ML18005A651

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Safety Evaluation Supporting First 10-yr Inservice Insp Program Plan
ML18005A651
Person / Time
Site: Harris 
Issue date: 09/30/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18005A650 List:
References
NUDOCS 8810170429
Download: ML18005A651 (18)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN CAROLItIA POWER 8

LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400

1.0 INTRODUCTION

Technical Specification 4.0.5 for the Shearon Harris ttuclear Power Plant, Unit 1, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1,

2 and 3 components shall be applicable as follows:

Inservice Inspection of ASME Code Class 1,

2 and 3 components shall be performed in accordance with Section XI of the ASME Code and applicable

Addenda, as required by 10 CFR 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).

Pursuant to 10 CFR 50.55a(g)(4),

ASME Code Class 1,

2 and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"

to the extent practical within the limitations of

design, geometry, and IIIaterials of construction of the components.

The regulations require that inservice examination of components and systems pressure tests conducted during the first ten-year interval shall comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the date of issuance of the operating license, subject to the limitations and modifications listed therein.

The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.

Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that confor-mance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement.

After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),

the Commission may grant relief and may impose alternative requirements as it determines are authorized by law and will not endanger life or property or the common defense and security, and are otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the. requirements were imposed.

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Vf' 2.0 On January 28, 1988, Carolina Power 5 Light Company (the licensee) submitted the First Ten-Year Interval Inservice Inspection (ISI) Program Plan for the Shearon Harris Nuclear Power Plant, Unit 1,'o meet the requirements of the 1983 Edition, Summer 1983 Addenda,Section XI, of the ASME Boiler and Pressure Vessel

Code, except that the extent of examina-tion of Class 2 piping welds was determined by the 1974 Edition, Summer 1975 Addenda.

The staff, with technical assistance from its Contractor, Idaho National Engineering Laboratory

( INEL), has evaluated the First Ten-Year Interval Inser vice Inspection Program Plan, additional informa-tion related to the plan, and the requests for relief from certain ASME Code requirements determined to be impractical to perform at Shearon Harris, Unit 1, during the first inspection interval.

EVALUATION 3.0 The ISI Program Plan has been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with examination and test requirements of Section XI, (c) acceptability of the examination

sample, (d) compliance with comnitments made by the licensee prior to plant operation, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequacy of information in support of requests for relief from impractical Section XI Code requirements.
The, staff has determined that the licensee's ISI Program Plan reflects com-pliance with the requirements listed above.

The information provided by the licensee in support of requests for relief from impractical require-ments has been evaluated and the bases for granting relief from those requirements are documented in the attached INEL Technical Evaluation Report (TER).

Table 1 of this safety evaluation provides the NRC staff's summary of reliefs requested and results of the staff's review.

We concur with the findings and recommendations contained in the TER with the exception of pressurizer welds II-PZR-01CSW-03 and II-PZR-01LSW-06 listed in Relief Request No. Rl-004.

These welds are not scheduled to be examined during this inspection interval and, therefore, should not be a

part of the examination program.

This is reflected in the staff's safety evaluation by omission of these welds from Table 1.

CONCLUSION Pursuant to 10 CFR 50.55a(g)(6)(i),

the staff has evaluated the licensee's supporting information and determined that the Section XI Code require-ments cited by the licensee are impractical to perform at Shearon Harris, Unit 1.

Imposition of the requirements could result in the redesign, replacement, or addition of a significant number of components and systems at the facility.

The staff has granted relief from those requirements that are impractical to perform and has imposed alternative requirements for Relief Request RI-005(A) and RI-005(B).

The granting of the reliefs and imposition of the alternative requirements are authorized by law and will not endanger life or property or the common defense and security and is in the public interest giving due consideration to the burden on the licensee that could result if the requirements were imposed at Shearon

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5 Harris, Unit 1.

The staff, therefore, concludes that the Shearon Harris, Unit 1 First Ten-Year ISI Program Plan with the additional information provided and the specific written reliefs granted constitutes an accept-able basis for compliance with 10 CFR 50.55a(g) and Technical Specifica-tion 4.0.5.

Principal Contributors:

G. Johnson J. Schiffgens B. Buckley Dated:

September 30, 1988

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SUMMARY

OF RELIEF RE UESTS

81. 11 Exam.

Item IIo.

