HNP-97-217, 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

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: HNP-97-217, 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 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 FACIL:50-.400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH,~RAIMI~~.-

AUTHOR AFFILIATION ROBINSON,W.R.

Carolina Power

&. Light Co.

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

DOCKET ¹ 05000400

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 COPIES RECEIVED: LTR J ENCL I

SIZE: ICI 4 H.

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES:Application for permit renewal filed.

05000400 G

RECIPIENT ID CODE/NAME PD2-1 LA ROONEY, V INTERNAL: ACRS E

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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:

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Carolina Power &Light Company PO Box 165 New Hill NC 27562 William R. Robinson Vice President Harris NUclear Plant DEC 16 1997 SERIAL: HNP-97-217 10 CFR 50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEARPOWER PLANT DOCKETNO. 50<00/LICENSE NO. NPF-63 ASME BOILERANDPRESSURE 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 followingAmerican Society ofMechanical Engineers (ASME) Boiler and Pressure Vessel (BkPV) Code,Section XI,requirements for the final inspection period of the first 10-year inspection interval:

"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 ASMEBAPV 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

('rocedures qualified in accordance with Appendix VIIIof Section XI, as implemented by the utilityPerformance Demonstration Initiative. In addition, the welds were subject to visual 97i2230009 97i2i6 Ifllllflllfllllfllfllfffl/illlff/fll jl 5413 Shearon Harris Road New Hill NC Tel 919 362-2502 Fax 919 362-2095

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Document Control Desk 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&Lcommitted 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 reliefnumber 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 ofquality and safety has been achieved. 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 Mr. T. C. Bell Mr. H. K. Chernoff (RNP)

Mr. B.H. Clark Mr. G. W. Davis Mr. J. W. Donahue Mr. W. J. Dorman (BNP)

Mr. W. J. Hindman Mr. W. D. Johnson Mr. R.M. Krich Ms. W. C. Langston (PEARAS File)

Mr. C. W. Martin (BNP)

Mr. R. D. Martin Mr. P. M. Odom (RNP)

Mr. W. S. Orser Mr. R. F. Saunders Mr. D. L. Tibbitts Mr. C. A. VanDenburgh Nuclear Records 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 RETAININGWELDS INREACTOR VESSEL COMPONENTS FOR WHICHRELIEF IS REQUESTED:

B1.11 B1.21 B1.22 B1.30 B3.90 B3.90 B3.90 B5.10 B5.10 STHW-RV-04 CHW-RV-17 MHW-RV-16 FTSW-RV-01 RVNOZB0-N-02 RVNOZ CO-N-04 RVNOZAO-N-06 RVNOZAI-N-01-SE RVNOZB0-N-02-SE Lower shell to bottom head Bottom Head Dome Meridional

@45'lange to Upper Shell Outlet Nozzle 9265'utlet Nozzle 6145'utlet Nozzle 925'afe End to Inlet Nozzle 9335'utlet Nozzle to Safe End 9265'Table 1)

(Table 2)

(Table 2)

(Table 2)

(Table 2)

(Table 2)

(Table 2)

(Table 2)

(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 ofphysical 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 RETAININGWELDS 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.

TECHNICALJUSTIFICATIONFOR 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 ofindications recorded during the preservice examinations and first interval inservice examinations indicate that the majority of the vessel examination volume is free ofdetrimental 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 willhave 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.

Page Al-2

A ACHMENT 1 TO SERIAL HNP 17 REQUEST FOR RELIEF NO. R 1-011 PRESSURE RETAININGWELDS IN REACTOR VESSEL Table 1: Results ofHarris Augmented Reactor Pressure Vessel Examinations 1" 10-Year Interval WELD CSW-RV-02 CSW-RV-03 STHW-RV-04 LSW-RV-05 LSW-RV-06 LSW-RV-07 LSW-RV-08 LSW-RV-09 LSW-RV-10 ITEMNO.

