ML25155B861

ASME Section XI Inservice Inspection Program Relief Requests for Limited Coverage Examinations Performed in the Third Period of the Fifth 10-Year Inspection Interval

ML25155B861
Person / Time
Site:	Surry
Issue date:	06/04/2025
From:	James Holloway Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
25-152
Download: ML25155B861 (1)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 June 4, 2025 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 ASME SECTION XI INSERVICE INSPECTION PROGRAM Serial No.

NRA/DPJ Docket No.

License No.25-152 RO 50-280 DPR-32 RELIEF REQUESTS FOR LIMITED COVERAGE EXAMINATIONS PERFORMED IN THE THIRD PERIOD OF THE FIFTH 10-YEAR INSPECTION INTERVAL The Surry Power Station (SPS) Unit 1 fifth 10-year interval for the inservice inspection program began on December 14, 2013 and ended June 13, 2024. During this interval, certain components received examination coverage that did not meet the requirements of Section XI of the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code. Two relief requests (S1-I5-LMT-C01 and S1I5-LMT-P01) for this interval were previously submitted and were approved by the NRC by letter dated February 28, 2019 (ADAMS Accession No. ML18331A060). Additional components that received less than the required examination coverage during this interval are identified in Attachments 1 through 3. Accordingly, Virginia Electric and Power Company (Dominion Energy Virginia) requests relief for these components pursuant to 10 CFR 50.55a(g)(5)(iii), on the basis that the required examination coverage was impractical due to physical obstructions and limitations imposed by design, geometry and materials of construction.

Attachments 1 through 3 contain the specific relief requests and the individual basis for each request. These relief requests have been reviewed and approved by the station's Facility Safety Review Committee.

If you have any questions or require additional information, please contact Daniel Johnson at (804) 273-2381.

Sin(}4h/~ Pr7 James E. Holloway Vice President - Nuclear Engineering and Fleet Support Virginia Electric and Power Company (Dominion Energy Virginia)

Serial No.25-152 Docket No. 50-280 Page 2 of 2 Attachments:

1. Relief Request S1-I5-LMT-C02 - Limited Examination Coverage of the Reactor Vessel Circumferential Shell Welds

2. Relief Request S1-I5-LMT-C03 - Limited Examination Coverage of the Pressurizer Shell-to-Head Circumferential and Longitudinal Shell Welds

3. Relief Request S1-I5-LMT-C04 - Limited Examination Coverage of the Pressurizer Nozzle Inner Radius Section Commitments made in this letter: None cc:

U.S. Nuclear Regulatory Commission - Region II Attn: Regional Administrator Marquis One Tower 245 Peachtree Center Avenue, NE., Suite 1200 Atlanta, Georgia 30303-1257 L. John Klos (w/o enclosure)

NRC Senior Project Manager - (SPS Units 1 and 2)

U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E-3 11555 Rockville Pike Rockville, Maryland 20852-2738 NRC Senior Resident Inspector Surry Power Station

Serial No.25-152 Docket No. 50-280 ATTACHMENT 1 RELIEF REQUEST S1-I5-LMT-C02 LIMITED EXAMINATION COVERAGE OF THE REACTOR VESSEL CIRCUMFERENTIAL SHELL WELDS VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 1

Serial No.25-152 Docket No. 50-280, Page 1 of 4 Relief Request S1-I5-LMT-C02 Limited Examination Coverage of the Reactor Vessel Circumferential Shell Welds Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)

Impractical ISI Code Requirements

1. ASME Code Components Affected The Code components affected are the Class 1 Reactor Vessel Circumferential and Longitudinal Shell Welds.

Weld No.:

1-04 Drawing:

11448-WMKS-RC-R-1.1 ASME Class:

1 ASME Category:

B-A ASME Item:

B1.11

==

Description:==

Reactor Vessel Lower Shell to Bottom Shell Circumferential Weld

2. Applicable Code Edition and Addenda

2004 Edition of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI

3. Applicable Code Requirement

The 2004 Edition of ASME Section XI Table IWB-2500-1, Examination category B-A, Item B1.11 requires volumetric examination of essentially 100%

of the weld length of all welds. The examination volume is shown in Figure IWB-2500-1. The volume to be examined includes the weld plus 1/2t (t=thickness) of base material on each side of the weld.

