J B9.31 Loop Pipe to 10" Branch Connection Loop Pipe Branch A376 TP316 A-182 F-316 202/03 C-B C2.21 Boron Injection Tank Lower Head to Nozzle Weld Head Nozzle SA-182

_______________________________________ SA-240 TP-304 F-304 202/04 C-B C2.21 Boron Injection Tank Upper Head to Nozzle Weld Head Nozzle SA-182 SA-240 TP-304 F-304 205/08 C-B C2.21 Steam Generator "A" Upper Shell to Feedwater Nozzle Shell Nozzle SA-533 GR-A SA-508 CLASS

_______ ~~~~~~~~~~~~~~~~~~~~CL.

2 2a 205A/07 C-B C2.21 Steam Generator "B" Upper Head to Steam Nozzle Shell Nozzle SA-533 GR-A SA-508 CLASS CL.2 2a 205A/08 C-B C2.21 Steam Generator "B" Upper Shell to Feedwater Nozzle Shell Nozzle SA-533 GR-A SA-508 CLASS

._ _ __________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ C L. 2 2a

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 51 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 117/01DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.40 CONFIGURATION: NOZZLE TO SAFE END  % CRV ACHIEVED: 74.80%

PDI TECHNIQUE YES EXAM DATE: 3114/98 USED:

450 SHEAR & RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED _

1 95% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

2 26% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

3 89% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

4 89% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

600 SHEAR & RL SCAN SCAN %VOLUME LIMITATION ACHIEVED 1 95% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

2 26% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION AND ADJACENT WELD.

• See attached CRV plot for examination coverage.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 53 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 118/01DM ASME CATEGORY: B-F ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B5.40 CONFIGURATION: NOZZLE TO SAFE END  % CRV ACHIEVED: 88.25%

PDI TECHNIQUE YES EXAM DATE: 3/14/98 USED:

450 SHEAR & RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 53% 1/2V SINGLE SIDED EXAM DUE TO INTEGRAL CAST NOZZLE TO SAFE END CONFIGURATION, AS-WELDED CONDITION AND DOWNSTREAM WELD.

3 100% NONE 4 100% NONE

• See attached CRV plot for examination coverage.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 55 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 108/OlBC ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-10 ASME ITEM NUMBER: B9.31 CONFIGURATION: BRANCH CONNECTION TO LOOP  % CRV ACHIEVED: 62%

PIPE PDI TECHNIQUE YES EXAM DATE: 4/30/01 USED:

380 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 3 55% NOZZLE CONFIGURATION LIMITS THE CIRCUMFERENTIAL SCAN.

4 55% NOZZLE CONFIGURATION LIMITS THE CIRCUMFERENTIAL SCAN.

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 38% 112V SINGLE SIDED EXAM AND BRANCH CONNECTION TO PIPE CONFIGURATION.

2 96% 1/2V SINGLE SIDED EXAM AND BRANCH CONNECTION TO PIPE CONFIGURATION.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO BRANCH CONNECTION TO PIPE CONFIGURATION.

2 100% NONE 600 RL SCAN SCAN t VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO BRANCH CONNECTION TO PIPE CONFIGURATION.

2 100% NONE See attached CRV plots for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 56 of 184 Washington Pg ~~~~~~~~~~~~~~W.R.o 4D ~ # _______

Client: lI.R.ROBItNSON Project: RO-20 Report No.: 01OS System- RC 2005 Procedure: JIBR.UT4S6-1 Rev.: I Date: 430 Line No.: 12-RC-10 Drawing No.: 111R2-10618 SIIT.13 Rev.- I Zomponent l.D.: 108ICtInc Search Unit's. 'CtRCt/45' SHEAR &h SHEAR &RL SCAN LIMIlAMlON SKE[UIl TOP VIEW

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(-I D1aaSheet -~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA03-0160 Page 60 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSIIEET (UT)

COMPONENT ID: 112/OBC ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-10 ASME ITEM NUMBER: B9.31 CONFIGURATION: BRANCH CONNECTION TO LOOP  % CRV ACHIEVED: 60%

PIPE PDI TECHNIQUE YES EXAM DATE: 5/3/01 USED:

380 SIIEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 3 70% NOZZLE CONFIGURATION LIMITS THE CIRCUMFERENTIAL SCAN.

4 70% NOZZLE CONFIGURATION LIMITS THE CIRCUMFERENTIAL SCAN.

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED i 100% NONE 2 0% NO SCAN DUE TO BRANCH CONNECTION TO PIPE CONFIGURATION.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO BRANCH CONNECTION TO PIPE CONFIGURATION.

60° RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO BRANCH CONNECTION TO PIPE CONFIGURATION.

• See attached CRV plot for examination coverage.

I

);~~~~~~~E

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00 0.

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due to grain structure and metallurgIcal conditions. this additional coverage cannot be claimed.

Eaie:Level: 11 D/e 430/01 Examiner C i Level; N/A Date: NtA Reeve(W ashingtL nL Level:2DAte:_C3-d/ Reviewer (Clientl Level: Date- .LL Reviewet (ANtI) Date: 11 c1 1I O Rcer to atached Ultrasonic Indicaon Data Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 62 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 202/03 ASME CATEGORY: C-B ASME CODE FIGURE: IC-2500-4(a) ASME ITEM NUMBER: C2.21 CONFIGURATION: BOTTOM HEAD TO NOZZLE  % CRV ACHIEVED: 74.25%

PDI TECHNIQUE NO EXAM DATE: 4/26/01 USED:

450 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 69% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 28% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

3 100% NONE 4 100% NONE 600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 64% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 20% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

3 100% NONE 4 100% NONE 600 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 62% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 20% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

• See attached CRV plots for examination coverage, and supplemental photograph showing component configuration.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 63 of 184

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 67 of 184

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160  :

Page 68 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 202/04 ASME CATEGORY: C-B ASME CODE FIGURE: IWC-2500-4(a) ASME ITEM NUMBER: C2.21 CONFIGURATION: UPPER HEAD TO NOZZLE  % CRV ACHIEVED: 84%

PDI TECHNIQUE NO EXAM DATE: 4/24/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 82% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 68% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

3 93% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

4 93% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 82% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 68% LIMITED SCAN DUE TO HEAD TO NO77T CONFIGURATION.

3 93% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

4 93% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

600 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 82% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

2 68% LIMITED SCAN DUE TO HEAD TO NOZZLE CONFIGURATION.

• See attached CRV plots for examination coverage, and supplemental photograph showing component configuration.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 69 of 184 w

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 74 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 205/08 ASME CATEGORY: C-B ASME CODE FIGURE: IWC-25004(a) ASME ITEM NUMBER: C2.21 CONFIGURATION: UPPER SHELL TO FEEDWATER  % CRV ACHIEVED: 53%

NOZZLE PDI TECHNIQUE NO EXAM DATE: 9/29/93 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 80% COMPONENT NOZZLE TO SHELL CONFIGURATION AND INSULATION RING.

2 0% NO SCAN DUE TO COMPONENT NOZZLE TO SHELL CONFIGURATION.

3 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

4 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

60° SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 80% COMPONENT NOZZLE TO SHELL CONFIGURATION AND INSULATION RING.

2 0% NO SCAN DUE TO COMPONENT NOZZLE TO SHELL CONFIGURATION.

3 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

4 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

0° LAMB SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

• See attached CRV plots for examination coverage.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 78 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 205A107 ASME CATEGORY: C-B ASME CODE FIGURE: IWC-2500-4(a) ASME ITEM NUMBER: C2.21 CONFIGURATION: STEAM GENERATOR UPPER  % CRV ACHIEVED: 44%

l HEAD TO STEAM NOZZLE PDI TECHNIQUE NO EXAM DATE: 3/18/98 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 70% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND WELD CROWN.

2 6% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND WELD CROWN.

3 35% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND WELD CROWN.

4 35% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND WELD CROWN.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 0% NO SCAN - BEAM IS OUTSIDE THE CODE-REQUIRED VOLUME.

3 35% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND WELD CROWN.

4 35% LIMITED EXAM DUE TO NOZZLE CONFIGURATION AND

__ELD CROWN.

• See attached CRV plots for examination coverage

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 83 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 205A108 ASME CATEGORY: C-B ASME CODE FIGURE: IWC-2500-4(a) ASME ITEM NUMBER: C2.21 CONFIGURATION: UPPER SHELL TO FEEDWATER  % CRV ACHIEVED: 56%

NOZZLE PDI TECHNIQUE NO EXAM DATE: 3/18/98 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 92% COMPONENT NOZZLE TO SHELL CONFIGURATION AND INSULATION RING.

