ML18016A260

Requests Relief from Criteria of 10CFR50.55a(g)(6)(ii)(A)(2) for Augmented Exams of RPV Welds at Plant.Relief Requested from Listed ASME B&PV Code,Section Xi,Requirements for Final Insp Period of First 20 Year Insp Interval

ML18016A260
Person / Time
Site:	Harris
Issue date:	12/16/1997
From:	Robinson W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18016A262	List: ML18016A260 ML18016A263
References
HNP-97-217, NUDOCS 9712230009
Download: ML18016A260 (12)

Text

CATEGORY REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR:9712230009 DOC.DATE: 97/12/16 NOTARIZED: NO DOCKET ¹ FACIL:50-.400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH,~RAIMI~~ .- AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power &. Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Requests relief from criteria of 10CFR50.55a(g) (6) (ii) (A) (2) for augmented exams of RPV welds at plant. Relief requested from listed ASME B&PV Code,Section XI,requirements for final insp period of first 20 year insp interval.

DISTRIBUTION CODE: A047D TITLE: OR COPIES RECEIVED: LTR Submittal: Inservice/Testing/Relief from J ENCL I SIZE: ICI 4 ASME Code - GL-89-04 H.

NOTES:Application for permit renewal filed. 05000400 G

RECIPIENT COPIES RECIPIENT COPIES 0 ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 ROONEY, V 1 1 Y

INTERNAL: ACRS 1 1 AEOD/SPD/RAB 1 1 E CE E 1 1 1 NRR/DE/EMEB 1 .'1 NUDO -ABSTRACT 1 1 OGC/HDS2 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 D N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13

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Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris NUclear Plant SERIAL: HNP-97-217 DEC 16 1997 10 CFR 50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50<00/LICENSE NO. NPF-63 ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI INSERVICE INSPECTION PROGRAM RELIEF REQUEST REACTOR PRESSURE VESSEL

Dear Sir or Madam:

In accordance with 10 CFR 50.55a(a)(3), Carolina Power & Light Company (COL) hereby requests relief from the criteria of 10 CFR 50.55a(g)(6)(ii)(A)(2) for augmented examinations of reactor pressure vessel (RPV) welds at the Harris Nuclear Plant (HNP). Specifically, relief is requested from the following American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BkPV) Code,Section XI, requirements for the final inspection period of the first 10-year inspection interval:

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"Essentially 100%" (i.e., 90%) volumetric coverage for each reactor pressure vessel shell weld in accordance with Table IWB-2500-1, Examination Category B-A, Item Number B1.11 (one weld).

"Essentially 100%" (i.e., >90%) volumetric coverage for each reactor pressure vessel weld (other than shell welds) in accordance with Table IWB-2500-1, Examination Category B-A, Item Numbers B1.21 (one weld), B1.22 (one weld) and B1.30 (one weld); Examination Category B-D, Item Number B3.90 (three welds); and Examination Category B-F, Item Number B5.10 (two welds).

The required 10-year Inservice Inspection (ISI) examinations performed on the RPV welds in accordance with ASME BAPV Code 1983 Edition, with Addenda through Summer 1983,Section XI, were completed in May 1997. Allexaminations were performed to the maximum extent possible utilizing automated examination equipment, techniques, and data I recording/analysis systems. The RPV welds were volumetrically (UT) examined using +0 qualified in accordance with Appendix VIIIof Section XI, as implemented by the ('rocedures utility Performance Demonstration Initiative. In addition, the welds were subject to visual 97i2230009 97i2i6 Ifllllflllfllllfllfll jl fffl/illlff/fll 5413 Shearon Harris Road New Hill NC Tel 919 362-2502 Fax 919 362-2095

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Document Control Desk e

SERIAL: HNP-97-217 Page 2

'(VT-2) examinations. As a result of the examinations, six recordable indications were detected, but were within the allowable Code limits. By letter dated August 29, 1997 (HNP-97-169),

CP8cL forwarded the HNP ISI Summary Report documenting the inspections performed during Cycle 7 operations, including Refueling Outage No. 7 (RFO-7).

As stated in the CP8cL letter to the NRC dated March 11, 1997 (HNP-97-060), CP&L committed to notify the NRC ifthe augmented examinations conducted during RFO-7 could not obtain "essentially 100%" volumetric coverage for each RPV weld. Due to RPV design configuration obstructions and/or limitations, several welds did not receive "essentially 100%" volumetric coverage examination. Therefore, CPS's requesting relief from the "essentially 100%"

volumetric coverage requirement for these welds.

The detailed request for relief number R1-011 is provided in Attachment 1 to this letter. This relief request indicates the specific components for which relief is requested, the basis for requesting relief, the alternate examinations performed, and the justification that an acceptable level of quality and safety has been achieved. Attachment 2 to this letter provides the results of the 1997 automated inservice examination of the RPV and adjacent piping welds at HNP.

Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646.

Sincerely, AEC/aec Attachments (2) c: Mr. J. B. Brady (NRC Senior Resident Inspector)

Mr. L. A. Reyes (NRC Regional Administrator, Region II)

Mr. V. L. Rooney (NRR Project Manager, HNP)

Document Control Desk SERIAL: HNP-97-217 Page 3 bc: Ms. D. B. Alexander Ms. W. C. Langston (PEARAS File)

Mr. T. C. Bell Mr. C. W. Martin (BNP)

Mr. H. K. Chernoff (RNP) Mr. R. D. Martin Mr. B.H. Clark Mr. P. M. Odom (RNP)

Mr. G. W. Davis Mr. W. S. Orser Mr. J. W. Donahue Mr. R. F. Saunders Mr. W. J. Dorman (BNP) Mr. D. L. Tibbitts Mr. W. J. Hindman Mr. C. A. VanDenburgh Mr. W. D. Johnson Nuclear Records Mr. R.M. Krich Licensing File File: H-X-0710

ATTACHMENT1 TO SERIAL: HNP-97-217 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL

A ACHMENT I TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAINING WELDS IN REACTOR VESSEL COMPONENTS FOR WHICH RELIEF IS REQUESTED:

B1.11 STHW-RV-04 Lower shell to bottom head 1)

B1.21 CHW-RV-17 Bottom Head Dome (Table 2)

B1.22 MHW-RV-16 Meridional (Table 2)

FTSW-RV-01 to Upper Shell (Table

@45'lange B1.30 2)

B3.90 RVNOZB0-N-02 Outlet Nozzle 9265'utlet 9265'Table (Table 2)

B3.90 RVNOZ CO-N-04 Nozzle (Table 2) 6145'utlet B3.90 RVNOZAO-N-06 Nozzle 925'afe (Table 2)

B5.10 RVNOZAI-N-01-SE End to Inlet Nozzle (Table 2) 9335'utlet B5.10 RVNOZB0-N-02-SE Nozzle to Safe End (Table 2)

Table 1 provides the results of the augmented RPV examinations for the RPV shell welds.

Table 2 provides the results of the RPV examinations for RPV welds other than shell welds.

INSERVICE INSPECTION REQUIREMENTS:

ASME Section XI, 1983 Edition with Addenda through Summer 1983.

Examination Category B-A, Item Number B1.11, B1.21, B1.22, B1.30 Examination Category B-D, Item Number B3.90 Examination Category B-F, Item Number B5.10 CODE RELIEF REQUEST:

Relief is requested from 100 percent volumetric (UT) examination coverage due to pressure retaining welds not being 100 percent accessible over the entire length. The examinations are limited because of physical obstructions and surface geometry such as instrumentation tubes, support lugs, weld transition, integral extension and counterbore geometry.

BASIS FOR REQUESTING RELIEF:

The subject welds received limited examination coverage due to physical obstructions and nonconducive geometric surface conditions. The obstructions physically prevent 100 percent examination coverage of the subject weld volume. The nonconducive geometric surface conditions prevent sufficient sound propagation into the weld examination volume at specific locations, therefore 100 percent examination coverage is not achievable. Attempting to perform supplemental examinations from the outside surface would have required extensive surface preparation and expended unwarranted dose without a commensurate increase in the level of reliability, quality, or safety.

Page A1-1

A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. Rl-011 PRESSURE RETAINING WELDS IN REACTOR VESSEL

'ALTERNATEEXAMINATIONS:

The Reactor Pressure Vessel (RPV) pressure retaining welds are volumetrically (UT) examined to the maximum extent possible in accordance with the Inservice Inspection Program schedule.

In addition, the welds are subject to visual (VT-2) pressure tests during each refueling outage.

TECHNICALJUSTIFICATION FOR REQUESTING RELIEF:

Pressure retaining welds in the RPV have been volumetrically (UT) examined to the maximum extent possible during preservice and first interval inservice examinations with no rejectable indications noted. The design configuration introduces obstructions and nonconducive surface conditions that prevent 100 percent volumetric examination coverage. The minimal number and magnitude of indications recorded during the preservice examinations and first interval inservice examinations indicate that the majority of the vessel examination volume is free of detrimental discontinuities. Therefore, the likelihood of the limited areas not examined due to physical obstructions having a rejectable indication is minimal. The RPV examinations have been performed utilizing the state of the art examination equipment, techniques and data recording/analysis systems. Additionally, Performance Demonstration Initiative procedures, qualified personnel and techniques were utilized as a conservative measure to incorporate the current industry practice and technology.