Table IWB-2500-1, Examination category B-A, Item B1.21 requires volumetric examination of essentially 100% of the weld length of the accessible length of all welds. The examination volume is shown in Figure IWB-2500-3.

The volume to be examined includes the weld plus 1/2t (t=thickness) of base material on each side of the weld.

Serial No.25-152 Docket No. 50-280, Page 2 of 4

4. Impracticality of Compliance

There are four radial core support lugs located at 0°, 90°, 180°, and 270° positions of the vessel inside surface just above the weld which restrict complete coverage of the require examination volume. The ultrasonic examination of this weld was performed by scanning the accessible surfaces between and below the support lugs.

Figure 1-1 shows the general configuration of the reactor vessel and location of weld 1-04.

5. Burden Caused by Compliance

Significant modifications to the design of the RV (Reactor Vessel) would have to be implemented to obtain essentially 100% volumetric coverage.

Modification of the reactor vessel is considered impractical and would cause unnecessary radiation exposure to plant personnel and potential detrimental impact to plant equipment.

6. Proposed Alternative and Basis for Use

Weld 1-04 was ultrasonically examined using automated phased array ultrasonic technique and procedure. Scanning was performed to the maximum extent possible for the weld configurations. In the area where scanning was limited, "single-sided" scan parameters (excluding the inner 15%) was used to improve coverage when they could provide improved coverage. The examination procedure has been qualified for single side access to address these configuration limitations.

Weld 1-04 contains three acceptable indications. These flaws are classified as subsurface. These indications were evaluated as acceptable per IWB-3510-1.

The indications are characteristic of slag inclusions from the welding process during fabrication. Measured alt% was 1.2, 1.4, and 1.7 for the indications compared to an allowable alt% of 2.2, where alt% is a ratio of the crack depth and wall thickness.

System leakage tests of the bottom of the RV including the bottom mounted instrumentation penetration nozzles is conducted at the ambient pressure and temperature during the refueling outage, as authorized by the NRC in ADAMS Accession No. ML14192B388 (dated July 17, 2014). The VT-2 visual-examination of both the insulated and non-insulated area of the bottom of the RV including the bottom mounted instrumentation penetration nozzles in accordance with IWA-5240 would detect pressure retaining boundary leakage that would originate from a flaw.

Serial No.25-152 Docket No. 50-280, Page 3 of 4 Further, Surry Power Station (SPS) has Technical Specifications (TS) requirements for monitoring leakage from the reactor coolant system.

The total aggregate examination coverage value obtained for weld 1-04 was 82%. The coverage for this weld increased this interval from 73.4% achieved in the previous performance of this examination. The NRC staff determined that imposing the code required coverage requirements was impractical in the third ISI Interval for SPS and concluded that the achieved limited coverage provided reasonable assurance of the structural integrity of the component-reference ADAMS Accession No. ML060540284 (dated March 28, 2006).

Dominion Energy Virginia concludes that the scanning percentage coverage obtained (82%), the VT-2 examination of the RV conducted every refueling outage to detect evidence of leakage, and the TS surveillance requirements to RCS leakage monitoring provide reasonable assurance of structural integrity for the Reactor Vessel Lower Shell to Bottom Shell Circumferential Weld-1-04.

7. Duration of Proposed Alternative

This proposed alternative is requested to meet requirements for the fifth ten-year inspection interval for SPS Unit 1, which began December 14, 2013, and ended on June 13, 2024.

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Serial No.25-152 Docket No. 50-280 ATTACHMENT 2 RELIEF REQUEST S1-I5-LMT-C03 LIMITED EXAMINATION COVERAGE OF THE PRESSURIZER SHELL-TO-HEAD CIRCUMFERENTIAL AND LONGITUDINAL SHELL WELDS VIRGINIA ELECTRIC POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 1

Serial No.25-152 Docket No. 50-280, Page 1 of 10 Relief Request S1-I5-LMT-C03 Limited Examination Coverage of the Pressurizer Shell-to-Head Circumferential and Longitudinal Shell Welds Proposed Relief In Accordance with 10 CFR 50.55a(g)(5)(iii)

-Impractical ISI Code Requirements-

1. ASME Code Components Affected:

The Code components affected are the Class 1 Pressurizer Shell-to-Head Circumferential and Longitudinal Welds.