2 0% NO SCAN DUE TO COMPONENT NOZZLE TO SHELL CONFIGURATION.

3 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

4 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

600 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 90% COMPONENT NOZZLE TO SHELL CONFIGURATION AND INSULATION RING.

2 0% NO SCAN DUE TO COMPONENT NOZZLE TO SHELL CONFIGURATION.

3 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

4 66% COMPONENT NOZZLE TO SHELL CONFIGURATION.

00 LAMB SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 91% COMPONENT NOZZLE TO SHELL CONFIGURATION.

• See attached CRV plots for examination coverage.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 89 of 184 CATEGORIES B-J, C-F-1, AND C-F-2 PIPING EXAMINATIONS Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2 piping associated with the welds identified in Table 1.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Categories B-J, C-F-I, and C-F-2, Item Numbers B9.11, B9.40, C5.11, C5.21, and C5.51, respectively. The applicable Code examination requirements, as interpreted by Code Case N-460, "Alternative Examination Requirements for Class I and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Categories B-J, C-F-I, and C-F-2, Item Numbers B9.11, B9.40, C5.11, C5.21, and C5.51, respectively, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1,"

which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e.,

coverage is greater than 90%). The examination coverage achieved for the components listed in Table 1 are the maximum extent practical for these components. Table I lists the coverage that was achieved and the reason for the limitation.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Ultrasonic examination techniques utilized during the Third Ten-Year Interval on the piping configurations were consistent with industry standards during the time frame the examination occurred. The weld profiles provided show the configurations as well as the scans performed inclusive of beam path coverage. Beam path coverage does not account for beam spread, which would increase the coverage for each weld.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 90 of 184 Typically, a one-sided exam a on a valve to pipe or flange with an as-welded crown will result in a limitation of 50% when the examination is performed on stainless steel utilizing the applicable PDI technique. If the crown is ground flush, a maximum credit for coverage would typically be 75%. Table 1 quantifies the extent of coverage, and Table 2 identifies the materials joined.

Scan directions utilized are as follows:

Scan 1 With flow Scan 2 Against flow Scan 3 Clockwise, looking in the direction of flow Scan 4 Counterclockwise, looking in the direction of flow Each scan direction was assigned a value of 100% of the required scan volume for each direction. Each scan percentage was compiled and divided by the four directions to arrive at a cumulative coverage percentage.

Additional information included in support of this relief request are Inservice Inspection Determination of Percent Coverage Worksheets, associated weld coverage plots for examination coverage, or weld scan limitation details, as applicable.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 91 of 184 TABLE 1 PIPING COVERAGE AND LIMITATIONS Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Technique Component Coverage 112/19 Safety Injection 13-J 139.11 VOL 66% Elbow to Tee configuration. PDI Accumulator Discharge Elbow to Tee 113/01 RHR Return Line B-J B9.11 VOL 43.75% Reducer to valve configuration. PDI 10" X 8" Reducer to Valve SI-876A 114/03 RHR Return Line B-J B9.11 VOL 56.70% Pipe to valve configuration. PDI Pipe to Valve SI-876B 115/04 RHR Return Line B-J B9.11 VOL 56.70% Pipe to valve configuration. PDI Pipe to Valve SI-876C 116B/18 Pressurizer Spray B-J B9.11 VOL 75% Elbow to Pipe configuration. PDI Line Elbow to Pipe 116B/19 Pressurizer Spray B-J 139.11 VOL 51% Pipe to safe-end configuration. Standard ASME Code Line Pipe to Safe- manual ultrasonic End examination.

18SA/01 Pressurizer Safety B-J B9.11 VOL 62.5% Safe-end to pipe configuration. PDI Line Safe-End to Pipe 11813/08 Pressurizer Spray B-J B9.11 VOL 75% Elbow to flange configuration. PDI Line Elbow to Flange 133/10 Seal Injection Pipe B-J B9.40 SUR 90% Limited at 00 due to proximity of the N/A to Elbow . elbow to the ceiling. .-

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 92 of 184 TABLE 1 PIPING COVERAGE AND LIMITATIONS (Continued)

Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Technique Component Coverage 219A/203 Safety Injection C-F-i CS.1 I VOL 75% Weld crown configuration. PDI System Reducer to Pipe 220/38 RHR System Pipe to C-F-I C5.11 VOL 82.50% Weld crown configuration. PDI Elbow 220A/69 RHR System Pipe to C-F- I C5.11 VOL 71.50% Weld crown configuration. Standard ASME Code Elbow manual ultrasonic examination.

239/01 Safety Injection C-F-I C5.21 VOL 89.50% Weld crown configuration. PDI System Tee to Pipe 212/21 Main Steam System C-F-2 C5.51 VOL 75% Pipe to valve configuration. PDI Pipe to Valve MS-V1-3A 213/17 Main Steam System C-F-2 C5.51 VOL 85% Pipe to valve configuration. Standard ASME Code Pipe to Valve manual ultrasonic MS-V1-3B1 examination.

213/22 Main Steam System C-F-2 C5.51 VOL 87.50% Pipe to valve configuration. Standard ASME Code Branch Connection manual ultrasonic to Valve SV1-11B examination.

214/19 Main Steam System C-F-2 C5.51 VOL 75% Pipe to valve configuration. PDI Pipe to Valve MS-V 1-3C 216/15 Main Feedwater C-F-2 C5.51 VOL 71% Pipe to valve configuration. Standard ASME Code System Pipe to manual ultrasonic Valve FW-8B examination.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 93 of 184 TABLE 2 PIPING WELD MATERIAL AND WELD IDENTIFICATION WELD ID CODE CODE DESCRIPTION MATERIAL 1 MATERIAL 2 CATEGORY ITEM #

112/19 B-J 139.11 Safety Injection Accumulator Discharge Elbow to Tee Elbow Tee A-403 WP-316 A-403 WP-316 113/01 B-J B9.11 RHR Return Line 10" X 8" Reducer to Valve SI-876A Reducer Valve A-403 WP-304 A351 GR CF8 114/03 B-J 139.11 RHR Return Line Pipe to Valve SI-876B Pipe Valve A-376 TP-316 A-351 GR CF8 115/04 B-J 139.11 RHR Return Line Pipe to Valve SI-876C Pipe Valve

.________ .A-376 TP-316 A-351 GR CF8 116B1/18 B-J B9.11 Pressurizer Spray Line Elbow to Pipe Elbow Pipe A-403 WP-316 A-376 TP-316 116B/19 B-J B9.11 Pressurizer Spray Line Pipe to Safe-End Pipe Safe-End A-376 TP-316 SA 182 TP316 118A/01 B-J B9.11 Pressurizer Safety Line Safe-End to Pipe Pipe Safe-End A-376 TP-316 SA182TP316 11813/08 B-J B9.11 Pressurizer Spray Line Elbow to Flange Elbow Flange A-403 WP-316 A- 182 F-316 133/10 B-J B9.40 Seal Injection Pipe to Elbow Pipe Elbow A-376 TP-316 A-403 WP-316 219A/203 C-F-I C5.11 Safety Injection System Reducer to Pipe Reducer Pipe A-403 WP-304 A-376 TP-316 220/38 C-F-1 C5. 11 RHR System Pipe to Elbow Pipe Elbow A-358 CLI TP-304 A-403 WP-304 220A/69 C-F-i C5.11 RHR System Pipe to Elbow Pipe Elbow A-358 CL I TP-304 A-403 WP-304 239/01 C-F-i C5.21 Safety Injection System Tee to Pipe Pipe Tee A-312 TP-316 A-403 WP-304 212/21 C-F-2 C5.51 Main Steam System Pipe to Valve MS-V 1-3A Pipe Valve A 106 GRB A216 WCB 213/17 C-F-2 C5.51 Main Steam System Pipe to Valve MS-V 1-3B Pipe Valve

_______A 106OGR B A216WCB

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 94 of 184 TABLE 2 PIPING WELD MATERIAL AND WELD IDENTIFICATION (Continued)

WELD ID CODE CODE DESCRIPTION MATERIAL MATERIAL 2 CATEGORY ITEM #

213/22 C-F-2 C5.51 Main Steam System Branch Connection to Valve SVI- Branch Valve 1B A 106 GR SA216 WCB 214/19 C-F-2 C5.5 1 Main Steam System Pipe to Valve MS-V 1-3C Pipe Valve II _I A 106 GR B A216 WCB 216/15 C-F-2 C5.51 Main Feedwater System Pipe to Valve FW-8B Pipe Valve I______

_______ _____ ___________________________ A 106 GR B A216 WCB

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 95 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 112/19 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: TEE TO ELBOW  % CRV ACHIEVED: 66%

PDI TECHNIQUE YES EXAM DATE: 4/22/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO ELBOW TO TEE CONFIGURATION.

