ML20155F910
| ML20155F910 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/10/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20155F907 | List: |
| References | |
| NUDOCS 8604250311 | |
| Download: ML20155F910 (9) | |
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UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION
{
WASHINGTON, D. C. 20655
% )
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO THE GRANTING OF RELIEF FROM CERTAIN INSERVICE INSPECTION REQUIREMENTS FOR ARKANSAS NUCLEAR ONE, UNIT NO. 1 ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 INTRODUCTION Technical Specifications for Arkansas Nuclear One, Unit No.1 state that inservice examination of 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.
We have reviewed the licensee's first ten-year interval inservice inspection program plan and the requests for relief from certain regiikements of the applicable ASME Code edition and addenda.
By letter dateo April 18, 1983, we had granted relief from the examination requirements which we had
-g determined to be impractical to perform at Arkansas Nuclear One, Unit 1.
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_We had also denied relief in those cases where the necessary findings enuld not be made.
Additional information and requests for relief from certain Code inspectic-requirements in the 1974 Edition of Section XI of the ASME Boiler and Pressure Vessel Code with Addenda through Summer 1975 determined to be impratical were received by letters dated November 12, 1982, November 19, 1984, December 19, 1984, January 31, 1985, and June 24, 1985.
In order to' complete the first ten-year inspection interval at the Arkansas Nuclear One, Unit 1, these requests for relief from inservice inspection requirements of the 1974 Edition nf the ASME Code Section XI with Addenda through Summer 1975 would need to be reviewed and granted as applicable.
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. EVALUATION Requests for relief from the requirements of Section XI which have been determined to be impractical to perform have been reviewed by our contractor, Science Applications International Corporation. The contractor's evaluations of the licensee's reouests for relief and his recommendations are presented in the Technical Evaluation Report (TER) attached (ATTACHMENT 1).
We have reviewed the TER and adopt the evaluations and recommendations.
A suninary of our determinations is presented in the following tables:
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CLASS 1 COMPONENTS LICENSEE' PROPOSED IWB-2600 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS Bl.6 &
B-F Bl.6:
Bl.6:
Volumetric Volumetric Granted B4.1 Reactor Nozzle-to-
& Surface From Vessel Vessel Safe End Welds ID Coincident B4.1:
B4.1:
with Vessel Piping Safe-End to Nozzle Exam Pressure Piping Welds Boundary
& Safe-End in Branch Piping Welds (2 Core Flood Nozzle-to-Safe End & Safe End-to-Pipe Welds)
Bl.12 B-H Reactor Integrally-Volumet '.
None Granted Vessel We?ded Vessel Provided e pports Visual Exam s
(vassel is Conducted Support Early in 2nd Skirt-to-Inspection Vessel Weld)
Interval Bl.13, Bl.14, Bl.13 &
Bl.13 &
Bl.13:
Bl.13:
Visual of Granted.
B2.9 & B3.8 Bl.14:
Bl.14:
Clocure Visual &
Accessible B-I-1 Reactor Head Surface.
Areas (1977 B2.9 &
Vessel Cladding or Volumetric Edition of B3.8:
B2.9:
Bl.14, B2.9 &
Bl.14. B2.9 Code Thru B-I-2 Pressuri-B3.8:
& B3.8:
Summer 1978 zer Vessel Visual Addenda)
B3.8:
Cladding Steam Generators
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TABLE 1 CLASS 1 COMPONENTS (continued) j i
LICENSEE PROPOSED IWB-2600 IWB,2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS B4.6 & B4.7 B-J Piping Branch B4.6:
Exam Per Granted Pressure Pipe Volumetric 1977 Edition Boundary Connection B4.7:
of Code Thru Welds Surface Summer 1978 l
B4.6:
Addenda Exceeding 6 in. Diameter B4.7:
6 in. Diameter
& Smaller B5.6 B-L-1 Reactor Pump Casing Volumetric Radiographic Granted Coolant Welds Exam (MINAC)
Pump Early in 2nd Inspection Interval B5.7 B-L-2 Pump Pump Visual Partial Granted Casings Surface Provided Replication Code-Required 4
Obtained Exam is Per-from Casing formed Upon Weld Volu-Pump Dis-metric Exam assembly l
for Maintenance e
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TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2600 IWC-2520 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM. CAT.
COMPONENT EXAMINED METHOD EXAMINATION STATUS C1.2 C-B Decay Nozzle-to-Volumetric Surface of Granted Heat Vessel Welds Nozzle-to-Removal (Welds with Collar &
Cooler Installed Collar-to-Reinforcing Vessel Fillet Collars)
Welds II)
C2.1, C2.2 C-F &
Piping C2.1:
Volumetric Exam of Granted
& C2.3 C-G Circumferential Pipes with Butt Welds Wall Thickness C2.2:
0.5 in. or Longitudinal Less Per 1977 Weld Joints Edition of in Fittings Code Thru C2.3:
Summer 1978 Branch Addenda Pipe-to-Pipe Weld Joints Note: I ) Relief is granted with implementation of proposed alternative. The extent of examination in the Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal Systems when using the 1974 Edition Sumer 1975 Addenda of Section XI does not include the exemption criteria given in IWC-1220 relating to pipe size, Pressure & Temperature, and Chemistry control.
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TABLE 4 COMPONE;iT SUPPORTS NO RELIEF REQUESTS O
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ULTRASONIC EXAMINATION TECHNIQUE LICENSEE PROPOSED RELIEF SYSTEM OR ALTERNATIVE REQUEST COMPONENT REQUIREMENT TEST STATUS Reactor Appendix I Article 4 of Granted
- Vessel, of Section XI Section V, 1977 Pressurizer, (Paragraph Edition of Code
& Steam IWA-2232)
Thru Summer 1978 Generator Addenda i
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