Weld No.:

1-07 Drawing:

11448-WMKS-RC-E-2 ASME Class:

1 ASME Category:

B-B ASME Item:

B2.11

==

Description:==

Pressurizer Shell-to-Head Circumferential Weld Weld No.:

1-15 Drawing:

11448-WMKS-RC-E-2 ASME Class:

1 ASME Category:

B-B ASME Item:

B2.12

==

Description:==

Pressurizer Shell-to-Head Longitudinal Weld

2. Applicable Code Edition and Addenda

2004 Edition of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI

Serial No.25-152 Docket No. 50-280, Page 2 of 10

3. Applicable Code Requirement

The 2004 Edition of ASME Section XI Table IWB-2500-1, Examination category B-B, Item B2.11 requires volumetric examination of essentially 100% of the weld length of both circumferential welds. The examination volume is shown in Figure IWB-2500-1.

Table IWB-2500-1 category B-B, item B2.12, of the 2004 Edition requires volumetric examination of one foot on the longitudinal weld that intersects the selected circumferential shell to head weld.

4. Impracticality of Compliance

The pressurizer is covered with an insulation support ring as shown in Figure 2-1. The insulation support ring is 6 inches wide where examination interference is encountered for weld 1-07. As seen in Figure 2-1, this insulation support ring and a power operated relief valve (PORV) support prevent complete volumetric coverage of both the upper circumferential head weld 1-07 and the intersecting longitudinal weld 1-15. Figures 2-2 and 2-3 contain the examination reports detailing the examination coverage obtained for welds 1-07 and 1-15 respectively.

5. Burden Caused by Compliance

Total removal of the support ring at the mechanical connections is considered impractical due to the extreme high dose rates in the pressurizer area. Total radiation dose to perform removal of the interfering support and to perform the examination is estimated to be 15.13 rem. This includes expended dose necessary for various crafts:

mechanical maintenance, insulators, rigging crews and the Non-destructive Examination (NDE) workers. Partial removal of the support ring could allow some increased coverage; however, the actual increase would be very small in relation to the entire weld length. This is not a viable effort when considering consequential disturbance of interconnected cross supports and the welded connections to safety and power operation relief valve supports. Any removal of the mechanical connections or forced spreading apart of components would create a risk of misalignment and possibly warp the structure. Furthermore, civil engineering proposed that cutting the support could be necessary for removal, which would destroy the support ring.

Serial No.25-152 Docket No. 50-280, Page 3 of 10

6. Proposed Alternative and Basis for Use

Examination of pressurizer shell welds 1-07 and 1-15 obtained 63.9% and 54.5% of the required examination volume, respectively, with no relevant indications. The coverage for these welds increased above the 46% and 31% achieved respectively for welds 1-07 and 1-15 in the previous performance of this examination during the fourth inservice inspection interval. For the fourth inservice inspection interval, the NRC staff determined that imposing the code required coverage requirements was impractical because access to the pressurizer circumferential welds was severely limited due to the interference caused by the insulation support ring and PORV support disassembly of those structures would impose unwarranted dose. Relief was granted by the staff for the fourth interval and concluded that the limited coverage achieved provided reasonable assurance of the structural integrity of the component-reference ADAMS Accession No. ML16208A009 (dated August 24, 2016).

No additional ultrasonic examination techniques would provide meaningful additional data on this cladded material for the examination volume not attained. The pressurizer receives a visual (VT-2) examination every refueling outage as required by Section XI, Table IWB-2500-1, Category B-P for Class 1 components. Any effort to achieve greater coverage would be impractical, creating risk for component damage or destruction and excessive personnel dose exposure.

Surry Power Station (SPS) also has Technical Specifications (TS) requirements for monitoring leakage from the reactor coolant system (RCS).

Dominion Energy Virginia concludes that the scanning percentage coverage obtained (63.9% and 54.5% respectively for welds 1-07 and 1-15), the VT-2 examination of the pressurizer conducted every refueling outage to detect evidence of leakage, and the TS surveillance requirements for RCS leakage monitoring provide reasonable assurance of structural integrity for the Pressurizer Shell-to-Head Circumferential and Longitudinal Shell Welds.

7. Duration of Proposed Alternative

This proposed alternative is requested to meet requirements for the fifth ten-year inspection interval for SPS Unit 1, which began December 14, 2013 and ended on June 13, 2024.