2 50% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

3 82% SINGLE SIDED 12V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

4 82% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

600 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO ELBOW TO TEE CONFIGURATION.

70% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

700 RL SCAN SCAN  % VOLUME LIMITATION

._____ ACHIEVED I 0% NO SCAN DUE TO ELBOW TO TEE CONFIGURATION.

2 100% NONE

• See attached CRV plot for examination coverage.

phge _5. of S I Washington o O=

-B -

Cient IIB ROBINSON 2 RO.20 - System: ACCUM.DISCHARGE RportNo.: t)/- 0/2 Line Nwo. 10-SI-54 Co- rponent ID.: 112/19 Preeedure: HBR-UT4&I Rev.: I Date: 4/22101 Rev.: 3 ' Smh Unit Angle: 4s, 6, A 70 Mode: 4PSAS70RL .

Dhwing No.: 11BR2.1061! ShL 17  :.

0 0 5OX CObL &OAMcb C.DvepU4 oarAlIesb rA SaNAImrG- 0 r-0 0

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TEE ELBOW

-,r Level: Dxle  : h ere -nin  : I ILmvl; OVI Dte: /

Ex=iint Revie4 i -' ==Lvel: 7 Dat: /ff42/ Rviewer. (ClIen) l Level M Date:5SlSO0 Revewe r ANII) nDve:

El Refer to attxhed Ultrsonie lnication DIM Sheet . .. _

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 97 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 113/01 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: REDUCER TO VALVE  % CRV ACHIEVED: 43.75%

PDI TECHNIQUE YES EXAM DATE: 4/28/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 33% COMPONENT CONFIGURATION AND AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE REDUCER/VALVE.

2 0% NO SCAN DUE TO REDUCER TO VALVE CONFIGURATION.

3 71% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE REDUCER/VALVE.

4 71% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE REDUCERIVALVE.

700 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 2% SINGLE SIDED 1/2V EXAM DUE TO REDUCER TO VALVE CONFIGURATION.

2 0% NO SCAN DUE TO REDUCER TO VALVE CONFIGURATION.

• See attached CRV plot for examination coverage.

NOTE: An RL transducer could not be used due to the limited scanning surface. The appropriately focused RL transducer is too large to scan the area and a smaller RL transducer did not have the focal depth necessary to provide an adequate exam. Also, due to the weld crown being in an as-welded condition, scanning could not be performed over the weld crown.

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paxge L r C W.R.i ilA oO O 0 RO-20 System: St 2030 Repot No.: 01-013 Clknt: LB. Robinson Projeet: _ CD I

13/01 Proedure: llBR-UT86B1 Rev.: I Dte: 4/260 Line No_ &SI-37 Component ID.:

Rev.: 2* Seazdh Unit Angle: 4 &70 Mode: 45-S &701S Drawing No.: NIBR2-1061SSbt. I -

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4~,v FLOW wowoLevel: nl Date: El-innenr -_ _ _ _ _ Level: Date: AIA Exarrninerr D4.:gt ,fi,-<<5/t Reviewen. Washingtonlat.- P Level. Reviewe (Clien-t) De:DLevel'Z-. (

Revkwet: (ANtI) F Date 0 Refer to attched Ulsasornt Indication Data Shet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 99 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 114/03 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9. 11 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 56.70%

PDI TECHNIQUE YES EXAM DATE: 3/23/98 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE CREATING LIFT-OFF OF THE TRANSDUCER.

2 5.4% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE AND PIPE TO VALVE CONFIGURATION.

3 58% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE.

4 58% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE.

45° RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 5.4% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE AND PIPE TO VALVE CONFIGURATION.

60° SIIEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 0% NO SCAN DUE TO PIPE TO VALVE CONFIGURATION.

ULTRASONIC BEAM PATH IS OUTSIDE OF THE CRV BLOCK.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 100 of 184 OAT.,, .Y JoT 3-rA, ro q c'17

/JFZ V3SESt 3 da.r-t F/&I Raw . \

,-43 Val

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 101 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WNIORKSHEET (UT)

COMPONENT ID: 115/04 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 56.70%

PDI TECHNIQUE YES EXAM DATE: 3/19/98 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 5% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO VALVE CONFIGURATION. LIMITED ACCESS FROM THE VALVE SIDE OF THE WELD DUE TO COMPONENT CONFIGURATION.

2 100% NONE 3 60.9% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE.

4 60.9% AS-WELDED CONDITION LIMITS CONTACT ON THE SURFACE OF THE WELD TOE INTERFACE AT THE PIPE/VALVE.

600 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO VALVE CONFIGURATION. NO SCAN ACCESS IS PERMITTED FROM THE VALVE SIDE OF THE WELD DUE TO COMPONENT CONFIGURATION.

2 100% NONE 60° SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO VALVE CONFIGURATION. NO SCAN ACCESS IS PERMITTED FROM THE VALVE SIDE OF THE WELD DUE TO COMPONENT CONFIGURATION.

2 100% NONE

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 102 of 184 53a-rk s- vD- ,

d°oJcVra pro-khELb~A/

)

- Fht PoweA~j'XkIa 4X/1401-L-,9-.- 9 3-114' W..'

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 103 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 116B/18 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: ELBOW TO PIPE  % CRV ACHIEVED: 75%

PDI TECHNIQUE YES EXAM DATE: 4/29/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO ADJACENT WELD I 16B1/19.

3 100% NONE 4 100% NONE 450 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 0% NO SCAN DUE TO ADJACENT WELD 116B/19.

700 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 0% NO SCAN DUE TO ADJACENT WELD 116B/19.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 104 of 184 Page 5 of 5

) Washington W.R. sf W.R. # N/A Client CP &L -Project: IL B. Robinson Report No.: 01.017 System: RC 2005 Procedure: IBR-UT.86-1 Rev.: I Date: 4/29/01 Lne No.: 4RC30 Drawing No.: IIBR2-10618 sht. 23 Rev: I ComponentlD.: 116B/IS SearchUnitAngle: 45-and704 Mode: Sh&R/L Flow Elbow Nozzle Achieved 50% 191.1% 44Oqverc, ttvune dA ICoI Total Volume 2.708"3 Clockwise = 100%

Counterclockwise = 100%

AgainstFo w=. S A-ct With Fo= 100%

otai = 364A% 14 = 9 I.I%Actual Coverage Achieved Note: 50% Code Required coverage was obtained from scanning single sided.

The screen range was established to enconpass an additional 13T but, due to grain structure and metadlurgIeal conditions his additional coverage cannot be claimed.

Einer.JayMiller 4 - 1 -- Level: il Date: 4/29/01 Examiner. <>g\,P/ _ Level-  : Date: 1 Reviewer (Washingto- Level: 7 Date: .$ 7/

Reviewer. (Clent) Level: Date: e. 0 1 Rviefert c (ITdct.i r t Date:- (1.J° i1 Refer to attached Ultrasonic Indication Data Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 105 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 116B/19 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: PIPE TO SAFE END  % CRV ACHIEVED: 51%

PDI TECHNIQUE NO EXAM DATE: 10/7/93 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 3 68% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT WELD 116B/18.

4 68% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT WELD 116B/18.

70° SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO ADJACENT WELD 16B/18.

2 68% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT WELD 116B/18.

• See attached CRV plot for examination coverage.

> c i i JDA VEtD a

• 0 ~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0

/

.b>KA'rb AIft0

.LM rz0,3J SC..wS 21~~~~~~~~~~~~~~~~~~~~~~~~~~~~1 2.=Lrmno Awr  ; A-7

/.

sM~mvuxe °z_____. r~roS0--93i tf'l noz~~~~~~~~~~~~~~~~~~~~ik 116B - /

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 107 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 118A/01 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: PIPE TO SAFE END  % CRV ACHIEVED: 62.50%

PDI TECHNIQUE YES EXAM DATE: 4/29/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO ADJACENT SAFE-END CONFIGURATION.

2 80% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT SAFE-END CONFIGURATION.

3 78% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT SAFE-END CONFIGURATION.

4 78% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT SAFE-END CONFIGURATION.

450 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO ADJACENT SAFE-END CONFIGURATION.

