ML19165A140

Response to Request for Additional Information - Relief Request 63 - Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval

ML19165A140
Person / Time
Site:	Palo Verde
Issue date:	06/14/2019
From:	Lacal M Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-07929-MLL/MDD
Download: ML19165A140 (8)

Text

102-07929-MLL/MDD June 14, 2019 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station Unit 3 Docket No. STN 50-530 Renewed Operating License No. NPF-74 10 CFR 50.SSa MARIA L. LACAL Se ni o r Vi ce Pr eside n t, N uc l ea r Reg ul a t o ry & Ove r s i g ht Palo Verde Nuclear Generating Station P.O. B ox 52034 P h oe ni x, AZ 85072 M ai l Stat i o n 7605 Tel 623.393.6 4 9 1 Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval By letter number 102-07851, dated January 10, 2019 (Agencywide Documents Access and Management System Accession No. ML19010A307), Arizona Public Service Company (APS) submitted relief request 63 in accordance with 10 CFR 50.55a(g)(S)(iii).

Certain ultrasonic e x aminations of welds identified in letter 102-07851 required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, sub-articles IWB-2500 and IWC-2500 have been determined to be impractical for Unit 3 third 10-Year inservice inspection interval.

The Nuclear Regulato r y Commission (NRC) staff has requested additional information (RAI) to complete their review with regard to ASME Code class 2 components.

A clarifying phone call was held between NRC and APS on April 4, 2019, to discuss the additional information needed. The APS response to the request for additional information is provided in the enclosure to this letter. The response due date was June 7, 2019. APS has granted a week extension to June 14, 2019 for the response during a call with the NRC project manager on June 5, 2019. No new commitments are being made in this submittal.

If you have any questions about this request, please contact Michael D. Dilorenzo, Department Leader of Nuclear Regulatory Affairs, at (623) 393-3945. Sincerely, ~* cxf~ MLL/MDD

Enclosure:

Response to Request for Additional Information

-Relief Request 63, Unit 3 Impractical E x aminations for the Third 10-Year Inservice Inspection Interval cc: S. A. Morris S. P. Lingam C. A. Pea body NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance L L C Callaway* Diablo Canyon* Palo Verde* Wo l f Cr e ek Enclosure Response to Request for Additional Information Relief Request 63 Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval 10 CFR 50.SSa Request Number 63 Response to Request for Additional Information Unit 3 Inservice Inspection Impracticality Third 10-Year Inservice Inspection Interval By letter number 102-07851, dated January 10, 2019, Agencywide Documents Access and Management System Accession No. ML19010A307, Arizona Public Service Company (APS) submitted relief request 63 in accordance with 10 CFR 50.55a(g)(S)(iii).

Certain ultrasonic examinations of welds identified in letter 102-07851 required by Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, sub-articles IWB-2500 and IWC-2500 have been determined to be impractical for Unit 3 third 10-Year inservice inspection interval (ISi). The Nuclear Regulatory Commission (NRC) staff has reviewed RR 63 and requested additional information in order to complete the review with regard to ASME Code Class 2 components.

A clarifying phone call was held between NRC and APS on April 4, 2019, to discuss the additional information needed. The APS response is provided after each NRC request for additional information.

NRC MPHB-RAl-1:

Please discuss whether, as a substitute, examinations were performed on similar welds in the same piping systems that essentially 100 percent coverage could be achieved.

APS Response:

There are no examinations that can formally be credited in place of the limited examinations identified in Tables 2 and 3 of Relief Request 63. However, other ultrasonic (UT) examinations were completed on similar welds of the same piping systems, often on the same lines, that have essentially 100 percent coverage and no rejectable indications.

Those completed UT examinations which correspond to the limited examinations within the same piping systems are referenced in Tables 2A and 3A. NRC MPHB-RAl-2:

One of the notes associated with Tables 2 and 3 of the relief request states that " ... All piping material for C-F-1 welds in the Table above are Austenitic Stainless Steel ... " Please discuss the exact weld metal (material specification) used in the welds of Tables 2 and 3 APS Response:

Tables 2B and 3B have been provided as supplemental information to Tables 2 and 3 that were originally submitted as part of Relief Request 63. Tables 2B and 3B provide two weld material specifications for each weld. Specification "SFA-5.9 / ER316 / F6 / GTAW" was used for the initial passes (root) of each weld. The balance of each weld was completed using either SFA-5.9 / ER316 / F6 / GTAW or SFA-5.4 / ER316 / F5 / SMAW.

Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval NRC MPH8-RAl-3:

Tables 2 and 3 of the relief request show that welds are located in various zones. Please describe the location of these zones (inside or outside of the containment), how the zones are designated, operational leakage monitoring and radiation dose, if any, in these zones. APS Response:

The location of the applicable zones are provided in Tables 28 and 38. The ISi program is subdivided into zones for convenience of program management.

Each zone may represent a room within the plant or a portion of a system separated by building penetrations, code classification boundaries, or otherwise.

The Unit 3 Inservice Inspection program currently defines zones 1 through 6, and zones 16 through 129. Zones 7 through 15 are not currently used as zone designations within the program. The physical locations of each weld have been provided in Tables 28 and 38, however the piping/line description resides in Tables 2 and 3 of Relief Request 63. Leak detection/monitoring is provided for the areas and/or rooms and includes control room indication.

Dose rates for each room have been provided in Tables 28 and 38 as averages during the previous 5 years. NRC MPH8-RAl-4:

Please discuss the design and operating conditions (e.g., temperature and pressure) of the welds in Tables 2 and 3 of the relief request. APS Response:

Design and operating conditions (e.g., temperature and pressure) of the welds identified in Tables 2 and 3 have been provided in Tables 28 and 38. 2 Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 2A -SUQQlemental Information for Category C-F-1, Item CS.11 Welds Limited Exam Weld Information Similar Code Required Volume Weld Information ISI Zone Weld No.(s) Pipe Comments No. Weld No. Pipe Diam. Weld Configuration Credited with Diam. Weld Configuration (inches) Code Required (inches) (in direction of flow) Volume 83 74-105 14 sweepolet to pipe 74-115 14 pipe to elbow Same line 90 85-9 24 flange to pipe 85-29 24 pipe to elbow Same line 90 85-11 24 pipe to valve 85-29 24 pipe to elbow Same line 91 76-7 12 orifice to pipe 76-8, 76-2 12 pipe to elbow (76-8), Same line reducer to pipe (76-2) 91 77-7 12 orifice to pipe 77-8 12 pipe to elbow Same line 91 77-14 12 pipe to valve 77-8 12 pipe to elbow Same line 91 77-16 12 valve to pipe 77-8 12 pipe to elbow Same line 78-45, 78-44, elbow to pipe (78-45), 98 78-47 12 pipe to valve 78-43 12 pipe to elbow (78-44), Same line elbow to pipe (78-43) 22-21, 22-17, pipe to elbow (22-21), 101 71-123 16 valve to pipe 22-14 16 pipe to elbow (22-17), Same line pipe to elbow (22-14) 104 85-46 20 pipe to valve 85-44 20 elbow to pipe Same line 104 85-47 20 valve to pipe 85-44 20 elbow to pipe Same line 3 Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 3A -Sui:;1i:;1lemental Information for Category C-F-1, Item CS.21 Welds Limited Exam Weld Information Similar Code Required Volume Weld Information

