ML20151Y254

Safety Evaluation Re Requests for Relief from Inservice Insp Requirements.Relief Not Granted for Surface & Volumetric Exam of Drywell Piping Spray Welds Since Requirements Not Impractical

ML20151Y254
Person / Time
Site:	Cooper
Issue date:	01/27/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151Y247	List: ML20151Y243 ML20151Y254 ML20151Y280
References
TAC-54588, NUDOCS 8602120633
Download: ML20151Y254 (8)

Text

_ - _ _ _ _ .- __ _._._- .

~/ UNITED STATES

~%o NUCLEAR REGULATORY COMMISSION I wasHWGTON, D. C. 20665 i

\...../

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RE0 VESTS FOR-RELIEF FROM INSERVICE INSPECTION REQUIREMENTS NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298

1.0 INTRODUCTION

Technical Specification 4.6G for the Cooper Nuclear Station states 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. Certain requirements of later editions and addenda of Section XI are impractical to perform on older plants because of the plants' design, component geometry, and materials of construction. Thus, 10 CFR 50.55a(g)(6)(1) authorizes the Commission to grant relief from those requirements upon making the

-necessary findings.

By letters dated March 1, 1984, and March 15, 1985, Nebraska Public Power District submitted its inservice inspection program, revisions, or additional information related to requests for relief from certain Code requirements determined to be impractical to perform on the Cooper Nuclear Station 1 during the inspection interval. The program is based on the requirements of the 1980 Edition through Winter 1981 Addenda of Sections IX of the ASME Code, and remains in effect until July 1,1994 unless the program is modified or changed prior to the interval end date.  ;

2.0 EVALUATION Requests for relief from the requirements of Section XI have been reviewed by

/ the Staff's contractor, Science Applications International Corporation. The i

contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the Technical Evaluation Report (TER) attached. The staff has reviewed the TER and concurs with the evaluations and recommendations. A summary of the determinations made by the staff is presented in the following tables:

m 0602120633 860127 PDR ADOCK 05000290 G ' PDR W

C___ ___._.___.__m________m_ -_m_

i TABLE 1 i CLASS 1 COMPONENTS l .

LICENSEE i

1 PROPOSED SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST

! IWB-2500-1 IWB-2500-1 STATUS COMPONENT EXAMINED METHOD EXAMINATION 1 ITEM NO. EXAM. CAT.

Reactor Shell Welds Volumetric Visual During Granted Bl.11, B-A System Provided 81.12, Vessel and Head Welds (See Hydrostatic Volumetric ,

B1.21, & Test is Performed 81.22 Attachment I i

to Table 1) to Extent

! Practical,

! Volumetric i of Additional .

Shell Welds 1

, to Achieve ,

Total Code- A' i Required l

Weld Length, and Visual of Beltline Region Weld

! Areas From j Vessel Interior (No

! Relief Required i for Welds 1M 1,

! VCB-BB-1 and -3, l and VCL-BB-1,-2, and -3) l l

i 4

TABLE l' ,

CLASS 1 COMPONENTS (continued)

LICENSEE l

PROPOSED l

IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST i EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS i ITEM NO.

l B3.100 B-D Reactor Nozzle Inside Volumetric Surface Granted Vessel Radius Section (Nozzles: Head Spray Nozzle N6A, Instrumentation Nozzle N68, and Head Vent Nozzle N7)

B9.11 B-J Contain- Pipe Size > 4 Surface and Visual for Granted i in., Circui- Volumetric Leakage During Provided Y' ment Pene-tration ferential System Surface Assembly Welds (See Hydrostatic and Volu-Attachment Test metric of II to Table 1) First Accessi-ble Pressure Boundary Weld Either Upstream or Downstream of Inaccessible Weld Over 100%

of Its Length, if Practical.

6- .