2 100% NONE 700 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% SINGLE SIDED 1/2V EXAM DUE TO ADJACENT l SAFE-END CONFIGURATION 2 100% NONE

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 108 of 184

@WWashington Page of S Client CP&L Project: II.B.Robinson ReportNo.: 01-018

• System: RC 2005 Procedure: IIBR-Utr-8-1 Rev I Dae V4/2801 Une No.: 4-RC43 Drawing No.: HBR2-10618 shL 28 Rev: 3

Com nent ID.: 118A/OI Search Unit Angle: 45& 70 Mode: Sh&RtL Flow Nozzle Elbow

., WitFOo5 Agist1 1o I Achieved150% 199.63 of the Code Required Coverage I oue=2.70' ke=1100%

otlCvrge =393 4 = 9.3%

Note: 50% Code Required Coverage was obtained from scanning single sided.

Ie screen range was established to encompass an addition IMf but, due to grain structure and tmetallurgical conditions, this additional coverage cannot be claimed.

xainner:

Jay Miller Levl: III Date: 4/28/0

- Examiner 9-A 4 Level: 1 Daw, ~

Reviewer. (Client)

• . Rkeviewer (AN1I) Date:_ I o Refer to attached Ultrasonic fitilication Data Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 109 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 118B/08 ASME CATEGORY: l_B-J_ l ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.11 CONFIGURATION: ELBOW TO FLANGE  % CRV ACHIEVED: 75%

PDI TECHNIQUE YES EXAM DATE: 4/22/01 USED:

450 SHEAR & RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 0% NO SCAN DUE TO ELBOW TO FLANGE CONFIGURATION.

3 100% NONE 4 100% NONE 700 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 0% 1 NO SCAN DUE TO ELBOW TO FLANGE CONFIGURATION.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 10 of 184 Washington page fA I W.R. #N/A Client CP &L Project _ . B. Robinson F_ Rcport No.: 01-019 System: RC2005 Procedurc: IIBR-UT-86-1 _Rev 1 Date: 428101 Line No.: 4-RC-45 Drawing No.: IfllR210618 sht. 28 Rev.: 3 Component ID.: 118B108 Search Unit Angle: 45e & 70 Mode: Sh&RI, Flow Valve Elbow

. ts~~~~~

Achieved 50% 1/% of the Code Required Coverage Volure 3.23' oc se=100%

Countc =100%

With ow AgalnstFlow=

Flo Totalu3971%/4= 5%

Note: 50% Code Required Coverage was obtained from scanning single sided.

The screen range was established to encompass an additional 113T but, due to grain structure and metallurgical conditIon, this additonal coverage cannot be clalmed.

Exariner Jav MiLler 4 _ _ ,Q- I Level: 1ll Date: 428/01 Examiner. A4 Io. >

XO .,,e -Level: Oi: Date: 0I P, Reviewcr (Wasington Level: . Date: S s /

Reviewer (Client) Level: M Date: sCS l Reviewer (ANII) Date: ______

E] Refer to attached Ultrasonic Indication Data Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 111 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (PT)

COMPONENT ID: 133/10 ASME CATEGORY: B-J ASME CODE FIGURE: IWB-2500-8 ASME ITEM NUMBER: B9.40 CONFIGURATION: PIPE TO ELBOW  % CRS ACHIEVED: 90%

PDI TECHNIQUE N/A EXAM DATE: 10/11/93 USED: I I

• Exam was limited at top dead center due to the close proximity of the ceiling; see sketch for surface examination limitation. Code-required surface is estimated at 90% CRS.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 112 of 184

,-/7- O-7 PACE a OF rCPL- 133 WELP to

- .e 09%

LIMZTED XA1 TP OF SOCKET EL-80 D TO CErIZJ-G E.YAMrIJE\ E LEVEL -E A J0-1p-j-95

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 113 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 219A/203 ASME CATEGORY: C-F-1 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.11 CONFIGURATION: REDUCER TO PIPE  % CRV ACHIEVED: 75%

PDI TECHNIQUE YES EXAM DATE: 4/26/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO REDUCER TO PIPE CONFIGURATION.

2 50% 1/2V SINGLE SIDED EXAM DUE TO REDUCER TO PIPE CONFIGURATION.

3 100% NONE 4 100% NONE 600 SIIEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO REDUCER TO PIPE CONFIGURATION.

2 75% 1/2V SINGLE SIDED EXAM DUE TO REDUCER TO PIPE CONFIGURATION.

700 RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% NO SCAN DUE TO REDUCER TO PIPE CONFIGURATION.

2 100% NONE

• See attached CRV plot for examination coverage.

-p_. C Page G or .

Washington W.R. N AI RO.Z0 SYstni S 208 Rert No..;. /- S/ 0 0 Cient: -H.B. ROBINSON . Projct:_ .

O 21!9203 Pmeedurr: HBR-UT46.1 Rev.: I Dale:_ 4/26t0_

Une No,: 8.51.37 _ Componemt I.D. _ 0C Rev,: 2 Searh Unit Angle: N/A Mod: NIA  :. _

Drznug No.: H 0 H7 P CD

........... 1.

qOQ t CD w

?rsqt 4fc feA svOED 6~.MA-l AS~ C--bL4 4"'O4d o o 56~b ' ,Lt eLDC e r.4C4 e cW Ptp .

yIAg51 4e S icva . OW 8VM -5 6¶44e LAWct.a,-mA& n tzome~~u - coW% 1a#,i,btris &cmc, Ceatoc- wO PIP ReoucER vG, E2 I kldr 41"txv- /

`~ \I f )Vrft Wf _ _ _ _ _ _ _ _ _ _

Plow A ReYieWer (Whin B 1 O = H;IC: ___Revieser.

54_ et) _CILcv. E Dae:.7, 4 "IteweoANII) J - - Mme a Refer to atuched Uimonc IRlCaiOfl Dg: Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 115 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 220/38 ASME CATEGORY: C-F-I ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.11 CONFIGURATION: PIPE TO ELBOW  % CRV ACHIEVED: 82.50%

PDI TECHNIQUE YES EXAM DATE: 8/30/99 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 30% SINGLE SIDED 12V EXAM DUE TO PIPE TO ELBOW CONFIGURATION.

2 80% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO ELBOW CONFIGURATION.

3 100% NONE 4 100% NONE 700 S1hEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 0% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO ELBOW CONFIGURATION.

2 100% NONE

• See attached CRV plots for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 116 of 184 Raytheon Rcp'ofl. 14 ii

• ' ngineers & Constructors ReportNo.: -_q0 Z CODE REQUIRED VOLUME COVERAGE PLOT FOR COMPONENT NO.:

4sy 0S-4 4 r/o w A~t6oL/ p /Pt Ai 3o7o 7O AZ~- 1Q CL- oo07 Ct co "Z Z1 - = -e v AefE~ ~eSf a7 Commas:,a75o ,oo'n & "vfe 7rO 19'62V' /""/ Ct/

G f /a-r Date F 3 -

I1 Exani tel-Im_, 4 td-.

I -r, s ._Vc - - V.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 117 of 184 IRaytheon f11 t')Engineers & Constructors Page of Rcpon No.: q - z -

CODE REQUIRED VOLUME COVERAGE PLOT FOR COMPONENT NO.: ZZO /3-?

7Q0 5 /4t rpml

~~br~

I IZ ZIE ----  :

I6A/ -

Comments: L tC-,D '; / .-  ;.',f, 1Pa,,iirJr CZ..

. ( Examiner / Level d- A5= Date JF I N, 3ly -  ?

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 118 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WN'ORKSHEET (UT)

COMPONENT ID: 220A/69 ASME CATEGORY: C-F-1 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.11 CONFIGURATION: 450 ELBOW TO PIPE  % CRV ACHIEVED: 71.50%

PDI TECHNIQUE NO EXAM DATE: 8/29/96 USED: . -

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 0% NO SCAN DUE TO 450 ELBOW TO PUP PIECE. CLOSE PROXIMITY OF WELD 68 WILL NOT ALLOW SCANNING FROM UPSTREAM SIDE (1 SCAN).

2 50% SINGLE SIDED 1/2V EXAM DUE TO 450 ELBOW TO PUP PIECE.

CLOSE PROXIMITY OF WELD 68 WILL NOT ALLOW SCANNING FROM UPSTREAM SIDE (1 SCAN). EXISTING WELD CROWN AND COMPONENT CONFIGURATION LIMITS SCAN AREA.

3 100% NONE 4 100% NONE 700 SHEAR SCAN SCAN  % VOLUME LIMITATION

._____ ACHIEVED 1 0% NO SCAN DUE TO 450 ELBOW TO PUP PIECE. CLOSE PROXIMITY OF WELD 68 WILL NOT ALLOW SCANNING FROM UPSTREAM SIDE (1 SCAN).

2 86% SINGLE SIDED 1/2V EXAM DUE TO 450 ELBOW TO PUP PIECE.