B1.11 B1.11 B1.11 B1.12 B1.12 B1.12 B1.12 B1.12 B1.12 DESCRIPTION Upper Shell to Intermediate Shell Intermediate Shell to Lower Shell Lower Shell to Bottom Head Upper Shell Longitudinal Upper Shell Longitudinal Intermediate Shell Longitudinal Intermediate Shell Longitudinal Lower Shell Longitudinal Lower Shell Longitudinal COVERAGE 100%

100%

80%

91%

96%

100%

100%

100%

100%

LIMITATION N/A N/A Radial Support Lugs and Weld Transition Noz. AON-06 and Flange Taper (>90%)

Noz. BIN-03 and Flange Taper (>90%)

N/A N/A N/A 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 ofHarris Reactor Pressure Vessel Examinations 1" 10-Year Interval WELD CHW-RV-17 MHW-RV-11 MHW-RV-12 MHWRV-13 MHW-RV-14 MHW-RV-15 MHW-RV-16 FTSW-RV-01 RVNOZAI-N-01 RVNOZB0-N-02 RVNOZBI-N-03 RVNOZCO-N-04 RVNOZCI-N-05 RVNOZAO-N-06 RVNOZAO-N IRS RVNOZB0-N IRS RVNOZBI-N IRS ITEMNO.

B1.21 B1.22 B1.22 B1.22 B1.22 B1.22 B1.22 B1.30 B3.90 B3.90 B3.90 B3.90 B3.90 B3.90 B3.10 B3.10 B3.10 DESCRIPTION Bottom Head Dome Meridional 8345'eridional 8285'eridional 8225'eridional 8165'eridional 8105'eridional

@45'lange to Upper Shell Inlet Nozzle 8335'utlet Nozzle

@265'nlet Nozzle

@215'utlet Nozzle

@145'nlet Nozzle 895'utlet Nozzle 825'nlet Nozzle

@335'utlet Nozzle 8265'nlet Nozzle 8215'OVERAGE 67%

94%

94%

95%

95%

91%

90%

67%

93%

80%

93%

80%

93%

80%

100%

100%

100%

LIMITATION Instrumentation Tubes Instrumentation Tubes and Radial Support Lug (>90%)

Instrumentation Tubes and Radial Support Lug (>90%)

Instrumentation Tubes

(>90%)

Radial Support Lug (>90%)

Instrumentation Tubes and Radial Support Lug (>90%)

Instrumentation Tubes ID Surface Taper Nozzle Inner Radius

(>90%)

Integral Extension Nozzle Inner Radius

(>90%)

Integral Extension Nozzle Inner Radius

(>90%)

Integral Extension N/A Integral Extension N/A 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 ofHarris Reactor Pressure Vessel Examinations 1" 10-Year Interval WELD RVNOZCO-N IRS RVNOZCI-N IRS RVNOZAO-N IRS RVNOZAI-N SE RVNOZB0-N SE RVNOZBI-N SE

'VNOZCO-N SE RVNOZCI-N SE RVNOZAO-N SE ITEMNO.

B3.10 B3.10 B3.10 B5.10 B5.10 B5.10 85.10 B5.10 B5.10 DESCRIPTION Outlet Nozzle 8145'nlet Nozzle 895'utlet Nozzle 825'afe End to Inlet Nozzle 8335'utlet Nozzle to Safe End 8265'afe End to Inlet Nozzle 8215'utlet Nozzle to Safe End 6

145'afe End to Inlet Nozzle 95'utlet Nozzle to Safe End 825'OVERAGE 100%

100%

100%

74%

76%

95%

94%

92%

99%

LIMITATION Integral Extension N/A Integral Extension ID Surface Counterbore ID Surface Counterbore No Relief Requested

(>90%)

No Relief Requested

(>90%)

No Relief Requested

(>90%)

No Relief Requested

(>90%)

Page A1-5

ATTACHMENT2 TO SERIAL: HNP,-97-217 1997 AUTOMATEDINSERVICE EXAMINATIONOF THE REACTOR PRESSURE VESSEL ANDADJACENTPIPING WELDS ATTHE HARRIS NUCLEARPLANT