!SI Zone Weld No.(s) Pipe Comments No. Weld No. Pipe Diam. Weld Configuration Credited with Diam. Weld Configuration (inches) Code Required (inches) (in direction of flow) Volume tee to pipe (110-25), This line changes line number and 110-25, 110-33, size, but runs continuous with the 110 110-17 2 pipe to valve 110-34 4 orifice to pipe (110-33), line of the three welds identified as pipe to elbow (110-34) similar welds tee to pipe (110-25), This line changes line number and 110-25, 110-33, size, but runs continuous with the 110 110-52 2 pipe to tee 110-34 4 orifice to pipe (110-33), line of the three welds identified as pipe to elbow (110-34) similar welds This line changes line number and 111 111-34 4 pipe to orifice 111-21 2 pipe to elbow size, but runs continuous with the line of the weld identified as a similar weld This line changes line number and 113 113-28 2 valve to pipe 113-2, 113-9 4 (113-2), elbow to pipe (113-2), size, but runs continuous with the 2 (113-9) elbow to pipe (113-9) line of the two welds identified as similar welds 118 118-46 3 penetration to pipe 118-47, 118-48 3 Pipe to elbow (118-47), Same line elbow to pipe (118-48) 118 118-49 3 pipe to valve 118-47, 118-48 3 Pipe to elbow (118-47), Same line elbow to pipe (118-48) 119 119-52 3 pipe to valve 119-26 3 tee to pipe Same line This line changes line number and 119 119-53 2 valve to pipe 119-26 3 tee to pipe size, but runs continuous with the line of the weld identified as a similar weld 4 Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 2B -SURRlemental Information for Category C-F-1, Item CS.11 Welds ISI Pipe Typical Design Conditions Operating Conditions Weld Filler Material Specifications Area Dose Leakage Zone No. Diam. ASME / AWS / F No. / Process Plant Location Rates Monitoring Pressure Temp. Pressure Temp. No. (inches) (mR/hr) (psi) (Deg. F) (psi) (Deg. F) SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg. -83 74-105 14 SFA-5.4 / ER316 / F5 / SMAW Shutdown Cooling 0.3 -9.0 Yes 650 400 370 350 HTX'A' Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -90 85-9 24 SFA-5.4 / ER316 / F5 / SMAW East Mechanical 0.2 -22.0 Yes 100 350 100 120 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -90 85-11 24 SFA-5.4 / ER316 / F5 / SMAW East Mechanical 0.2 -22.0 Yes 100 350 100 120 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -91 76-7 12 SFA-5.4 / ER316 / F5 / SMAW West Mechanical 0.2 -11.0 Yes 650 550 370 350 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -91 77-7 12 SFA-5.4 / ER316 / F5 / SMAW West Mechanical 0.2 -11.0 Yes 650 550 370 350 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -91 77-14 12 SFA-5.4 / ER316 / F5 / SMAW West Mechanical 0.2 -11.0 Yes 650 550 370 350 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -91 77-16 12 SFA-5.4 / ER316 / F5 / SMAW West Mechanical 0.2 -11.0 Yes 2485 650 370 350 Penetration Room SFA-5.9 / ER316 / F6 / GTAW Containment

-98 78-47 12 SFA-5.4 / ER316 / F5 / SMAW 103' el. Outside <0.2 Yes 2485 650 370 350 Bio-Shield SFA-5.9 / ER316 / F6 / GTAW Containment

-90' 101 71-123 16 el. Outside Bio-0.5 -4.0 Yes 485 400 370 350 SFA-5.4 / ER316 / F5 / SMAW Shield Auxiliary Bldg -104 85-46 20 SFA-5.9 / ER316 / F6 / GTAW Low Pressure 0.4 -33.0 Yes 100 350 100 120 SFA-5.4 / ER316 / F5 / SMAW Safety Injection Pump Room 42' el. Auxiliary Bldg -104 85-47 20 SFA-5.9 / ER316 / F6 / GTAW Low Pressure 0.4 -33.0 Yes 100 350 100 120 SFA-5.4 / ER316 / F5 / SMAW Safety Injection Pump Room 42' el. 5 Enclosure Response to Request for Additional Information

-Relief Request 63 -Unit 3 Impractical Examinations for the Third 10-Year Inservice Inspection Interval Table 3B -SUQQlemental Information for Category C-F-1, Item CS.21 Welds Design Conditions Operating Conditions

!SI Zone Weld Pipe Filler Material Specifications Typical Area Dose Leakage No. No. Diam. ASME / AWS / F No./ Process Plant Location Rates (mR/hr) Monitoring Pressure Temp. Pressure Temp. (inches) (psi) (Deg. F) (psi) (Deg. F) SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -West 110 110-17 2 Mechanical 0.2 -11.0 Yes 2050 350 1822 350 SFA-5.4 / ER316 / F5 / SMAW Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -West 110 110-52 2 Mechanical 0.2 -11.0 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -West 111 111-34 4 Mechanical 0.2 -11.0 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Penetration Room SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -East 113 113-28 2 Mechanical 0.2 -22 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Penetration Room SFA-5.9 / ER316 / F6 / GTAW Containment

-90' 118 118-46 3 el. Outside Bio-0.5 -4.0 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Shield SFA-5.9 / ER316 / F6 / GTAW Containment

-90' 118 118-49 3 el. Outside Bio-0.5 -4.0 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Shield SFA-5.9 / ER316 / F6 / GTAW Containment

-90' 119 119-52 3 el. Outside Bio-0.5 -4.0 Yes 2485 650 1822 350 SFA-5.4 / ER316 / F5 / SMAW Shield SFA-5.9 / ER316 / F6 / GTAW Auxiliary Bldg -CH 119 119-53 2 SFA-5.4 / ER316 / F5 / SMAW Pump Valve Gallery 0.2 -2.0 Yes 2485 650 1822 350 100' el. 6