ML16141A978
| ML16141A978 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/15/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML15118A400 | List: |
| References | |
| NUDOCS 9511210312 | |
| Download: ML16141A978 (6) | |
Text
0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN, REVISION 1 AND ASSOCIATED REQUESTS FOR RELIEF FOR DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1. 2 AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287
1.0 INTRODUCTION
The Technical Specifications for Oconee Nuclear Station, Units 1, 2, and 3, state that the inservice inspection 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 Title 10 of the Code of Federal Regulations (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). Section 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 the first 10-year interval and subsequent intervals 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) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the Oconee Nuclear Station, Units 1, 2, and 3, third 10-year inservice inspection 9511210312 951115 PDR ADOCK 05000269 G
2 (ISI) interval is the 1989 Edition. The third 10-year interval for Unit 1 began July 15, 1994, and ends July 15, 2004. Unit 2 third 10-year interval began December 16, 1994, and ends September 9, 2004, and for Unit 3 the third 10-year interval began December 16, 1994, and ends December 16, 2004.
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.
In a letter dated December 20, 1993, Duke Power Company submitted to the NRC its Third.Ten-Year Interval Inservice Inspection Program Plan, Revision 0, and associated requests for relief for the Oconee Nuclear Station, Units 1, 2 and 3. During the staff's review of Revision 0 of the third 10-year ISI program plan, the licensee submitted Revision 1 of its program plan and associated requests for relief. Although, the staff reviewed Revision 0, this review is based on the latest revision of the licensee's program plan.
Additional information for Revisions 0 and I was provided by the licensee in its letters dated January 24 and May 11, 1995, respectively.
2.0 EVALUATION AND CONCLUSIONS The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the information provided by the licensee in support of its Third Ten-Year Interval Inservice Inspection Program Plan, Revision 0 through Revision 1, and associated requests for relief for Oconee Nuclear Station, Units 1, 2, and 3. Table 1 provides a summary of the licensee's requests for reliefs and the actions and conclusions of the staff.
Based on the information submitted, the staff adopts the contractor's conclusions and recommendations presented in the attached Technical Evaluation Report. No deviations from regulatory requirements or commitments were identified in the Oconee Nuclear Station, Units 1, 2, and 3 Third Ten-Year Interval Inservice Inspection Program Plan, Revision 1, with the exception of Requests for Relief Nos. ONS-007 (Unit 1) and ONS-008 (Units 2 and 3).
Requests for Relief Nos. ONS-007 and ONS-008 are denied, because the licensee did not provide sufficient technical information justification for relief from the Code requirement. The staff concludes that in lieu of Requests for Relief Nos. ONS-007 and ONS-008, the licensee should reconsider the use of Code Case N-481 for use at Oconee Nuclear Station, Units 1, 2, and 3.
However, if a technical problem exists in implementing Code Case N-481, then a
.3 request for relief from the Code requirements may be submitted citing the technical problems with the use of the Code Case and why the alternative would provide an acceptable level of quality and safety.
The proposed alternatives contained in Requests for Relief Nos. ONS-001, ONS 002, ONS-003, ONS-005, and ONS-006 will provide an acceptable level of quality and safety and are authorized pursuant to 10 CFR 50.55a(a)(3)(i) as requested with the exception of Requests for Relief Nos. ONS-001, ONS-002, and ONS-003, which are authorized with conditions. Requests for Relief Nos. ONS-001 and ONS-002 are authorized provided that the licensee's alternative meets the following two conditions specified in BAW-2228P Revision 1, "Fracture Mechanics Assessment of Postulated Outer Surface Semi-Elliptical' Circumferential RV Nozzle-to-Pipe Weld Flaws":
- 1.
The input stresses under normal/upset and emergency/faulted conditions shown in Table la. and lb. for the respective Oconee units are the result of using the bounding transient in the analysis; and
- 2.
The material in the inlet, outlet, and core flood nozzles is either A508 Class 2 carbon steel or SA 336.(316) stainless steel.
(Subsequent to the staff's review of the licensee's third 10-year inservice inspection program plan and associated requests for relief for Oconee, Units 1, 2, and 3, Revision 1 of BAW-2228P was submitted by the B&W Owners Group in its letter dated August 21, 1995, and has not been approved by the NRC at this time. However, the staff determined that, based on the above two conditions, it is acceptable for use by the licensee for Oconee, Units 1, 2, and 3.)