~Cate or I

8-A System or

~Com oncet Reactor Pressure Vessel Volume or Area to be Examined Circumferential Shel 1 Meld II-RV-001CWS-RV-02 Required Hcthod Volumetric Licensee ProPosed Alternative Volumetric (UT)

Examination to Extent Practical p

Rel ief Request Status panted 81.12 81.21 81.22 81.40

83. 90 8-A 8-A 8-A 8-A B-D Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Longitudinal Shell Mclds:

II-RV-001LSW-RV-05 I I-RV-001LSM-RV-06 Circumferential Mead Welds:

II-RV-001CHW-RV-17 II-RV-OOSTHW-RV-04 Hcridional Mead Welds:

II-RV-001HHM-RV-ll I I-RV-001HHW-RV-12 II-RV-001HHM-RV-13 II-RV-001HHM-RV-14 I I-RV-001HHM-RV-15 II-RV-001HIHM-RV-16 Head-To-Flange Meld Nozzle-To-Vessel Wclds:

II-RV-001RVNOZAI-N-01 II-RV-001RVNOZAO-N-GG I I-RV-001RVNOZBO-N-02 II-RV-001RVNOZCO-N-04 Volumetric Volumetric Volumetric Vo1 umetr ic and Surface Volumetric Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Surface and Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Granted Granted Granted Granted Granted 82.11 8-8 Pressurizer Shel 1 -TO-Head hei ds:

II-PZR-01STHW-01 II-PZR-01STHM-04 Volumetric Volumetric (UT)

Examination to Extent Practical Granted

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TABLE 1 (cont'd)

SUMMARY

OF RELIEF RE UESTS Exam.

Item IIo.

~Cate or B3.110 B-D System or

~COlll OfiaAt I

Pressurizer Volume or Area to be Examined Nozzle-To-Vessel Wel ds:

I I-PZR-01NTHM-08 II-PZR-01NTHM-09 I I-PZR-01NTHM-10 II-PZR-01NTHW-11 I I-PZR-01NTHM-12 II-PZR-01NTHW-13 Required Method Volume tri c Licensee Relief Proposed Request Alternative.'tatus I

Volumetric (UT)

Granted Examination to t

Extent Practical 85.40 B-F Pressurizer Nozzle-to Safe End Wel ds:

II-PZR-01NSEW-15 II-PZR-01NSEW-16 II-PZR-01NSEM-17 II-PZR-01NSEM-18 II-PZR-01NSEW-19 II-PZR-01NSWE-20 Volumetric and Surface 100$ Surface Examination and Volumetric (UT) to Extent Practical Granted 88.20 B-H Pressurizer Integrally Welded Attach-ments:

I I-PZR-01SBW-A1A II-PZR-01SBM-A1B II-PZR-01SBW-A2A II-PZR-01SBM-A2B II-PZR-01SBW-A3A II-PZR-01SBW-A3B I1-PZR-01SBW-A4A II-PZR-01SBW-A4B Surface or Volumetric Surface to extent Granted Practical and Visual of I" Base Metal B2.40 8-B Steam Generator Tubesheet-To-Head Welds:

II-SG-001SGA-TSTHW-06 II-SG-001SGB-TSTHW-06 II-SG-001SGC-TSTHM-P6 Volumetric Volumetric (UT)

Examination to Extent Practical Granted

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TABLE 1 (cont'd)

SUMMARY

OF RELIEF RE UESTS Exam.,

Item No.

~Cate or B3. 130 B-D System or

~Com ooeot.

I Stcam Generator Volume or Area to be Examined Nozzle-To-Vessel Welds:

I I-SG-001SGA-CLNTVW-12 II-SG-001SGA-HLNTVW-07 I I-SG-001SGB-CLNTVM-12 II-SG-001SGB-CLNTVM-07 I I-SG-001SGC-CLNTVW-12 II-SG-001SGC-CLNTVW-07 Required Method Volumetric Licensee Proposed Alternative.'

Volumetric (UT) to Extent Practical Relief Request

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Granted B9.31 B-J Piping Wclds:

II-FMR-01RC-10-17-SM-L2 II-FMR-02RC-10-18-SM-K8 II-FMR-03RC-10-19-SM-N2 II-FMR-03RC-10-19-SM-N3 Surface and Volumetric 100K Surface Examination and Volumetric to Extent Practical Granted B9.11 B-J Piping Melds:

II-FMR-01RC-10-17-FW-2 II-FMR-02RC-10-18-FM-3 II-FMR-02RC-10-18-FM-8 II-FMR"03RC-10" 19-FW-2 II-RC-009RC-FW-1 II-RC-023RC-FW-327 II-RC-023RC-SW-B4 II-RC-023RC-SM-B5 II-RC-023RC-SM-C13 II-RC-023RC-SW-C9 II-RC-024RC-FW-318 II-RC-025RC-FW-331 II-RC-025RC-SW-A3 II-RC-027RC-SM-A11 II-RH-009RC-FW-292 II-RH-009RC-SW-A4 II-RH-009RC-SM-A5 II-RH-009RC-SM-A6 Surface arid IOOX Surface Volumetric and Volumetric (UT) to Extent Practical Granted

TABLE 1 (cont'd)

S NM IIF

~~IIUHT Exam.