CLOSE PROXIMITY OF WELD #68 AND EXISTING WELD CROWN LIMIT SCAN AREA.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 119 of 184 CAROLINA POWER & LIGHT COMPANY Rcpon Number: q l WELD EXAMINATION PROFILE SHEET Page k of .

System: L4L. Weld No.: 692_1elkaA Plant: tKP eUnit: . . UT Exam Calibration Sheet No.: A.LI-Crown Height: *LL. Weld Toes Verified y: E3Direct VT Etch OStamp Marks QOther Crown Width: . . .. Weld Circumference/Length: q4.".

Note: Thickness measurements should be at 0.25' increments. Additional readings and locations can be performed at Technician's discretion and documented. Flow direction shall be noted. Weld profile shall be noted' showing crown, root, weld toes and joint configuration.

CPL-U II, Rev. A

. >~~~~~~~~~~~~~~~Dt

_______________70 __ _ __ _ __ P _ kkS EaieBy Eaie y eiwdApoe Date _ _ _ *___ _ t: _ _ _ _ _ _ _ _ D t: _ _ _ _ _ _

PL-UT-s Rev.. Ii,

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 120 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 239/01 ASME CATEGORY: C-F-I ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5. 11 CONFIGURATION: TEE TO PIPE  % CRV ACHIEVED: 89.50%

PDI TECHNIQUE YES EXAM DATE: 4/26/01 USE D:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 3 100% NONE 4 100% NONE 600 SHEAR SCAN SCAN  % VOLUME LIMITATION

._____ ACHIEVED 1 78.94% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

2 78.94% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

700 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 78.94% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

2 78.94% SINGLE SIDED 1/2V EXAM DUE TO PIPE TO TEE INTRADOSE CONFIGURATION.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 121 of 184 Washington Page WJY..

of NIA Client CP & L Project 11. B. Robinson Report No.: 01-055 System: IIPSI Procedure: HBR-Ur-l4 Rev.: 1 Date: 426101 UneNo.: 4-SI-I10 DrawingNo.: IlBR2-10618shL 105 Rev: S mponuntLD.: -239tl Search Uit Angie: 60° & 70 Modc: Shear Flow Tee Pipe Notc Weld width was less than thrte times the thickness. A 70° Shear was performed from both sides. therefore 100% coverage was obtained as deomonstrate during PDI-UT-2 procedure expansion for as welded conditions.

Were=cc the PDI letter dated April 18. 2000.

Pipe Tee Fxam;nton limited from 25 CW to 5.5" CW and S5 CW to 115 CW on the te side duc to configuntion.

rotal Coverage claimed for 6 = 50% (one sided exam) rota] Voltrne = 1.85'

-lockwst= 100%

aouteCckwise t 00%

Wlth FloW (8.25') l00%*57.89% = 57.89% 78.94%

With Flow (6') = 0%'42.1 1%= 21.05%

Against Flow (82") = 100%S7.89% = 57.89% 79.94%

Against nMw (6") = 50%*42.1 1%= 21.05" rotal = 357.88 14 =89.5%

TOtLW covtrace dd eaamiDer. Jy NIIkr 1f\ vvl ~ zLevel: IM Da: 4'# '0t EXa nw: A 11A

/ I ~ z , A & / -Level: A t//, -Date: Igf Reviewer (Wahington) - A(Client)

Reviewer.

r4a /ZA S LeVel:

~~~Level:

=

..- 2Z Date. 3° Date: __________

Reviewer. (Clent) Ma LCVI: DatC - - 1 Q Rcfir to attached Ultisonic Indication Data Sheet

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 122 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 212/21 ASME CATEGORY: C-F-2 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.51 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 75%

PDI TECHNIQUE YES EXAM DATE: 4/26/01 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% I 1/2V SINGLE SIDED EXAM DUE TO PIPE TO VALVE CONFIGURATION.

2 100% I 1/2V SINGLE SIDED EXAM (SCAN 1) DUE TO PIPE TO VALVE CONFIGURATION. SCAN 2 IS CREDITED BY I 1/2V SINGLE SIDED EXAM.

3 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

60 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% I 1/2V SINGLE SIDED EXAM DUE TO PIPE TO VALVE CONFIGURATION.

2 100% I 1/2V SINGLE SIDED EXAM (SCAN 1)DUE TO PIPE TO VALVE CONFIGURATION. SCAN 2 IS CREDITED BY I 1/2V SINGLE SIDED EXAM.

3 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 123 of 184 0j Washington PAge _. of 4 Client CP &L Prject H.B. Robinson ReponNo.: 01-044 System: Main Stem Procedure: BR-UT-86-9 Rev: 0 Date: 4f26/01 Line No.: 26-MS-1 Drawing No IBR2-10618 SHT-Pr71 Wa Rev.: 2 Component D.: 212/21 Componentlbickness: 1.042- Item No. CS.51 KI I +L2 + 1 +JO% 1-dZO%+I 1e So + 100/'<+ 0 O _ 3_ _ 7 n 4 4 4 7%2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -- _-- - i Examiner: ZUALA/~ Level: Date: 4-24 -of Examincr le>/zf ^ Level: Dat:

Reviewer: (&asnitu) - Level: _ _: '6/v A) I/1 Reviewer. (Client) lb..,- Level: - 5, 3-01 Reviewer. (ANII) _ __ _D te:

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 124 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 213/17 ASME CATEGORY: C-F-2 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.51 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 85%

PDI TECHNIQUE NO EXAM DATE: 9/13/96 USED:

450 SHEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% 1 1/2V SINGLE SIDED EXAM DUE TO PIPE TO VALVE CONFIGURATION.

2 100% 1 1/2V SINGLE SIDED EXAM (SCAN 1) DUE TO PIPE TO VALVE CONFIGURATION. SCAN 2 IS CREDITED BY 1 1/2V SINGLE SIDED EXAM.

3 70% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 70% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 125 of 184

./

I CAROLINA POWER & LIGHT COMPANY Report Number:  ?&- Z7 WELD EXAMINATION PROFILE SHEET Page 3 of 3 System: m s . Weld No.: -L lk3. W17 Plant: ( p3 Unit: -L.... UT Exam Calibration Sheet No.:

Crown Height: . " Weld Toes Verified By: Mtirect VT OEtch OStamp Marks QOther Crown Width: 1 3" Wild Cisrm be ngth: a 6, V Note: Thickness measurements should be at 0.25' increments. Additional readings and locations can be performed at Technician's discretion and documented. Flow direction shall be noted. Weld profile shall be noted showing crown, root, weld toes and joint configuration.

~~~~~~V- _-e

. ~~-T_ -1H S~~~~~~~~~~~~~~~~~('

te Examined By: Examined By: Reviewed Approved Date: 9_ 4s - Date:

MA

/jJ Date:

,/

I____6_____

//

trL-ul-IL'ALY. J

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 126 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 213/22 ASME CATEGORY: C-F-2 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.51 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 87.50%

PDI TECHNIQUE NO EXAM DATE: 9/12/96 USED:

450 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% 1 1/2V SINGLE SIDED EXAM DUE TO PIPE TO VALVE CONFIGURATION.

2 100% I 1/2V SINGLE SIDED EXAM (SCAN 1) DUE TO PIPE TO VALVE CONFIGURATION. SCAN 2 IS CREDITED BY I 12V SINGLE SIDED EXAM.

3 75% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 75% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA103-0160 Page 127 of 184 F.."

I~. A CAROLINA POWER & LIGHT COMPANY Repon Number .. ,2LA WELD EXAMINATION PROFIL SHEE Page _!L of _L_.

M System:.4&55 Weld No.: A a PL a

,, . . x . Unit: a Iru Exam Calibration sheet No.: _

Crown Height: to" Weld Toes Verified By: 'Dircct VT Etch OStamp Marb 0Other Crown Width: LI. ..... Weld CircumferenceLngth: pce I Note: Tickness measurements should be at 0.25' increments. Additional readings and locations can be performed at Tichnician's discretion and documented. Flow direction shall be noted. Weld profle shall be noted showing crown, root, weld toes and joint configuration.

Reviewed Approved l Ined Ay:

9; N/A~~~~~

t / I I Date: 9-42-96 .

I

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 128 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 214/19 ASME CATEGORY: C-F-2 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.51 CONFIGURATION: PIPE TO VALVE  % CRV ACHIEVED: 75%

PDI TECHNIQUE YES EXAM DATE: 4/26/01 USED:

450 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED I 100% NONE 2 100% NONE 3 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

600 ShEAR SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 100% NONE 2 100% NONE 3 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 50% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 129 of 184 0 Washington Page W.R.