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Serial No.25-152 Docket No. 50-280 ATTACHMENT 3 RELIEF REQUEST S1-I5-LMT-C04 LIMITED EXAMINATION COVERAGE OF THE PRESSURIZER NOZZLE INNER RADIUS SECTION VIRGINIA ELECTRIC POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNIT 1

Serial No.25-152 Docket No. 50-280, Page 1 of 6 Relief Request S1-I5-LMT-C04 Limited Examination Coverage of the Pressurizer Nozzle Inner Radius Section Proposed Relief in Accordance with 10 CFR 50.55a(g)(5)(iii)

Impractical ISI Code Requirements

1. ASME Code Components Affected The Code components affected is the Class 1 pressurizer full penetration welded nozzle.

Weld No.:

20NIR Drawing:

11448-WMKS-RC-E-2 ASME Class:

1 ASME Category:

8-D ASME Item:

83.120

==

Description:==

Pressurizer Nozzle Inner Radius Section

2. Applicable Code Edition and Addenda

2004 Edition of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI

3. Applicable Code Requirement

The 2004 Edition of ASME Section XI does not require examination of Class 1 Nozzle Inner Radius (NIR) Sections.

Title 10, Code of Federal Regulations Part 50.55a(b)(2)(xxi) conditions the requirements of ASME Section XI Table IW8-2500-1, Examination Category 8-D. The condition mandates that the 1998 Edition of Section XI be used which requires examination of the pressurizer nozzle inner radius-Item No. 83.120. Either an ultrasonic or enhanced visual examination from the ID (inner diameter) shall be performed.

Serial No.25-152 Docket No. 50-280, Page 2 of 6

4. Impracticality of Compliance

The pressurizer is covered with an insulation support ring (Figure 3-1). As can be seen, the support ring interferes with completion of a full volumetric examination around the circumference of the 20NIR, nozzle leading to a pressurizer safety valve. The examination was further limited by a surface indentation which did not allow for adequate probe contact. Figure 3-2 contains the examination report detailing the examination coverage obtained for weld 20NIR.

5. Burden Caused by Compliance

Total removal of the support ring at the mechanical connections is considered impractical due to the extremely high dose rates in the pressurizer area. Furthermore, this is not a viable effort when considering consequential disturbance of interconnected cross supports and the welded connections to safety and power operation relief valve supports. Any removal of the mechanical connections or forced spreading apart of components would create a risk of misalignment and possibly warp the structure. Civil engineering proposed that cutting the support could be necessary for removal, which would destroy the support ring.

6. Proposed Alternative and Basis for Use

Component 20NIR was ultrasonically examined using an NOE procedure that incorporates Electric Power Research Institute (EPRI) modeling report IR-2012-485 specific to the Surry Power Station (SPS) Unit 1 pressurizer safety/relief nozzles. This modeling report details the required ultrasonic scan parameters which should be applied to achieve full coverage of the examination volume. Modeling report IR-2012-485 requires a combination of ultrasonic scanning both from the nozzle blend region and the pressurizer vessel head. Different transducer angles, skews and wedge contours were used for the required scans.

The prior ultrasonic examination performed during the fourth ISI interval consisted of only scanning from the nozzle blend region; scanning was not required from the vessel head. Most of the documented limitations (86.65%) occurred in the region on the vessel head which was previously not scanned.

No additional ultrasonic examination techniques would provide meaningful additional data on this cladded material for the examination volume not attained. The pressurizer receives a visual (VT-2) examination every refueling outage as required by Section XI, Table IWB-2500-1, Category 8-P for Class 1 components performed at normal operating pressure and temperature. Any effort to achieve greater coverage would be impractical,

Serial No.25-152 Docket No. 50-280, Page 3 of 6 creating risk for component damage or destruction and excessive personnel dose exposure.

The 20NIR nozzle inner radius section is located at the top of the pressurizer. During plant operations, this location is subjected to a relatively constant temperature with the primary temperature fluctuations being associated with reactor heat up and cooldown. Those fluctuations are controlled for the thermal effects on components. Further, the nozzle inner radius sections are not welds but cast material components. There have been no known through wall flaws in class 1 nozzle inner radius section components. Similar SPS Unit 1 pressurizer nozzle inner radius section 19NIR was examined on October 26, 2016 during the fifth interval; greater than 90% coverage was obtained with no indications.

SPS also has Technical Specifications (TS) requirements for monitoring leakage from the reactor coolant system (RCS).

