ML17291B159
| ML17291B159 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/12/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17291B158 | List: |
| References | |
| NUDOCS 9512180136 | |
| Download: ML17291B159 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 AF UT N
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- 1. 0 INTRODUCTION:
The Technical Specifications for Washington Nuclear Project No.
2 (WNP-2) state that the inservice inspection of the American Society of Mechanical Engineers (AStIE) Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASHE 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}.
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 ASHE Code,Section XI., "Rules for Inservice Inspection of Nuclear Power Plant Components,'o the extent practical within the limitations of design,
- geometry, and aIaiberials of construction of the components.
The regulations requirethat 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 ASHE 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 ASHE Code for the WNP-2, second 10-year inservice inspection (ISI) interval is the 1989 Edition.
The second 10-year interval for WNP-2 began December 14,
- 1994, and ends December 13, 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'hall be submitted to the Commission in support of that determination and a request made for relief from the ASHE Code requirement.
After evaluation of the determination, pursuant to 9512i80i3b 95i2i2 PDR ADOCK 050003 7
l
the Commission may grant relief and may impose alternative requirements that are determined to be authorized bg 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 27, 1994, Washington Public Power Supply System submitted to the HRC its Second Ten-Year Interval Inservice Inspection Program Plan, Revision 0, and associated requests for relief for WNP-2.
Additional information for Revision 0 was provided by the licensee in its letter dated Hay 12, 1995.
2.0 KvVUA 0 I 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 Second Ten-Year Interval Inservice Inspection Program Plan, Revision 0, and the associated relief requests for WNP-2.
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 WNP-2 Second Ten-Year Interval Inservice Inspection Program Plan, Revision 0, with the exception of Relief Request No. 2ISI-Ol (Part 1).
Relief Request 2ISI-01 (Part
- 1) is denied because the licensee has not proposed an acceptable alternative to the required augmented examination of reactor vessel shell welds, nor has the licensee provided sufficient technical justification to justify the impracticality or burden associated with performing the augmented examination.
Additional details can be found in the staff letter to the licensee dated February 1, 1995.
3.0 CONCLUSION
Based on the information provided by the licensee, the staff has determined that, with respect to request for relief 2ISI-Ol (Part 2) for the reactor vessel head and requests for relief 2ISI-02, 2ISI-04, 2ISI-10, and 2ISI-12 for shell-to-flange welds, the testing requirements for the subject components are impractical.
Pursuant to 10 CFR 50.55a(g)(6)(i),
the staff has concluded that granting of relief is authorized by law, will not endanger life, property or the common defense and security, and is otherwise in the public interest.
The staff has determined that the proposed alternatives for requests for relief 2ISI-03, 2ISI-07, and 2ISI-14, are acceptable pursuant to 10 CFR 50.55a(a)(3)(i).
The staff has determined that, with respect to requests for relief 2ISI-05, 2ISI-06, 2ISI-08, and 2ISI-09, compliance by Washington Public Power Supply System would result in hardship or unusual difficultywithout a compensating increase in the level of quality and safety, and therefore the proposed alternatives are authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
The licensee's proposed alternative to use Code Case N-416-1 in lieu of Code requirements contained in relief request 2ISI-13 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii),
provided that an additional surface examination is performed on the root pass layer of Class 3 butt and socket welds.
Code Case N-416-1 is authorized for use until such time as the Code Case is published in
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wNP-2 Second 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Page 1 of 3 2ISI.01 (Part 1)
Reactor vessel B-A B1.11 Shell welds AB and AD Volunetr Ic examination Perform votuaetr ic exam to the extent practical Denied 2ISI-01 (Part 2)
Reactor vessel B-A B1.21 B1.22 81.30 Need and shell-to-flange welds; AE, OA, DB, OC, OD, OE, OF ~
DGg and DR Voiunetric examination Perform voluaetric exes to the extent practical Granted 2ISI.02 Reactor vessel B-0 B3.90 Nozzle-to-vessel Volunetric eximination Perform voiuimtric exam to the extent practical Granted 2ISI.03 Reactor vessel closure head nuts 8.0-1 B6.10 Nuts 36-1-1A through 36-1-76A Surface examination Voiunetric exam of the threaded areas and surface exam of the rest of the nut Authorized 2ISI.04 Service water system IIIA.5244 Buried components Flow test Verify flow and puip discharge pressure Granted 2ISI-05 Hain steam INO-5223 Piping downstream of relief valves Pneunatic test Authorized 2ISI-06 Control rod drive Flanges INA.5250 Bolting VT-3 visual examination Replace bolting every 10 year s Authorized 21SI-07 Class 1, 2, and 3 sys't ems IWA-5250 Leaking bolted connections Removal of all bolting at effected joint with a subsequent VT-3 visual examination Removal of the bolt closest to leakage source with a VT-3 visual examination Authorized
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WNP-2 Second 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Page 2 of 3
!~Relief,:::',:.':
j::Request":~
'".pSystem 'or~ "..
2ISI-OB Integrally welded attachments to Class 1
piping 8-K-1 810.10 Integrally welded attachments:
RRC-HA.1(M)
RRC-HB-1(M)
Surface examination Perform surface exam to the extent practical Authorized 21SI-09 Integrally welded attachments to Class 2
piping C C C3.20 Integrally welded attachments:
RHR 77(M)
RHR-410(M)
Surface examination Authorized 2ISI-10 Integral ly welded attachments to Class 3
piping D-B D2 ~ 20 Integrally welded attachments:
SM-90(M) ~ SM-123(M), SM.439(M)g SM-946N(M), SM.951N(M)
Surface examination Perform surface exin to the extent practical Granted 2ISI-11 Snubbers IMF.5300 Snubbers Snubber testing program To be evaluated under IST program 2ISI-12 Class 1, 2, and 3 systems IMA-4340 Meld repair when full thickness is removed and the back side of the joint is inaccessible Surface examination None Granted 2ISI-13 Class 1, 2, and 3 systems IMA-4400 Melded repairs or replacement System hydrostatic test in accordance with IMA.5000 Code Case N-416-1 Authorized conditionally
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WNP-2 Second 10-Year ISI Interval TABLE 1
SUIVlMARYOF RELlEF REQUESTS Page 3 of 3
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'!P.',Req'ulied Method;i'~,";.;
2isi 14 Class 1, 2, and 3 systems IIIA-5250 Leakage at repaired or replaced bolted connections Removal of all bolting at effected Joint with VT.3 visual examination Bolting used during repairs or replacements will receive a VT.1 visual examination prior to installation Authorized
J 0
After that time, the licensee is to follow all: the provisions in Code Case N-416-1 with limitations issued in Regulatory Guide 1.147, if any.
Relief request 2ISI-11 regarding inset.vice inspection requirements of snubbers is considered part of the inservice testing (IST)
- program, and is being evaluated separately.
Attachments:
1.
Table 1
2.
Technical Evaluation Report
- Principal Contributor:
G. B. Georgiev Date-December 12, 1995
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