4 of___

Client: CP&L Project: H.D Robinson ReportNo.: 01-045 System: Main Steam Pocedwe: HR-UT-B69 Rev.: 0 Date: 4126/Di Une No.: 26-MS-3 Drwing No.: IIBR2-1061B SHT.73 Rev: 2 Component l.: 214119 ComponentThickness: I.042" Item No. C5.SI

_____________ Io% 4- 106 -+ ( O  % I 4 4 -4

= =m Level: _ ~Date:

S4f2=°-/

Examine.z/ Leel: ,/8 Date: 4,//A Reviewer (W"aingtM) ) 4 Level: Date: 41 7 Reviewer. (Client) -Level: .1 Date: n S- I Reviewer_(ANII) _ _ _ _ _ _ _. Date:

.__ 2101&

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 130 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (UT)

COMPONENT ID: 216/15 ASME CATEGORY: C-F-2 ASME CODE FIGURE: IWC-2500-7 ASME ITEM NUMBER: C5.51 CONFIGURATION: VALVE TO PIPE  % CRV ACHIEVED: 71%

PDI TECHNIQUE NO EXAM DATE: 9/12/96 USED:

450 SHEAR & RL SCAN SCAN  % VOLUME LIMITATION ACHIEVED 1 60% 1 1/2V SINGLE SIDED EXAM DUE TO PIPE TO VALVE CONFIGURATION.

2 100% 1 1/2V SINGLE SIDED EXAM (SCAN 1) DUE TO PIPE TO VALVE CONFIGURATION. SCAN 2 IS CREDITED BY 1 1/2V SINGLE SIDED EXAM 3 62% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

4 62% LIMITED EXAM DUE TO PIPE TO VALVE CONFIGURATION AND WELD CROWN.

• See attached CRV plot for examination coverage.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 131 of 184 CAROLINA POWER & UGHT COMPANY "ICAROLINA POWTER & LIGHlT COMPANY Report Number: J

!_WE T EXAMNATION PROFILE SHEET Page -3 of -

System: rei Weld No.: ct .V (4 s

' Plant: R T) Unit: a it UT Exam Cajibration Sheet No.: _____

Crown Height: I. Weld Toes Verified By: Direct VT OEtch Stamp Marks 0Other Crown Width: 1. 3" Weld Circumference/Length: /( "

Note: Thickness measurements should be at 0.25' increments. Additional readings and locations can be performed at Technician's discretion and documented. Flow direction shall be noted. Weld profile shall be noted showing crown, root, weld toes and joint configuration.

Pcout.. fit bake Žt.s cnme ~ .

I 1 v~~~~~~~~~~~

fi~~~~

I-sr

,Exam'ed By: Examined By: Reviewed Approved Acid ~~~~~~~~~~

JV/

l>~~~~~~~~~,,)

14. e Date i - '2- - Date: _ _ _ __ Date:' 1- /J/i6 PLUT-1 Rev.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 132 of 184 CATEGORY C-C WELDED ATTACHMENTS Component(s) for Which Relief is Requested The components applicable to this relief request are the HBRSEP, Unit No. 2, welded attachments identified in Table 1.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Category C-C, Item Numbers C3.10 and C3.20. The applicable Code examination requirements, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," for the components listed in Table 1, require that examination coverage be essentially 100% of the subject weld or component. Although this Code Case applies to volumetric examinations, application of the same technique (i.e., >90% surface) for restricted access has been applied.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Category C-C, Item Numbers C3.10 and C3.20, as interpreted by Code Case N460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90%). The examination coverage achieved for the components listed in Table I are the maximum extent practical for these components.

Table 1 lists the coverage that was achieved and the reason for the limitation.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of these components. It is judged that patterns of degradation of the listed components would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the listed components has been provided.

Surface examination techniques utilized during the Third Ten-Year Interval on the affected configurations were consistent with industry standards during the time frame the exam occurred and were essentially unchanged during the interval. The affected configurations depict the support integral attachments and the examination area covered during the examination. Physical restrictions due to support configuration were the limiting factor which resulted in limited examination of the attachment welds.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 133 of 184 Additional information included in support of this relief request are Inservice Inspection Determination of Percent Coverage Worksheets, associated sketches for surface examination coverage limitations, and supplemental photographs showing component configurations, as applicable.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 134 of 184 TABLE 1 INTEGRAL ATTACHMENT COVERAGE AND LIMITATIONS Drawing/ Description Category Item NDE Exam Limitation/Comment Examination Type Component Coverage (Manual or Automated) 202/WS-1 Boron Injection C-C C3.10 SUR 88% Boron Injection Tank support leg Manual 202/WS-2 Tank Integral configuration.

202/WS-3 Attachments 202/WS-4 (Support Legs) 2041WSI-A Residual Heat C-C C3.10 SUR 80% Residual Heat Exchangers exam is Manual Exchanger Integral limited by physical Attachments access/component configuration.

(Support Legs) 212/A-WS Main Steam System C-C C3.20 SUR 50% Support configuration. Manual Integral Attachment 212/R-WS Main Steam System C-C C3.20 SUR 50% Support configuration. Manual Integral Attachment 213/F-WS Main Steam System C-C C3.20 SUR 84% Support configuration. Manual Integral Attachment 214/K-WS Main Steam System C-C C3.20 SUR 50% Support configuration. Manual Integral Attachment 216/G-WS Feedwater System C-C C3.20 SUR 50% Support configuration. Manual Integral Attachment 221A/1-WS Safety Injection C-C C3.20 SUR 75% Support configuration. Manual System Integral Attachment 233/D-WS Safety Injection C-C C3.20 SUR 50% Support configuration. Manual System Integral Attachment

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 135 of 184 TABLE 2 INTEGRAL ATTACHMENT MATERIAL IDENTIFICATION WELD ID CODE CODE DESCRIPTION MATERIAL I MATERIAL 2 CATEGORY ITEM# ,

2021WS-1 C-C C3.10 Boron Injection Tank Integral Attachments (Support Shell Attachment 2021WS-2 Legs) SA-351 CF8A 202/WS-3 202/WS-4 204/WS1-A C-C C3.10 Residual Heat Exchanger Integral Attachments Shell Attachment (Support Legs) SA-240 TP-304 SA-7 steel 212/A-WS C-C C3.20 Main Steam System Integral Attachment Pipe Attachment A-106 GR B A-500 GR B 212/R-WS C-C C3.20 Main Steam System Integral Attachment Pipe Attachment A-106GRB A-106GRB 213/F-WS C-C C3.20 Main Steam System Integral Attachment Pipe Attachment A-106 GR B A-106 GR B 214/K-WS C-C C3.20 Main Steam System Integral Attachment Pipe Attachment A-106GRB A-106GRB 216/G-WS C-C C3.20 Feedwater System Integral Attachment Pipe Attachment A-106GRB A-106GRB 221A/1-WS C-C C3.20 Safety Injection System Integral Attachment Pipe Attachment A-312 TP-304 A-312 TP-304 2331D-WS C-C C3.20 Safety Injection System Integral Attachment Pipe Attachment A-312 TP-304 A-312 TP-304

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 136 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WN'ORKSIIEET (PT)

COMPONENT ID: 2021WS-1 ASME CATEGORY: C-C 2021VS-2 202/WS-3 202/VS-4 ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.10 CONFIGURATION: WELDED ATTACHMENTS TO  % CRS ACHIEVED: 88%

VESSEL PDI TECHNIQUE N/A EXAM 202WS-1 4/14/92 USED: DATES: 2021WS-2 8/29196 2021VS-3 4/8/01 202/VS-4 4/26/01

• See CRS sketches for examination coverage, and supplemental photographs showing component configurations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 137 of 184 0 Washington P 7 ,< A*3 40-Clieut: CP IL Prp. o o R l No.: Oi - 0 z SYV= = IJV-7rAMI PrMI: Ai- P,. ~-/ Rev.: / Dat: 8 op LineNo.: Brr Tt1 DriwingNo.: HEV.%-10.B61 SH 5-N Rv.:

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 138 of 184 Page *... of .A . ¶,

