ML17275B237

Forwards Info Documenting Conformance W/Positions in NUREG- 0313, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping, in Response to NRC 780306 Request

ML17275B237
Person / Time
Site:	Columbia
Issue date:	06/26/1978
From:	Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML17275B236	List: ML17275B235 ML17275B237
References
RTR-NUREG-0313, RTR-NUREG-313 GO2-78-164, NUDOCS 8109150483
Download: ML17275B237 (48)

Text

..

THIS LETTF 8 SATISFIES COMMITMENTNO.

~)AT A~h?A Diss TR I BUTION THIS LETTE R QQg) )DOES, NOT) ESTABLISH A N E'1V COMMITh1ENT.

RG Cockrel 1 WPPSS coRREsPQNoENCE No.

WGonn G02 1 64 Holder June 26, 1 978 Kohl er AH Kug 1 er g)~t No. 50-397 DL Renberger/1 b GC Sorensen DC Timmingr. S. A. Varga, Chief E Trapp Light Water Reactor Branch Ho. 4

~ >> Vaug".n Di vi si on of'roj ect Management Docket Fi" EU S. Nuclear Regul atory Commission

~

WHP-2 Fi 1 ~shi ng ton, D. C. 20555 Com Control DCT/ 1 b .

Subject:

WPPSS NUCLEAR PRO J ECT HO.'

USE OF AUGTENITIC STAINLESS STEEI.

CH McG i 1 ton to r~

Stand,

Reference:

1 ) Letter, G I 2-78-1 08, SA Var ga HO same subject, dated March 6,.~78

2) Letter, G02-78-1 06, DL Ren5e~r',to SA Yarga, same subject, dated.Birch CT; l.978

~

Q ~ ~ J Dear hlr. Varga (1) requested i nformati~ocumenti ng our conformance

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Your reference -

~

with positions s~e in NUREG-031 3, "Technical Report on Material

~

Sel ection . and Proc ss~ng Gui del i nes for BWR Coolant Pressure Boundary

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Pi pi ng" . Accords qg y~ forty copi es of the requested i nformation i s

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~

~

~

de~ attachheAt~ for your revi ew and use. Thi s satisfies

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provi our commit&eat to ylsu mMe in reference (2) .

r 'i x i <~: . Very truly yours, D. L . RENBERGER Assi stant Di rector Genera ti on and Technology DLR: DCT/ 0 YE: cph

Attachment:

As stated cc: I Li ttman, -

~ WPPSS -. NY J ~ El 1 wanger, B&R E ~ Chang, GE FA MacLean, GE J J Verderber, B&R n Dn ss RDh i 50483 8 1 0{II02 ADOCK 050003{3)7 PDR Au-sHOR: DC TimrOi nS/OK Ea FCR slGNATURE oF: DL Renberger SECTION FOR APPRovAL QF I AN Kug 1 er lWG C n GC Sorensen )

JE Ho der l CH IcG> ton I y

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.Conformance of WNP-2 to Positions in NUREG-0313 WNP-2 austenitic stainless steel pipe and fittings (Type 304) to which NUREG-0313 applies consist of the following:

I o the reactor recirculation (RRC) system loops, o the residual heat removal (RHR) system shutdown cooling suction and return lines from the RRC system loops to the inner containment isolation valve or check=valves, and o the RRC'to reactor water cleanup system interties.

Conformance to Parts II and III of NUREG-0313 is as follows:

Part II.l Pipe and fittings conforming to the corrosion resistant guidelines in this part are the twelve (12) inch RRC return lines and the RRC bypass stubs. These components as-installed, with the exception of field welds, are in the solution annealed condition.

Part II.2 Field welds associated with the return lines and the stubs referred to above included corrosion resistant

' cladding,- 308 material with a maximum carbon content of 0.028/ arid a minimum ferrite content of 8%,, and standard 308 weld filler metal with a minimum of 8%

ferrite. The weld preparation after cladding allowed only the cladding material to form the weld on the interior diameter, i.e., no material which may have become sensitized by the field weld and comes in con-.

tact with the reactor coolant has a carbon content greater than 0.0285.

Part I I I. 1 See .Fiarts II.1 and II.2 above for piping which con-forms to Part II. The nonconforming RRC system piping is already installed. The nonconforming RHR system piping is presently being installed and scheduled for completion in September, 1978. As can be seen, WNP-2 conforms to Part II of NUREG-0313 to the extent practicable when considering schedule and the .status of plant construction.

Attachment I Page 2 of 3 Part III.2.A (1) The nonconforming, not seevi ce sensi ti ve, 1 ines will be initially examined in accordance with ASNE Section XI, Subsection IWB, at not more than 80'onths after beginning commercial operation. The lines affected by this time interval are the RRC loops, excluding the twelve (12) inch return lines which conform to Parts II.l and II.2.

Part III.2.A (2) The reactor coolant leakage detection system is described in the FSAR in Sections 5.2.5 and 7.6.1.4.

Part III.2.A (2a) The compliance with Reg. Guide 1.45 is discussed in Appendix C.2, pp C.2-39 through C.2-41 of the t

FSAR.

Part III.2.A (2b) WHP-2 currently plans to comply with the BWR 5 Stan-dard Technical Specification in this area as docu-mented in NUREG-0123, Rev. 1, April 1, 1978, if practicable. These specifications reflect compliance

'with the position.

Part III.2.A (2c) WNP-2 concurs with the definition of unidenti-fied leakage. With respect to this and the current Rev. 1 of HUREG-0123, it should be noted that the drywell floor drain flow monitoring system does collect leakage from the drywell dia-phragm f'loor seals. This leakage is not expected to be significant, however, and thus the floor drain system meets the intent of being the Pri-mary Containment air cooler condensate flow rate monitoring system as stated in NUREG-0123.

Part III.2.B The nonconforming, service sensitive, lines will be examined on a sampling basis (WNP-2 does not have RRC bypass lines) for three successive inspec-tions, not exceeding the time duration between each of the first three refueling outages. Other con-venient plant shutdowns may be used during this period for, one or more of the examinations. The lines affected by this inspection interval are the austenitic stainless steel RHR shutdown cooling suction and return lines an) the stagnated, short pipe spools that are associated with the RRC loops.

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Page 3 of 3 The reactor core spray piping is carbon steel and the RRC bypass stubs,. as previously discussed, conform to Part II and therefore are not subject to this part: In the event no unacceptable indications are found in the three successive inspections for the service sensitive lines, the inspection interval shall revert to an 80 month period.

fl APPENDIX C Inservice Inspection Drawings for RRC and RHR Systems ix pp~

1 h

04 I)0 NOTCSI

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