CONCLUSION Approval of this relief request will have no impact on overall plant quality, safety or reliability, since the welds have been subject to extensive construction code, preservice, and inservice examinations. In addition, the pressure retaining welds are subject to visual (VT-2) pressure tests during refueling outages.

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A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 1: Results of Harris Augmented Reactor Pressure Vessel Examinations 1" 10- Year Interval WELD ITEM NO. DESCRIPTION COVERAGE LIMITATION CSW-RV-02 B1.11 Upper Shell to Intermediate Shell 100% N/A CSW-RV-03 B1.11 Intermediate Shell to Lower Shell 100% N/A STHW-RV-04 B1.11 Lower Shell to Bottom Head 80% Radial Support Lugs and Weld Transition LSW-RV-05 B1.12 Upper Shell Longitudinal 91% Noz. AON-06 and Flange Taper (>90%)

LSW-RV-06 B1.12 Upper Shell Longitudinal 96% Noz. BIN-03 and Flange Taper (>90%)

LSW-RV-07 B1.12 Intermediate Shell Longitudinal 100% N/A LSW-RV-08 B1.12 Intermediate Shell Longitudinal 100% N/A LSW-RV-09 B1.12 Lower Shell Longitudinal 100% N/A LSW-RV-10 B1.12 Lower Shell Longitudinal 100% N/A Page Al-3

A ACHMENT 1 TO SERIAL HNP 7 REQUEST FOR RELIEF NO. Rl-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 2: Results of Harris Reactor Pressure Vessel Examinations 1" 10- Year Interval WELD ITEM NO. DESCRIPTION LIMITATION CHW-RV-17 B1.21 Bottom Head Dome 67% Instrumentation Tubes MHW-RV-11 B1.22 Meridional 94% Instrumentation Tubes and Radial Support Lug (>90%)

8345'eridional MHW-RV-12 B1.22 94% Instrumentation Tubes and Radial Support Lug (>90%)

8285'eridional MHW RV-13 B1.22 95% Instrumentation Tubes

(>90%)

8225'eridional MHW-RV-14 B1.22 95% Radial Support Lug (>90%)

8165'eridional MHW-RV-15 B1.22 91% Instrumentation Tubes and Radial Support Lug (>90%)

8105'eridional MHW-RV-16 B1.22 8215'OVERAGE 90% Instrumentation Tubes

@45'lange FTSW-RV-01 B1.30 to Upper Shell 67% ID Surface Taper RVNOZAI-N-01 B3.90 Inlet Nozzle 93% Nozzle Inner Radius 8335'utlet

(>90%)

RVNOZB0-N-02 B3.90 Nozzle 80% Integral Extension

@265'nlet RVNOZBI-N-03 B3.90 Nozzle 93% Nozzle Inner Radius

@215'utlet

(>90%)

RVNOZCO-N-04 B3.90 Nozzle 80% Integral Extension

@145'nlet RVNOZCI-N-05 B3.90 Nozzle 93% Nozzle Inner Radius 895'utlet

(>90%)

RVNOZAO-N-06 B3.90 Nozzle 80% Integral Extension 825'nlet RVNOZAO-N B3.10 Nozzle 100% N/A IRS @335'utlet RVNOZB0-N B3.10 Nozzle 100% Integral Extension IRS 8265'nlet RVNOZBI-N B3.10 Nozzle 100% N/A IRS Page Al-4

A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 2: Results of Harris Reactor Pressure Vessel Examinations 1" 10-Year Interval WELD ITEM NO. DESCRIPTION LIMITATION RVNOZCO-N Integral Extension B3.10 Outlet Nozzle 100%

IRS 8145'nlet RVNOZCI-N B3.10 Nozzle 100% N/A IRS 895'utlet RVNOZAO-N B3.10 Nozzle 100% Integral Extension IRS RVNOZAI-N B5.10 825'OVERAGE End to Inlet Nozzle 825'afe 74% ID Surface Counterbore SE 8335'utlet RVNOZB0-N B5.10 Nozzle to Safe End 76% ID Surface Counterbore SE 8265'afe RVNOZBI-N B5.10 End to Inlet Nozzle 95% No Relief Requested SE (>90%)

8215'utlet

'VNOZCO-N 85.10 Nozzle to Safe End 94% No Relief Requested SE 6 (>90%)

145'afe RVNOZCI-N B5.10 End to Inlet Nozzle 92% No Relief Requested SE (>90%)

95'utlet RVNOZAO-N B5.10 Nozzle to Safe End 99% No Relief Requested SE (>90%)

Page A1-5

ATTACHMENT2 TO SERIAL: HNP,-97-217 1997 AUTOMATEDINSERVICE EXAMINATIONOF THE REACTOR PRESSURE VESSEL AND ADJACENT PIPING WELDS AT THE HARRIS NUCLEAR PLANT