ML17261B123
| ML17261B123 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/06/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17261B121 | List: |
| References | |
| NUDOCS 9008080268 | |
| Download: ML17261B123 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING THE THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN LICENSE NO. DPR-18 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 INTRODUCTION Technical Specification 4.2.1.5 for the R. E. Ginna Nuclear Power Station 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 fo 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 the third 10-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 12 months prior to the start of the 120-month inspection interval, subject to the limitations and modifi-cations 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 his facility, information shall be submitted to the Commission ASME Code requirement After the 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 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.
9008080268 90080o PDR ADOCK 05000244 9
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The Licensee, Rochester Gas and Electric Corporation, has prepared the R.
E. Ginna Nuclear Power Station Third 10-Year Interval Inservice Inspection (ISI)
Program Plan to meet the requirements of the 1986 Edition of Section XI of the ASIDE Boiler and Pressure Vessel Code.
The sta'ff, with technical assistance from its Contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the Third 10-Year Interval Inservice Inspection Program Plan, additional information related to the Program Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for R. E. Ginna Nuclear Power Station during the third inspection interval.
EVALUAT!ON The ISI Program Plan has been evaluated for (a) application of the correct Section Y,I 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 impractical Section XI Code requirements.
Mith the exception of Requests for Relief Nos.
10 and 13, the 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 from impractical requirements has been evaluated and the bases for granting relief from those requirements are documented in the attached INEL Technical Evaluation Report EGG-t'S-8923 (Attachment 2).
1(e concur with the findings and recommendations contained in the subject report.
Table 1 (Attachment 1) presents a summary of the reliefs reouested and the status of the requests as determined by the staff.
CONCLUSION The staff concludes that the R. E. Ginna Nuclear Power Station Third 10-Year Interval Inservice Inspection Program Plan, with the additional information provided and the specific written relief, with the exception of Requests for Relief Nos.
10 and 13, constitutes the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.2.1.5 and is therefore acceptable.
Principal Contributor:
G. Johnson (301) 492-0756 Attachments:
1.
Summary of Relief Requests 2.
INEL Technical Evaluation Report
R.
E. Ginna Nuclear Power Station Page 1 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Attachment 1
Relief Request Number System or Exam.
Item Volume or Area to be Examined Reactor B-A B1.30 Shell-to-flange weld Pressure Vessel Required Method Volumetric (50%
examined by end of 1st period)
Licensee Proposed Alternative 100% volumetric exam.
performed at or near end of interval Relief Request Status Granted Reactor Pressure Vessel 8-D B3.90 Nozzle-to-vessel welds and and nozzle inside radius B3.100 sections Use of an "Authorized Inspection Agency" to provide inspection services Volumetric (partial deferral to end of interval)
Paragraph.
IWA-1400(f)
(Authorized Inspection Agency to provide inspection services.
Certain admi n.
functions perf.
by "Enforcement Authority" and "Authorized Nuclear Inservice Inspector.")
100% 'volumetric exam.
performed at or near end of interval Records and reports of IS I developed and maintained by Licensee.
Functions of the Authorized Nuclear Inservice Inspector performed by personnel from Hartford Steam Boiler Inspection and Insurance Company.
Granted Granted
R.
E. Ginna Nuclear Power Station Page 2 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number System or Exam.
Item Volume or Area
~C C
N to be Examined Required Method Licensee Proposed Alternative Relief Request Status Reactor Coolant Pumps B-L-1 B12. 10 Pump casing welds B-L-2 B12.20 Pump casing internal surfaces Volumetric VT-3 visual VT-1 visual exam. of external surfaces of welds of one pump casing VT-3 visual exam. of internal surfaces each time a
pump is disassembled Granted with conditions stated in Technical Evaluation Report Class 1
Valves B-H-2 B12.50 Internal surfaces of one valve in each of the following four groups:
10" Velan/Gate valves
- 700, 701,
- 720, 721; 10" Darling/Check valves 842A, 842B, 867A, 8678; 6" Velan/Check valves 852A, 852B; 6" Velan/Gate valves,853A, 853B VT-3 visual VT-3 visual when valves are disassembled Granted with conditions stated in Technical Evaluation Report Waste Disposal System Radioactive waste holdup tank Hydrostatic test Withdrawn by Licensee in I/16/90 submittal
R.
E. Ginna Nuclear Power Station Page 3 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Rel ief Request Number System or Exam.
Item N
Chemistry and Volume Control System Volume or Area to be Examined Charging Pumps I, 2, and 3 and associated discharge piping to discharge isolation valves Required Method Hydrostatic test at 3420 psig per IWC-5222(a)
Licensee Proposed Alternative Hydrostatic test at 2400 psig Relief Request Status Granted Reactor Coolant System Overpressure protection Nitrogen Accumulator System Valves PCV 430 and PCV 431C Hydrostatic test at 137.5 psig per IWC-5222(a)
Hydrostatic test Granted per Code up to flex connection of the valve operator Steam
'enerator and Hain Steam Piping Secondary side of the Steam Generator and associated Main Steam piping Hydrostatic test at 1356 psig per IWC-5222(a)
Hydrostatic test Granted at 1194 psig 10 Standby Auxiliary Feedwater System Standby Auxi1 iary Feedwater Pump recirculation line between valves AOV 9710A and AOV 9710B and their associated downstream flow orifices Hydrostatic test per IWD-5223(a)
VT-2 visual examination at'perational discharge pressure once each period during functional testing Denied
R.
E. Ginna Nuclear Power Station Page 4 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Rel ief Request Number System or
'xam.
Item Chemical and Volume Control System Volume or Area to be Examined Boric acid filter and associated piping Required Method Hydrostatic test Licensee Proposed Alternative Relief Request Status Withdrawn by Licensee in 1/16/90 submittal 12 Emergency Diesel Generation System Starting Air, including receiver tanks and associated piping; Fuel Oil Transfer
- pumps, suction and discharge lines, including miscellaneous lines terminating at oil storage tanks; and Jacket Cooling Water
- System, including miscellaneous lines terminating at the cooling water expansion tanks.
Hydrostatic test per IWD-5223(a)
Pressure decay test on air
- receiver, once each quarter, and surveillance test on a
monthly basis per Tech.
Spec.
6.4.1.
Granted 13 Non-ISI Classified Systems Lines of non-ISI classified
- systems, which do not carry radioactive gases or fluids, that penetrate primary containment:
- 120, 121,
- 124, 132,
- 202, 203,
- 210, 301,
- 303, 304,
- 305, 307,
- 309, 310,
- 313, 317,
- 324, 332 Hydrostatic test per IWC-5222(a)
Appendix J test and VT-2 visual exam. of exposed portions during normal operation Denied
R.
E. Ginna Nuclear Power Station Page 5 of 5 TABLE I
SUMMARY
OF RELIEF RE UESTS Relief Request Number 14 System or Exam.
Item
~C C..
II Service Water System Volume or Area to be Examined All pressure retaining components within the Class 3 portion of the Service Water System Required Method Hydrostatic test per IWD-5223(a)
Licensee Proposed Alternative Inservice test and assoc.
visual exam. of components within the operational boundary at operating pressure each period Relief Request Status Granted 15 Class 2
Piping Welds C-F-1 C5.10 and C5.50 Withdrawn by Licensee in 1/16/90 submittal 16 Class 1
Piping Integrally Welded Attachments Class 2
Piping Integrally Welded Attachments B-K-I B10. 10 C-C C3.20 Withdrawn by Licensee in I/16/90 submittal