Dominion Energy Virginia concludes that the scanning percentage coverage obtained (86.65% for weld 20NIR), the VT-2 examination of the pressurizer conducted every refueling outage to detect evidence of leakage, and the TS surveillance requirements for RCS leakage monitoring provide reasonable assurance of structural integrity.

7. Duration of Proposed Alternative

This proposed alternative is requested to meet requirements for the fifth ten-year inspection interval for SPS Unit 1, which began December 14, 2013, and ended on June 13, 2024.

Serial No.25-152 Docket No. 50-280, Page 4 of 6 Figure 3-1 Pressurizer Nozzle to Pipe Safety/Relief Valve Support Insulation Support Frame Insulation Support Pressurizer

Serial No.25-152 Docket No. 50-280, Page 5 of 6 Figure 3-2

,Dominion UT Inner Radius Examination Sltol\\Jnlt Sur,y /

1 Procedure:

ER-M,NDE4/T-705 Ovtoge No.:

S1R28 Summaly No.;

S1.83.1 20.00G Proced._..Rov,:

1 Rapoll No.:

UT-18-035 w__,.,

ISi Wort< Order No.:

S81W97043/NDE.R1S-002 Page:

1 of 2

COde:

ASME XI 2004 C.Ultem:

8-0/83.120 Lt>cadon:

PZR47 llra,mg No.a 11<148-WMKS,RC.E,2

~:

NOZZLE INNER RADIUS System ID:

RC --------------------------------------------

Ccm ponen I no:,,..... w1ou<S-Rc.E-2 / 1,RC,20NIR Sko/leng1h:

N/A ThicKneaa/Diameter.

NIA Umltations:

See attached scan limitation sketc,h.

Start Time:

2237 Finish Time:

23-09 Examination Surface:

Inside 0 Outslde@

Surf~Condition:.B~I*~*~-=-----------------------

Lo LD<:ollon:

EKtradol of OS Elbow Wo Locdon:

N~* C-,t*r Col4)18n1:

Soundufe Temp, TOOII Mfg.:

SfALED UNIT Sef1al No.:

4030900376 sunace Te"1).:

au

'F Col. RepoffNo.:

CAL-18-005, CAL-18-408, CAL-18-007 Alqe/Sltaw Scamf11gd8 In* t t1*i10* 1+21r I.. I..

lndlcation(s):

YffQ No@

Coounento:

None.

Results:

NRI,ll eo*,.zr RI 0 Pen::ent Of Covereg,e Obteined > 90%:

Examiner LOYei 111,POl Tlmm, Jtremy E.icaminer Level NJA.

NIA Other NIA leWII NIA LIT r,......, Radius ~

NIA I NIA H/A Scan~: Bo,.Q VNN1611 CW@ ccwr;a Geom 0 No Slgnattn Reviewed Prevk:>us Oete:

Yes Dale IR, SltchNo.:

17D011

Serial No.25-152 Docket No. 50-280, Page 6 of 6 Figure 3-2 (continued) i'=, Dominion

~

Energy Report No:

summnrv No: SL83. lZ01E3 Pg. 2of2 Prepared By: Jo"1myT. Timm f l-RC-20NIR Date: 4/21/2018 I

Umital,onSlttch*ndCoverageolSc,nSutfoce J?"'( ~J:. LI/ "M sj1/Jt; IPwillil'lll s~n klllJ Aw, - t.1-1 Sa. n.

r ---

AIM*l!l.ll1h.'

IIIIIV.t.a ta,i S.lfbw At8a ~ &fO,) ft_*

Scwl~l.ir,,ihllnnl

)IMINUl*ll'IJIII.

Si..tWC"llk\\'111Jliffl Am, - 1.9JSq lr.:k""\\

The sea* surfaces (bleoo *nd vessel) for l *RC*20NIR were obsmJCted bv the,tR fnsulauon 5uPP0rt Rint and al,c flmftod l>v a surfa<e Indentation which did not allow for adequate probe conrnct Tho tot~l.ar~a of sann!ns iurfaco ls 580.32 in.t.

TI,e total 1rea of l!mited sc-.onnlng Is 77.~3 ln.2.

Tutal pm:*nllls* limited* (77.43/,&0.52) x 100* U.!14" Percenrnge or san area scanned= lOO!I

• U.34ll = 86.651,

,t,.,,,_

Ol'llt~.-

7933 HSB E/4:1¢