TABLE 1 l ATTACHMENT I 1

IWB-2500-1 WELD WELD TYPE ITEM NO. COPMENTS l

HMB-BB-1 Botton Head Meridional Bl.22 HIE-BB-2 Botton Head Meridional Bl.22

! HMB-BB-3 Botton Head Meridional Bl.22 -

HMB-BB-4 Botton Head Meridional Bl.22 i 198-BB-5 Bottom Head Meridional Bl.22 HMB-BB-6 Botton Head Meridional Bl.22 M)-BB-1 Bottom Head Circumferential Bl.21 VCB-BA-2 Circumferential Shell Bl.11 Beltline l VCB-BB-1 Circumferential Shell Bl.11 i VCB-BB-3 Circumferential Shell B1.11 VLA-BA-1 Longitudinal Shell Bl.12 Beltline VLA-BA-2 Longitudinal Shell Bl.12 Beltline VLA-BA-3 Longitudinal Shell Bl.12 Beltline .

VLB-BA-1 Longitudinal Shell Bl.12 Beltline VLB-BA-2 Longitudinal Shell Bl.12 Beltline VLB-BA-3 Longitudinal Shell B1.12 Beltline l VLC-BB-1 Longitudinal Shell Bl.12 VLC-BB-2 Longitudinal Shell Bl.12 VLC-BB-3 Longitudinal Shell Bl.12 l

l

l s .

TABLE 1 '"

ATTACIMENT II ,

DESCRIPTION INACCESSIBLE WELD Core Spray Loop A CSA-BJ-25 Core Spray Loop B CSB-BJ-25 Reactor Water Cleanup CWA-BJ-27A Feedwater Loop A FWA-BJ-35 Feedwater Loop B FWD-BJ-34 Main Steam Loop A MSA-BJ-43 Main Steam Loop B MSB-BJ-39 Main Steam Loop C MSC-BJ-43 Main Steam Loop D MSD-BJ-47 HPCI Steam PSA-BJ-22 RHR 20-In Supply RHA-BJ-30A 4 e

l RHR Loop A RHB-BJ-28A RHR Loop B RHC-BJ-24 l RHR 6-Inch Head Spray RHO-BJ-31 j RCIC Steam RSA-BJ-13A l

I w -

TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2500-1 IWC-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METH00 EXANINATION STATUS l C1.30 C-A Residual Tubesheet- Volumetric Visual During Granted l

Heat to-Shell System Leakage

! Removal Weld . Test l Heat (Welds i Exchanger RHR-CA-5A I and RHR-CA-l 58) l C5.10 & C5.20 C-F Residual C5.10: C5.10: Visual During Not Granted '

l Heat Pipe Welds < Surface System l Removal 1/2 in. Walt C5.20: Pneumatic &' .

Drywell Thickness Surface Test Spray C5.20: and System Pipe Welds > Volumetric 1/2 in. Wall Thickness C5.11 C-F Floor Pipe Welds < Surface Visual During Granted Penetration 1/2 in. Walt . System Thickness, Hydrostatic Circumferential Test Weld (Weld RHD-CF-9) r w

TABLE 3 CLASS 3 COMPONENTS NO RELIEF REQUESTS l

r TABLE 4 l COMP 0flENT SUPPORTS

! NO RELIEF REQUESTS Y

i I

\

TABLE 5 l

PRESSURE TESTS NO RELIEF REQUESTS i

l _ _ _ _ _ ___ _ _ . - - -. - _

l l

3.0 CONCLUSION

Based on the review summarized above, the staff concludes that the relief granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity, that granting relief where the Code requirements are impractical is authorized by 10 CFR 50.55a(g)(b)(1) and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering t

the burden that could result if they were imposed on the facility. The relief not granted, for surface and volumetric examination of drywell spray piping welds is denied on the basis that the licensee has not shown the requirements to be impractical. Relief is therefore not authorized by 10CFR50.55a(g)(6)(1).

Attachment:

" Technical Evaluation Report, Second Interval Inservice Inspection Program, Cooper Nuclear Station" Report No.

SAIC - 84/1660, September 1985.

Principal Contributor: G. Johnson /S. Lee Dated: January 27, 1986 ,

l 1

l l