ML17222A742
| ML17222A742 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/07/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17222A740 | List: |
| References | |
| NUDOCS 8904170314 | |
| Download: ML17222A742 (11) | |
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~O 4~*~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ENCLOSURE 2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR THE SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN FLORIDA POWER EE LIGHT COMPANY ST.
LUCIE PLANT UNIT NO.
1 DOCKET NO. 50-335
1.0 INTRODUCTION
Technical Specification 4.0.5 for the St. Lucie Plant, Unit 1, 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).
In accordance with 10 CFR 50.55a(g)(4),
the 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 second 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 modifications listed therein.
The components (including supports) may meet the requirements set forth i n 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)(iii), 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 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 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.
89'04i703i4 85'0407 PDR ADOCK 05000335 9
P C t
The licensee, Florida Power and Light Company, has prepared the St. Lucie Plant, Unit 1, Second 10-Year Interval Inservice Inspection (ISI) Program, Revision 0, and Plan, Revision 0, to meet the requirements of the 1983 Edition,- Summer 1983 Addenda of Section XI of the"ASME Boiler and Pressure Vessel Code, with the exception of the extent of examination of Class 2 piping welds which has been determined by ASME Code Case N-408 as allowed by Regulatory Guide 1.147.
The staff, with technical assistance from its contractor, Idaho National Engineering Laboratory (INEL), has evaluated the Second 10-Year Interval Inservice Inspection
- Program, Revision 0, and Plan, Revision 0, additional information related to the
- Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for St. Lucie Plant, Unit 1, during the second inspection interval.
2.0 EVALUATION The ISI Program and Plan have 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 impractical Section. XI Code requirements.
The staff has determined that the licensee's ISI Program Plan reflects compliance with the requirements listed above except several Class 2 systems (CHR, CS, SD-CLG, LPSI) have been completely omitted from the'xamination program based on the pipe wall thickness exemptions contained in Code Case N-408.
Paragraph 10 CFR 50.55a(b)(2)(iv) requires that ASME Code Class 2
piping welds in the Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal systems shall be examined.
These systems must not be completely omitted from inservice volumetric examination based on Section XI exclusion criteria contained in IWC-1220 or in Code Case N-408.
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 stated in the INEL Technical Evaluation Report (TER),
EGG-MS-8286 (Enclosure 1).
The staff agrees with the findings and recommendations contained in the TER.
Table 1 presents a
summary of the reliefs requested and the status of the requests as determined by the staff.
3.0 CONCLUSION
The staff concludes that the St. Lucie Plant, Unit 1, Second 10-Year Interval Inservice Inspection
- Program, Revision 0, and Plan, Revision 0, with the addi-tional information provided and the granted reliefs, is conditionally acceptable.
The condition for being acceptable and in compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5 is the performance of examinations of welds in the Residual Heat
- Removal, Emergency Core Cooling and Containment Heat Removal systems in accordance with 10 CFR 50.55a(b)(2)(iv).
Date:
April 7, 1989 Princi al Contributor:
D. Jackson
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St. Lucie Plant, Unit 1 Page 1 of 5 TABLE 1
SUMMARY
OF PELIEF RE UESTS Relief Request t/umber Rk-1 System or
~tom onent Reactor Pressure Vessel Exam.
Itern Cat.
No.
B-A Bl.ll B1.12 81.21 81.22 B1.30 Volume or Area to be Examined Middle Shell-to-Lower Shell Weld 9-203; Lower Shell Vertical Weld 3-203C; Lower Head Dollar Plate Weld 204-02; Lower Head l1eridional Weld 204-03A; Upper Shell-to-Flange Weld 7-203 Required Method Volumetric Licensee Proposed Alternative Volumetric (UT) exam to extent practica'I; exams.include supplemental beam angles to maximize the percentage examined Relief Request Status Granted RR-2 Reactor B-A Pressure Vessel Closure Head Welds Withdrawn by Licensee 8/29/88 RR-3 (Part 1
of 2)
Steam Generator S/G-A B2.32 B2.40 Meridional Head Weld No.
