ML14183A232
| ML14183A232 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/19/1992 |
| From: | Mclellan T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A231 | List: |
| References | |
| NUDOCS 9210260389 | |
| Download: ML14183A232 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON NUCLEAR PROJECT, UNIT NO. 2 DOCKET NUMBER:
50-261
1.0 INTRODUCTION
Technical Specification 4.0.1 for H. B. Robinson Nuclear Project, Unit No. 2, (HBR 2) states that inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel 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).
10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
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 materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during each ten-year interval 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 start of the 120-month inspection interval, 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 conformance 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 that are determined to be authorized by law, will not endanger life, 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.
260399 921019 PDR ADOCK.05000261 o
-2 The Licensee, Carolina Power & Light Company, has prepared the H. B. Robinson Nuclear Project, Unit No. 2, Third Ten-Year Interval Inservice Inspection (ISI) Program Plan, Revision 0, to meet the requirements of the 1986 Edition of Section XI of the ASME Boiler and Pressure Vessel Code, with the following exception. The extent of examination for Class 1, Examination Category B-J, piping welds has been determined by the requirements of the 1974 Edition, through Summer 1975 Addenda, as permitted by 10 CFR 50.55a(b). The staff, with technical assistance from its Contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the H. B. Robinson Nuclear Project, Unit No. 2, Third Ten-Year Interval Inservice Inspection Program Plan, Revision 0, additional information related to the Program Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for HBR2, during the third inspection interval.
2.0 EVALUATION 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 prior ISI commitments made by the licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from certain Section XI Code requirements deemed impractical by the licensee. The NRC staff has determined that the licensee's ISI Program Plan reflects compliance with the requirements listed above.
The information provided by the licensee in support of requests for relief has been evaluated and documented in the attached INEL Technical Evaluation Report (TER) EGG-MS-10352. We concur with the findings and recommendations contained in the subject report. Table 1 presents a summary of the relief requests and the status of each as determined by the staff.
3.0 CONCLUSION
Pursuant to 10 CFR 50.55a(g)(6)(i), Requests for Relief No. 1, No. 2, No. 3, No. 5, No. 8, No. 12, and No. 18 are granted as requested. Request for Relief No. 13 is granted with the conditions specified in the attached TER. The remainder of the relief requests were withdrawn by the licensee.
The staff concludes that the H. B. Robinson Nuclear Project, Unit No. 2, Third Ten-Year Interval Inservice Inspection Program Plan, Revision 0, with the additional information provided and the specific written relief, constitutes the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.1 and is therefore acceptable.
Principal Contributor: T. McLellan Date: October 19, 1992
H. B. Robinson Nuclear Project Page 1 of 3 Third 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Relief Request System or xaExam Item Required Request Nmber Component Cate9ory No.
Volume or Ares to be Examined Method Li censee Proposed Alternative Status RR-01 Pressurizer B-D B3.120 Surge nozzle inside radius section Volumetric None. VT-2 visual exam Granted 2/13/92 examination during system pressure tests RR-02 Regenerative B-B 82.51 Class 1 circumferential head welds Volumetric None. VT-2 visual exam Granted part 1 Heat 92.60 Tubesheet-to-head weld examination during the system hydrostatic Exchangers B-D B3.150 Nozzle-to-vessel welds test at the end of the B3.160 Nozzle inside radius sections interval part 2 C-A C1.10 Class 2 circumferential shell welds Granted C1.30 Tubesheet-to-shell welds RR-03 Ultrasonic IWA-2232 Materials for fabrication of IWA-2232(a),
Use of existing calibration Granted Calibration calibration blocks (b), (c),
blocks Blocks and (d)
RR-04 Reactor Vessel B-F B5.10 Reactor vessel nozzle-to-safe end Surface and Withdrawn Piping volumetric in 2/13/92 85.130 Dissimilar metal piping welds examinations submittal RR-05 Reactor B-A 81.21 Closure head peel segment-to-disk Volumetric None. Visual during Granted Pressure Weld No. 1 examination regularly scheduled system Vessel pressure tests RR-06 Class 1 Piping B-J B9.10 Class 1 piping and branch Surface and Withdrawn 89.31 connection welds NPS 4 or larger volumetric in 2/13/92 examinations submittal RR-07 Reactor B-J 89.11 Crossover Leg elbows Surface and Withdrawn Coolant System B9.12 volumetric in 2/13/92 examinations submittal
H. B. Robinson Nuclear Project Page 2 of 3 Third 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Relief Request System or Exam Item Requi red Request Mumber Component Category No.
Volume or Area to be Examined ethod Licensee Proposed Alternative Status RR-08 Reactor B-J B9.11 Cold leg circumferential butt Surface and None Granted Coolant System Weld 13 on sketches CPL-107, -107A, volumetric and -107B examinations RR-09 Class 1 Piping B-K-1 610.10 Integrally welded attachments Volumetric Withdrawn or surface in 2/13/92 examinations submittal RR-10 Class 1 Pumps B-K-1 510.20 Integrally welded attachments Volumetric Withdrawn or surface in 2/13/92 examinations submittal RR-11 Regenerative B-D B3.150 Nozzle-to-vessel welds Volumetric Withdrawn.
Heat Exchanger examination in 2/13/92 submittal RR-12 Steam B-D B3.140 Nozzle inner radius sections Volumetric Visual exam once during the Granted Generators I
examination examination interval RR-13 Reactor B-L-1 812.10 Reactor coolant pump casing welds Volumetric External surface exam to the Granted Coolant Pumps examination extent practical with conditions B-L-2 812.20 Casing internal surfaces VT-3 visual VT-3 visual exam if a pump is in TER examination disassembled for maintenance RR-14 Regenerative C-A C1.30 Tubesheet-to-shel weld Volumetric Withdrawn Heat Exchanger examination in 2/13/92 submittal
H. B. Robinson Nuclear Project Page 3 of 3 Third 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Relief Request System or Exam Item Required Request Nmber Component Category No.
Volume or Area to be Examined Method Licensee Proposed Alternative Status RR-15 Class 2 Piping C-F-1 C5.11 Circumferential welds Surface and Withdrawn C5.21 volumetric in 2/13/92 examinations submittal RR-16 Ultrasonic Article Wall thickness variation between 111-3410 Code Case N-461 Withdrawn Calibration 111-3400 calibration block and piping in 2/13/92 Blocks submittal RR-17 Ultrasonic Article Walt thickness variation between 111-3410 Use of Code Case N-461 Withdrawv Calibration 111-3400 calibration block and piping in 2/13/92 Blocks submittal RR-18 Reactor Vessel B-F 85.10 Nozzle-to-safe end welds Surface and Ultrasonic examination from Granted Piping volumetric the ID of the pipe B5.130 Dissimilar metal welds examination
- . 4ENCLOSURE 1
EGG-MS-10352 August 1992 TECHNICAL REPORT TECHNICAL EVALUATION REPORT ON THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN:
IdBaho CAROLINA POWER AND LIGHT COMPANY, National H. B. ROBINSON NUCLEAR PROJECT, UNIT 2, Engineering DOCKET NUMBER 50-261 Laboratory Managed B. W. Brown by the U S.
S. G. Galbraith Department A. M. Porter of Energy n
Prepared for the 44 U.S. NUCLEAR REGULATORY COMMISSION Wor* performe under DOE Conact No. DE-AC7-76&DI15OD