The alternative contained in Request for Relief No. ONS-003 is authorized provided that all related requirements of the 1990 addenda are met.
The staff concluded that compliance with the Code requirements regarding Requests for Relief Nos. ONS-004 and ONS-011 would result in hardship without a compensating increase in safety and that the proposed alternatives contained in the relief requests will provide reasonable assurance of operational readiness. Therefore, the alternatives contained in Requests for Relief Nos.
ONS-004 and ONS-011 are authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
In the case of Requests for Relief Nos. ONS-009 and ONS-010, the licensee has demonstrated that specific Code requirements are impractical and that granting relief will not endanger life, property, or the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on
4 the facility. In addition, the staff has concluded that the proposed testing would provide reasonable assurance of operational readiness of the subject systems. Therefore, relief is granted for Requests for Relief Nos. ONS-009 and ONS-010 pursuant to 10 CFR 50.55a(g)(6)(i) as requested.
Attachments:
- 1. Table 1
- 2. Technical Evaluation Report Principal Contributor: T. McLellan Date:
November 15, 1995
OCONEE NUCLEAR STATION UNITS 1, 2, and 3 Page 1 of 2 Third 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS DNS-002 lss1BJ 5.1 Reactor VeFss5.1 Nozzle-to-Paeipe edsVolumetric and Perform volumetric Authorized pseing
.elds surface exam from the inside conditionally Cas1examinations surface of 100% of the 50.55a(a)(3)(i) pipingweld volume get~~~~exmnain suf of 100%.............
of...
the.
5
)(3)(i).
ONS-003 Class 1, 2, IA-5250 Leaking Bolted Connections Remove all bolting Remove only the bolt Authorized and 3 and perform a VT-3 closest to the source conditionely piping visual examination and perform a VT-3 50.55a(a)(3)(i) visual examination ONS-DO4 Control Rod l.B-2430 Bolting Additional VT-i Visual examination of Authorized Drives visual only bolting exposed 50.55a~a)(3)(ii) examinations when to boric acid if umnacceptable indications caused by indications are boric acid found DNS-005 Control Rod 3-0-2 37.80 Bolting VT-i visual Replace bolting Authorized Drives examination when 50.55a(a)(3)(i) disassembled ONS-006 Reactor
-D 63.90 Nozzle-to-Vessel Welds schueling Deferral of Authorized Vessel B-J 83.100 Nozzle inside Radius Sections examinations until 50.55e(a)(3)(i)
B9.11 Nozzle-to-Pipe Welds third period
OCONEE NUCLEAR STATION UNITS 1, 2, and 3 Page 2 of 2 Third 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS teefxamination Request system orli Xxs Ie Licensee Proposed aeifRes Caepo~r"at Cat0go0 tio.
Votee" orAs o
Examined RaedFred 0!ethod ALtratve StatX ONS-007 Reactor B-L-1 812.10 Casing Welds VoLumetric Perform examinations Denied Coolant B-L-2 112.20 Internal Surfaces examination of only if a pump is Pumps Weld disassembled for Unit 1 VT-3 visual maintenance examination of surfaces ONS-008 Reactor B-L-1 12.10 Casing Weds Volumetric Perform examinations Denied Coolant B-L-2 112.20 Internal Surfaces examination of only if a pump Is Pumps Weld disassembled for Units 2 VT-3 visual maintenance and 3 examination of surfaces DNS-009 Letdown 8-D B13.160 Nozzle Inner Radius sections Volumetric None Granted Cooler examination 50.55a(g)(6)(1)
ONS-010 Main Steam C-F-2 CS.81 Circumferential Welds at Branch Surface Surface examination of Granted connections NPS 42 inches examination surrounding guard pipe 50.55a(g)(6)(i)
ONS-011 Reactor IUB-2420 Reactor Coolant Pumps 3A2 and Successive Visual examination of Authorized Coolant 361 Stud Hotes examinations surrounding area for 50.55a(a)(3)(ii)
Pumps boric acid Evaluation with stud missing