Washington Pe NWA Client CP&L Project: H.B.Robinson ReponNo.: 01-04Z-System: 2080 SafCty Ineetion Procedure: H tBR-PT6-8l Rev, I .jDatc: 40 LincNo.: Boron niection Tank Drawing No: HBR2.10618 R.:___ I Component ID.: 20V1WS-3 Search Unit Angic: NIA Mode: NA Area A 2.50' x 16.00- = 40.00' r - - - -Area I B 1.75 x 7.0 12 25' 1Area C 250' x 16.00' -40.00'2 I Area D 16.00 x 050 - 8.00' AreaE7.00O50*3.50'

l. _ _ _ _ ; _ _ @ 1 l Area F 16.00' 050' - 8.00' Area G 16.00' x 050- - 8.00' I I Area It 13.00' x 0.50 - 7.50' Area I 1O6.0x 050- = 8 .00' Area J (1.50- x 050-) x 2 1.50 Restriction l I IX Area K (.50 x 0.50-) x 2 - 1.50 Rcstriction Area L 10.00-x LS0- 15.00' Restriction Area L = weld (0.50') +050 both sides i oIQ

> ~ 150.25' Total Examination Surface I 8.00' Total restriction 132.25 + 150.25' = 0.802 or 88.02%

I Level: A h Date: h 4

_Level: Z! Date: 4-8^-0/

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 141 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (PT)

COMPONENT ID: 2041WS1-A ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.10 CONFIGURATION: WELDED SUPPORTS TO  % CRS ACHIEVED: 80%

SHELL PDI TECHNIQUE N/A EXAM DATE: 8/30199 USED:

• Integral surface examination limited by support/vessel configuration. See CRS sketch for surface examination coverage, and supplemental photograph showing component configuration.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 144 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WVORKSIIEET (NIT)

COMPONENT ID: 212/A-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 50%

PDI TECHNIQUE N/A EXAM DATE: 10/7/93 USED: II

• The magnetic particle examination of this support could only be performed in one direction. The coverage is estimated at 50% of the Code-required surface (CRS). See CRS sketches for surface examination coverage limitations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 145 of 184 A, .,2, F 4 020i RESTRAINT LOCATION:

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 154 of 184 Al t24s NOTES:

1. FOR GENERAL NOTES. SEE SK-410D-CAR-GN-1, LATEST REVISION.

2. ALL WELDS ARE NEWAWELDS UNLESS OTHERWISE NOTED.

3. CONCRETE SHALL BE REI1OVED TO THE LIMITS SHOWN TO EXPOSE THE REINFORCING.BARS.

4. PRECAUTIONS SHALL BETAKEN 'TO AVOID DAMAGE TO BARS'DURING ALL CON1CRETE REtDVAL'OPERATIONS.

5. EXPOSED REINFORCING BARS SHALL BE CLEAN AD FREE OF OLD

'CONCRETE.

.6. EXPOSED CONCRETE SURFACES'-AGAINST WHICI NEW CONCRETEVWILL BE PLA'CED.SHALL.:BE ROUGHENED TO APPROXIMATELY..1/4 IIICH AND CLEANED PRIOR TO THE PLACEiENT.OF THE'REINFORCING BARS AND Ln NEW CONCRETE."

7. NEW REINFORCI[lG BRS SHALL.'BE DEFORMED AND SHALL CONFORM TO THE REQUIREMENTS 'OF.EBASCO'SPECIFICATION CAR-HBR-C-3; DATED.

-x FEBRUARY 3, 1977. ALLEBARS SHALL BE BENT COLD.

8. REINFORCING BAR WELDING PROCEDURES,'WORKM'ANSHIP, UALIFICATIONS, AND ISPECTION'SHALL BE PERFORMED IN ACCORDANCE WITHIAWS-D1.ti-79, "STRUCTURAL WELDING CODE - REINFORCING STEEL", SECTIONS 1, 4, 5, 6 AND 7, FOR ASTM A515 'GRADE 60 BARS'.

WELDING SHALL.BE ERFORf`ED USING THE MANUAL SHIELDED METALARC (SMAWI PROCESS. LOW'HYDROGEN ELECTRODES SHALL BE STORED 'III OVENS PER AWS Dl.14-79, ..AND.SHALL NOT BE'EXPOSED TO 'ASIENT ATMOSPHERE.FOR'MORE THAN .'ONE HOUR PRIOR'TO USE.

Mi[NIMUM PREHEAT.-AND INTERPASS TEMPERATURES SHALL BE IN ACCORDANCE.WITH AWS D1.4-79'TARLE 5.2.

ALL WELDS SHALL BE`VISUALLY EXAMINED' FOR NONCONFORMANCE WITH THE- ACCEPTANCE STANDARDS OF-AWS'D1.4-79, SECTION .4.'

NUCLEAR SAFET Y REL ATEDI

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EXPOSED REINFORCING BARS SHALL BE PROTECTED DURING THE WELDING OPERATION4 TO PREVENT INADVERTENT ARC STRIKES.

kC" 9. CONCRETE SHALL BE PLACED TO ORIGINAL CONFIGURATION. CONCRETE SHALL BE IN ACCORDANCE WITH CP&L SPECIFICATION L2-C-OO8 AND L-C-011, LATEST REVISIONS.

I0. AFTER CONCRETE HAS CURED, THEORIGIJAL COATIAG SYSTEM SHALL BE- APPLIED TO ALL CONCRETE SURFACES, IN ACCORDANCE WITH WORK PROCEDURE WP-3.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 156 of 184 AF I I N BILL OF MATERIALS QA CLASS

-3 ITEM OTY DESCRIPTION Q -NA

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 157 of 184 Ar g9241 Al BILL OF MATERIALS

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 158 of 184 BILL OF MATERIALS

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAI03-0160 Page 159 of 184 ea f -o(3 LIP1L TEb EXP1 ouc rO coMoiNENr ONE OrREeTzOM OAY.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 160 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (NIT)

COMPONENT ID: 212/R-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 50%

PDI TECHNIQUE N/A EXAM DATE: i0/793 USED: I I I

• The magnetic particle examination of this support could only be performed in one direction. The coverage is estimated at 50% of the Code-required surface (CRS). See CRS sketches for surface examination coverage limitations, and supplemental photograph showing component configuration.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 161 of 184 AK I .

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- p IDIV.CIVIL IDATEI&CR.A SERVICES VASCOINCORPORATED DR.GII- APPROVED F-2 -------

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M5-IA-1007 SCALE TS HS I ISO NO./ POINT NO. MS-IA/ 1007 SH ILOF1

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 162 of 184

i. _:-;

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAI03-0160 Page 163 of 184 TAThARL F1 FCrlET A -WC TA~LVIPE NICUME~aC RV/;

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,qtjp 4-2-cftj,

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 164 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (MT)

COMPONENT ID: 213/F-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 84%

PDI TECHNIQUE N/A EXAM DATE: 3/21/98 USED: I I

• The magnetic particle examination of this support was limited due to the configuration. The coverage is estimated at 84% of the Code-required surface (CRS). See CRS sketches for surface examination coverage limitations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 165 of 184 b RESTRAINT LOCATION:

=lbs SEE ISO NO. NS-IB PT NO. I o5000s)

=Ibs b 9,96o REACTOR BLDG-OUTSIDE

+j 9,44dS CRANE WALL 40 PIPE RESTRAINT STRUCTJRE LOAD CASE VW+ TDit*+o

-QAQSAF ('v+Tht4 +.O I!D CHT9 ?-UN BASE PLATE I DENTIFICATION IY8 8WIPE-_

I VTE: 0-11?~1E: 11:°1 AMj RESTRAINT LOADS I MOD. NO.

PMR. NO.

N /A N /A RING PeE(WELVE TO PIPE) i AELPEO . RIvNG:L EBASCO SERVICES INCORPORATED H. B. ROBINSON - UNIT 2 DIV.CIVIL D)f APPROVED AS-BUILT RESTRAINT SKETCH AB-CAR -

DATElI:4EhCRcr SYSTEM: MAIN STEAM MS-IB-1005 SCALE NTS I , ,, ISO NO./POINT NO. Ms-IB/ looS SK-LOF-L

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAJ03-0160 Page 166 of 184 T1TEG1PR L RBlmc"[ENT F-W1.J M

36ML-PIVE-Mr-UMV RENf, /;_

gREREAIED '7' iAD V M j-Pe dscu sbn thj Scot Lrs&-, alp canrnt aO.pl PT tz nCrC0Mw cV1 i

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 167 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WORKSHEET (MT)

COMPONENT ID: 214/K-WS ASME CATEGORY: C-C I ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 50%

PDI TECHNIQUE NiA EXAM DATE: 3/24/98 USED: I I

• The magnetic particle examination of this support was limited due to the configuration. The coverage is estimated at 50% of the Code-required surface (CRS). See CRS sketches for surface examination coverage limitations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 168 of 184

. + RESTRAINT LOCATIOt N:

N F= lbs SEE ISO NO. M5-1IC

[100.