Itms No.

~Cat o or B9.11 B-J

,System or

~Com onont Piping Volume or Area to be Examined I

Melds:

II-SI-017RC-FW-297 II-SI-021RC-FW-300 11-SI-022RC-FW-301 II-SI-023RC-FW-299 II-SI-024RC-FM-293 II-SI-024S I-FW-588 II-SI-025SI-FM-536 II-S I-027RC-F W-298 II-SI-027SI-FM-542 II-SI-028RC-FW-296 Required Method Surface arid Volumetric Licensee Proposed Alternative 100$ Surface and Volumetric (UT) to Extent Practical Relief Request Status I

Gran)ed B12.10 B-L-1 Reactor Coolant Pumps Casing Molds Volumetric None Granted Provided Exam-ination is Performed if Pump is Disassembled or Surface Examination Performed on Casing Weld 812.20 B12. 50 C1.20 B-L-2 B-N-2 C-A Reactor Coolant Pumps Valve Body Boron Injection Tank Internal Surfaces Internal Surface Circumferential Head Welds:

II-BIT-01STHW-01 I I-BIT-01STHM-02 Visual (VT-3)

Visual (VT-3)

Volumetric None None Volumetric (UT)

Examination to Extent Practical Granted Provided Exa ination is Performed s

Pump is Disassembled Granted Provided Exam-ination is Performed if Valve is Disassembled Granted

TABLE 1 (cont'd)

SUMMARY

OF RELIEF RE UESTS Exam.

Item No.

~Cate or C1.20 C-A System or

~Com oncet.

1 Excess Letdown Heat Exchanger Volume or Area to be Examined Circumferential Head Weld:

II-EL-001STHW-02 Required Method Volumetric Licensee Proposed Alternati vc

.'olumetric(UT)

Examination to Extent Practical Relief Request

~Satus p

Granted C1.20 C1.20 C1.10 C1.10 C1.10 C-A C-A C-A C-A C-A Steam Generator Regenerative Heat Exchanger Residual Heat Removal Heat Exchanger Stcam Generators Residual Heat Removal Heat Exchanger Circumferential Head Meld:

II"SG-001SGB"STHW-02 Circumferential Head Wclds:

I I-RHX-01CHTSW-01 II-RHX-01CHTSW-02 II-RHX-01CHTSW-03 II-RHX-01CHTSW-04 II-RHX-01CHTSW-05 II-RHX-01CHTSW-06 Circumferential Head Weld:

II-RHR-01RHRA-STHM-01 Circumferential Head Melds:

II-SG-001SGA-CSW-03 II-SG-001SGC-CSW-10 Circumferential Shell Meld:

II-RHR-01RHRA-CSW-02 Volumetric Volumetr ic Volumetric Volumetric Volumetric Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Volumetric (UT)

Examination to Extent Practical Granted Granted Granted Granted Granted

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TABLE 1 (cont'd)

SUMMARY

OF RELIEF RE UESTS Exam.

Item IIo.

~Cate or C2. 21 C-8 System or

~Com onent I

Boron Injection Tank Volume or Area to be Examined Nozzle-To-Shel 1 Wclds:

II-B17-01NTHM-03 II-B17-01NTHW-04 Licensee Required Proposed Method Alternative.'

Surface and 'olumetric and Volumetric Surface to Extent Practical Rel ief Request

~Satus p

Granted C2.21 C-B Stcam Generators Nozzle-To-Shel 1 -Melds:

I I-SG-001SGA-AFWNTSM-11 II-SG-001SGB-FWNTSM-05 II-SG-001SGC-MSNTHM-01 Surface and Volumetric Volumetric and Surface to Extent Practical Granted C1.30 C1.30 C2.22 C-A C-A C-B Steam Generator Regenerative Heat Exchangers Steam Generators Tubeshcet-To-Shell Weld:

II-SG-001SGC-TSTSW-09 Tubesheet-To-Shell Wclds:

II-RHX-01TSTSM-07 II-RHX-01TSTSW-08 II-RHX-01TSTSM-09 II-RHX-01TSTSW-10 II-RHX-01TSTSW-11 II-RHX-01TSTSW-12 Nozzle Inside Volumetric Radiuscd Sections:

II-SG-001-SGA-MSNIR-15 II-SG-001-SGB-MSNIR-15 II-SG-001-SGC-MSNIR-05 II-SG-001-SGC-MSNIR-15 Volumetric Volumetric to Extent Practical Volumetric Volumetric to Extent Practical Volumctri c Volumctri c to Extent Practical Granted Granted Granted C3.10 C5.21 C-C C-F Rcgcnerative Heat Exchanger Piping Integral ly Wcl dud'ttachment:

II-RHX-01HSTSW-Al Circumferenti al Melds:

II-AF-005AF-FW-249 II-AF-005AF-FW-251 Surface Surface and Volumetric Surface Examination to Extent Practical Surface and Volumetric to Extent Practical Granted Granted

TABLE 1 (cont'd)

SUMMRY OF RELIEF RE UESTS Exam.,

Itme No.

~Cate or C5.21 C-F System or

~Com anent Piping Volume or Area to be Examined Circumferential Welds:

I-AF-006AF-FW-246 I I-AF-007AF-FM-239 II-AF-007AF-FW-241 II-CS-007SI-FW-25 II-CS-022CS-FW-561 II-CS-022CS-FW-562 II-CS-092CS-FW-3029 II-CT-001CT-FM-8 I I-CT-001CT-FM-9 II-CT-002CT-FM-19 II-CT-002CT-FM-20 II-CT-014CT-FW-175 II-CT-016CT-FM-145 II-FW-00)FW-SW-D4 II-FW-00)FW-32-4-SW-1 II-FW-00)FW-32-5-SM-5 II-FW-002AF-FW-259 II-FW-003AF-FW-266 I1-FW-004AF-FW-273 II-FW-004AF-FW-276 II-HS-00)HS-SW-A)l II-NS-001HS-SW-Bll II-HS-00)HS-SM-C)1 II-HS-002NS-FW-566 II-HS-002NS-FW-567 II-NS-002HS-FM-568 Required Method Surface and Volumetric Licensee Proposed Alternative' Surface and p

Volumetric to Extent Practical Relief Request tatus Granted C5.21 C-F Piping Circumferential Welds:

II-HS-002HS-FW-690 II-HS-002HS-FW-691 II-NS-002NS-FM-692

'I-NS-007NS-FW.-678 II-RH-001RH-FW-8 II-RH-002RH-FM-21 I I-RH-002S I-FW-2)

Surface and Volumetric Surface and Volumetric to Extent Practical Granted

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TABLE 1 (cont'd).

SUGARY GF RELIEF RE UESTS Exam.

Item IIo.

~Cate or C5.21 C-F System or

~Com anent Pip>ng Volume or Area to be Examined Circumferential We 1 ds:

II-RH-009RH-FW-14 II-RH-G09RH-FM-15 II-RH-010RH-FW-193 II-RH-010RH-FW-2 II-SI-008SI-FW-450 II-SI-016SI-FM-36 II-SI-019SI-FW-277 II-SI-021SI-FW-557 II-SI-024SI-213-FW-573 II-SI-025SI-FW-578 II-SI-025SI-FM-580 II-SI-025SI-FM-583 II-SI-026SI-FM-582 II-SI-026SI-FM-592 II-SI-028SI-FM-610 II-SI-029SI-SM-C14 Required Method Surface and Volumetric Licensee Proposed-Alternative.'

Surface and Volumetric to Extent Practical Relief Request atus p

Granted C3.20 C3-30 C-C C-C Piping Pumps Integrally Wcldcd Attachments:

II-CS-021CS-H-00111 4)

I I-FMR-01FM-H-0212I 8)

Integral ly Wel acd Attachmerrzs:

II-CSIP-ICSIP-A-MA1 II-CS IP-ICS IP-A-WA2 II-CSIP-ICSIP-A-WA3 II-CSIP-ICSIP-A-MA4 Surface Surface Surface Exami-nation to Extent Practical Surface and Volumetric to Extent Practical Granted Granted C5.21 C-F Piping Circumferential Welds:

II-FW-002AF-FM-257 11-F Wi-002AF-FW-258 II-FW-003AF-FW-269 II-FM-004AF-FM-277 Il-AF-006AF-FM-245 Surface and Surface and Volumetric Volumetric Examination to Extent Practical Granted

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