1A-1-104-A; Tubesheet-to-Primary Extension Ring Weld and Primary Extension Ring-to-Head Weld Volumetri c Volumetric (UT) exam to extent practical; exams include supp lementa I beam angles to maximize the percentage examined Granted
St. Lucie Plant, Unit 2 Page 2 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number System or
~Con onent Exam.
Item Cat.
No.
Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status RR-3 (Part 2
of 2)
Steam Generator 1A Nozzles Steam Generator 18 Nozzles 8-D 83.130 Inlet Nozzle-to-Shell 83.140 Weld lA-111C; Outlet Nozz le-to-Shel 1
We 1ds lA-5-11 lA and 1A-5-1118; and nozzle inside radius sections; and 83.130 Inlet Nozz le-to-Shel 1
83.140 Weld 18-11 lC*; Outlet Nozzle-to-Shel 1
He 1ds 18-5-111A and 18-5-1118;-
and nozzle inside radius sections
- NOTE: Held 18-lllC was inadvertently listed as 1A-111C in the TER Volumetric Volumetric (UT) exam to extent practical; exams include supplemental beam ang les to maximize the percentage examined Granted RR-4 Reactor Pressure Vessel Nozz les 8-D 83.90 Nozzle-to-vessel we1ds 83.100 and nozzle inside radius sections for Outlet Nozzles 205-05, 205-10 and Inlet Nozzles 205-01A, 205-018, 205-09A, and 205-098 Volumetri c Volumetric (UT) exam to extent practical both from vessel shell and from nozzle bore Granted
St. Lucie Plant, Unit 1 Page 3 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number System or Exam.
Item Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status RR-5 Pressurizer B-D Nozzles B3.110 Nozzle-to-vessel we 1ds B3.120 and nozzle inside radius sections for Safety Nozzles SV-A, SV-B, and SV-C, Relief Nozzle RV, Spray Nozzle SP, and Surge Nozzle SURGE Volumetri c Volumetric (UT) exam to extent practical; exams include supp 1ementa 1
beam angles to maximize the percentage examined Granted RR-6 Class 1
Piping B-8 B9.11 Reactor Pressure Vessel nozile-to-pipe transition welds Volumetri c and Surface A remote volumetric (UT) examination of entire weld volume in lieu of surface exam Granted RR-7 Reactor Coolant Pump B-L-1 B12.10 Pump casing welds 8-L-2 B12.20 Pump casings Volumetri c Visual (VT-3)
Radiographic exam of casing welds if di sassemb 1 ed for maintenance Granted/
provided Code-required exams are performed VT-3 exam of if RC Pump casings if disassembled disassemb'led for for maintenance maintenance
St. Lucie Plant, Unit I page 4 of 5 TABLE 1
SUMMARY
OF RELIEF RE UESTS Relief Request Number System or
~Coi onent Exam.
Itern Cat.
No.
Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status RR-8 Class 1
B-H-2 Valve Bodies B12.50 Internal surfaces of one valve in each group of valves of the same construction, manufacturing
- method, and that performs similar functions in a system Visual (VT-3)
Visual (VT-3) examination if disassembled for maintenance a
J Granted/
provided VT-3 exams performed if valves disassembled for maintenance RR-9 Class 2
Piping Welds C-F Pressure retaining piping welds in Containment Spray System Withdrawn by Licensee 8/29/88 RR-10 Snubber Inservice Test (IST)
Requirements IST is not within scope of this document and is being eva luated elsewhere
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St. Lucie Plant, Unit 1
Page 5 of 5 TABLE 1 SUYiMARY OF RELIEF RE UESTS Relief Request t(umber RR-11 System or
~Com onent Ultrasonic Calibration Blocks Exam.
Itern Cat.
No.
Appendix III Volume or Area to be Examined Required Method Relief is requested from the requirement that calibration blocks UT-4A, UT-6, UT-45, UT-4, and UT-5 be made from the same materials and/or from the same nominal diameter and wall thickness or pipe schedule as the material being joined Licensee Proposed Alternative Continued use of current calibration blocks Rel ief Request Status Granted RR-12 (Part 1
of 2)
Class 1
Piping Helds B-J Mithdrawn by Licensee 8/29/88 RR-12 (Part 2 of 2)
Class 2
Piping Welds C-F Withdrawn by Licensee 8/29/88
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