, I Fyn - lbs PT NO. 1003N I1 W/A C- ) RP-ACTOK L-DC4 Ib H/A +az > FzII9'9WZbs DUT51DE CRANE " VAI

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BASE PLATE DATE:89-84TIME:I*4 PM MOD. NO.

IDENTIFICATION RE5TRAINT LOAD5 PMR. NO.RN:N/A I} _t _I .- t WELMP TOP WW4( i

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,BASCO SERVICES INCORPORATED H. B. ROBINSON - UNIT 2 APPROVED AS-BUILT RESTRAINT SKETCH AB -CAR-DyVCIVtILDR.9 D I D.SC ,. P SYSTEM: MAIN STEM L5-IC-100 SCALE NTS s0oS I ISO NO./ POINT NO. 85-IC/IOO

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RAI03-0160 Page 169 of 184 Pp r. L2 OF bAT- hest

• 1-;Vj, algal/

TflTEflT-L BTMClAEliM -W1

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/ An LF~*~mI~T TP Pl C\RCUNLERECF g22/6

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trsx Le also ejjaul bt. .eA.~I DE>: Ado po /2f r~a~casabz #r lznfr8 i

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 170 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WN'ORKSHEET (NIT)

COMPONENT ID: 216/G-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 50%

PDI TECHNIQUE N/A EXAM DATE: 10/10/93 USED: I I

• The magnetic particle examination of this support was limited due to the configuration. The coverage is estimated at 50% of the Code-required surface (CRS). See CRS sketches for surface examination coverage limitations.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 171 of 184 C(ZR-K /&-ujS RESTRAUT LOCATIOM SEE bO NO. FW-re, PT NO. 04 (1)

R 6 OUT'5DE CRANE WALL - OLJrH

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 172 of 184 AF 1245 4 0

tn Cv LUGS WELDED 0C ON OP ARD ALONG -

OUT 51DE TP) Pt N

5ECT A I Iz 17.1u165!

llI-vilb~d k es[1/

_fswA-NUCLEAR 5AFETY RELATED I IREVI DATE I BY ICHKIAPk EBASCO SERVICES INCORPORATED H.S. ROBINSON - UNIT 2 A DIV.VYIVL DR.FT APPROVED AS-BUILT RESTRAINT SKETCH AB-CAR-DATE90 '4:laRJ,t SYSTEM: FED WAlrE P .w-%-10 SCALE NTS #54 ISO'NO./POINT NO. -55/10Z4 SH.-2 OF%.

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 173 of 184 JP /2J8 ie57 Cc 2 e 2 co~~- A 4WI 729 (e,,~

7-U~e.4 -7/OAM

+ EOAD/REC7/c7j 6 2 L>

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 174 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE WN'ORKSHEET (PT)

COMPONENT ID: 221A/1-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 75%

PDI TECHNIQUE N/A EXAM DATE: 8/22/96 USED: I I _ _ I

• The liquid penetrant examination was performed on three of the four lugs on the subject support. The top/east lug is inaccessible due to obstruction caused by hanger design/installation. The total Code examination coverage of the required examination area was 75% (i.e., 25% reduction in coverage). The coverage obtained was the maximum practicable coverage due to the obstructions to surface examination caused by the permanent hanger installation. See sketches for surface examination coverage limitations, and supplemental photograph showing component configuration.

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 175 of 184 I RESTRAINT LOCATION:

• r, lb; SEE ISO NO. SL-20 PTF NO. 1200 (0)

F lbs 10 -AC- I - LC-140 PfIFE A LLEy -

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HoTh CORI 0 J LO A.5E BASE PLATE IDENTIFICATION LOADS N

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-A5-BU1LTLRESTRAW-.SKET.CK.I.-

I DATE SCALE NTS SYSTEM: SAFETY INJECTION ISO NO./ POINT NO.51-20/1z0

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 176 of 184 A

L e Lh/1iz rT CLEAR N CONT CTyP)

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 177 of 184 LU1l% KI ClP)

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 178 of 184 H.B. ROBINSON - UNIT 2 DIV.C2YVB.DR.Z&- APPROVED I AS-BILT.RE5TRAINT SKETCH .A-CAR-I DATE'1 SCALE NTS 4 C.., 7ne7n I

1 SYSTE/SAFETY IN5ECTION 5 1>O ISO NO./POINT NO.5I-Z011ZOO SHCARFS

+ r-Pbtz2WA

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 179 of 184 BILL OF MATERIALS QA CLASS ITEM QTY DESCRIPTION l NA 7 ~ ~~~

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ALL STRUCTURAL STEEL ASTM A 36 UNLESS NOTED I3 3 15L k-c.

REV DATE BY CHK A1k EBASCO SERVICES INCORPORATED cpaL/H.B.ROBINSON-UNIT 2 Ab -CAR-DIV.CIVILDR..Ik.. APPROVED A-BUILT RESTRAINT MUECH SAT OAT'~"cR4 . SYSTEM: Av-reY 'rW SC-T10'J ISO ./POINT NO.S=Zc4I7---

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 180 of 184

, 4,Ik J -,.t,,E.w<m a,.', #, _s HEAR CV_

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 181 of 184 INSERVICE INSPECTION DETERMINATION OF PERCENT COVERAGE VORKSIIEET (PT)

COMPONENT ID: 233/D-WS ASME CATEGORY: C-C ASME CODE FIGURE: IWC-2500-5 ASME ITEM NUMBER: C3.20 CONFIGURATION: INTEGRAL ATTACHMENT  % CRS ACHIEVED: 50%

PDI TECHNIQUE N/A EXAM DATE: 4/13/92 USED: I

• A liquid penetrant examination was performed on one of the two subject welded attachments. The backside lug is inaccessible due to obstruction caused by hanger design/installation, and piping above and below the subject integral attachments, making it physically impossible to access. The total Code examination coverage of the required examination area was 50% (i.e., one of the two lugs). The coverage obtained was the maximum practicable coverage due to the obstructions to surface examination caused by the permanent hanger installation and adjacent piping. See sketches for surface examination coverage limitations.

United States Nuclear Regulatory Commission.

Attachment to Serial: RNP-RA/03-0160 Page 182 of 184 A.VIw~.2^ -: "

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- - RESTRAINT LOCATION:,;

• '~~:j~~SEE 1SON0O.1ZQ

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United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 183 of 184 PAGE OF PAGE - OF 1151 DATA SHEET NO.

EXA ITEM 10 9r-;Xo CPL-Z33- D-REVI ISO TDWG. NO. - C1 -2 ?3 SKE TCH SHEET A

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ri, LMT1,,M EXAMINER 6VO -

0-d-: LEVEL LEVEL Jr AV',

DATE OATE t/ -/3-92_

WV/4f EXAMIN£R "A.

REVIEVER LEVEL 'or REVIEWER DATE Z<Z?;: E Z REVIEWER CC/ 0Z!1 DATE W & 4S-_

United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/03-0160 Page 184 of 184 CATEGORY B-G-1 REACTOR COOLANT PUMP STUD Component(s) for Which Relief is Requested The component applicable to this relief request is the HBRSEP, Unit No. 2, reactor coolant pump stud number 7.

Code Examination Requirements The applicable Code edition is the 1986 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Category B-G-1, Item Number B6.180. The applicable Code examination requirements, as interpreted by Code Case N-460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," require that examination coverage be essentially 100% of the subject component.

Requested Relief Relief is requested from the examination requirements of the ASME Code, 1986 Edition,Section XI, Category B-G-1, Item Number B6.180, as interpreted by Code Case N-460, "Alternative Examination Requirements for Class 1 and Class 2 Welds,Section XI, Division 1," which states that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10% (i.e., coverage is greater than 90o). The examination coverage achieved for reactor coolant pump stud number 7 was the maximum extent practical for this component.

Basis for Requested Relief This relief is requested pursuant to 10 CFR 50.55a(g)(6)(i) on the basis that compliance with the referenced Code requirements is impractical and that public health and safety will not be endangered by allowing the proposed alternatives in lieu of Code requirements. Substantial burden would be incurred to achieve additional coverage of this component. It is judged that patterns of degradation of this component would have been detected by the coverage that was achieved. Therefore, reasonable assurance of the integrity of the component has been provided.

The ultrasonic examination technique utilized during the Third Ten-Year Interval on reactor coolant pump stud number 7 was a stud bore probe. A limitation was identified on the lower eight inches of this stud due to a taper restriction. Future examination of this stud will be performed utilizing the PDI technique, which will encompass 100% of the reactor coolant pump studs. The limitation on reactor coolant pump stud number 7 equates to less than 0.36% of the overall volume of the reactor coolant pump studs when taken in aggregate.