ML17275B242

Forwards Matls Engineering Branch Request for Addl Info Re Facility FSAR by 811101 to Complete OL Application Review

ML17275B242
Person / Time
Site:	Columbia
Issue date:	09/08/1981
From:	Rajender Auluck Office of Nuclear Reactor Regulation
To:	Ferguson R WASHINGTON PUBLIC POWER SUPPLY SYSTEM
References
NUDOCS 8109180644
Download: ML17275B242 (10)

Text

0 Docket Ho; 50-397 Spp 8 $81 Hr. R. L. Ferguson ttanaging Director Washington Public Supply System 3000 George Washington Hay Richland, l<ashington 99352 Distribution:

(Docket-Fi-le LB82 File TERA NRC PDR Local PDR NSIC TIC ACRS (16)

DEisenhut RPurple RTedesco ASchwencer RVollmer RHartfield,MPA BElliot TMurley MService RAuluck OELD OI8E (3)

Subject:

l<HP-2 FSAR - Request for Additional Information As a result of our review of your application for operating license we find that <e need additional information regarding the WNP-2 FSAR.

lhe specific information required is as a result of the Materials Engineering Branch' review and is listed in the Enclosure.

To maintain our licensing review schedule for the WttP-2 FSAR, we will need responses to the enclosed request by November 1, 1981.

If you cannot meet ttds date, please inform us within seven days after receipt of this letter of the date you plan to submit your responses so that we may review our schedule for any necessary changes.

, ~r Please contact me, if you desire any discussion or clarification of the encl osed request.

Sincerely,

Enclosure:

As stated Onginat signed by Rajender Auluck, Project Manager Licensing Branch Ho.

2 Division of Licensing cc:

See next page 8i09180644 8i0908 PDR ADQCK 05000397','

PDR

• See previous concurrence OFFICEI SURNAM D 'R:ph DL A c cer

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Mr. R.

L. Ferguson Managing Director Washington Public Power Supply System P. 0.

Box 968 3000 George Washington Way Richland, Washington 99352 ccs:

Nicholas Reynolds, Esq.

'ebevoise 5 Liberman 1200 Seventeenth

Street, N.

W.

Washington, D. C.

20036 Richard g. guigley, Esq.

Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympis, Washington 98504 Mr. Albert D. Toth Resident Inspector/WPPSS-2 NPS c/o U.S. Nuclear Regulatory Commission P. 0.

Box 69

Richland, Washington 99352 Roger Nelson, Licensing Manager Washington Public Power Supply System P. 0.

Box 968

Richland, Washington 99352 Mr. 0.

K. Earle, Project Licensing Supervisor Burns and Roe, Incorporated 601 Williams Boulevard

Richland, Washington 99352

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ENCLOSURE 121.0 Materials Engineering Branch - Component Integrity Section 121.11 Provide data to justify that the value of -50 F used to estimate the nil ductility temperature for the beltline welds was obtained from test samples that represent the beltline welds in the WNP-2 reactor pressure vessel.

This information should include a comparison of.

the significant weld parameters (e.g.,

weld wire, flux, thermal treatment) and mechanical properties from both the sample and beltline welds.

121.12 In order to demonstrate that all reactor coolant pressure boundary (RCPB) materials comply with the requirements of Paragraph IV.A.2.a, the applicant must report the RTNDT for all ferritic (RCPB) plates,

pipes, forgings and welds outside the reactor vessel beltline region which will be limiting for operation of the reactor vessel.

If the method for determining RTNDT for these materials is different than that required by Paragraph IV.A.2.a, the applicant must identify the method and provide technical justification for its use.

121.13 Provide CVN impact data to demonstrate that all the reactor beltline materials except Girthwel d AB/E8018NM/492L4871/Lot A422B27AF1, Girthwel d AB/RACOlNM/5P6756/Lot 0342, and Girthwel d AB/E8018/04T931/

Lot A423B27AG have a minimum CVN impact test upper shelf energy of 75 ft-lb as required by Paragraph IV.B of Appendix G.

The applicant must provide additional data, information from the literature, and/or analyses to demonstrate that the materials'pper-shelf will be assured for normal operation.

The additional data should be from tests of plates having similar steelmaking practices and thermo-mechanical history.

For the we'lds, the additional data should be from similar welds, i.e., those having the same weld wire, flux, and

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thermal treatments as the beltline welds and prepared by the same fabricator as the original beltline w'elds.

121.14 To demonstrate compliance with Appendix H, 10 CFR Part 50, provide a

table that includes the following information for each surveillance material specimen:

(1)

Actual material specification; (2)

Origin of each surveillance specimen (base metal:

heat

number, plate identification number; weld metal:

weld wire, heat of

'filler material, production welding process, and plate material used to make weld specimens);

(3)

Test specimen, and type; (4)

Heat treatment of each test specimen; (5)

Chemical composition of each test specimen.'rovide the asmuthal

location, lead factor and withdrawal time for each specimen capsule.

k 121. 15 Provide the following data to demonstrate the main steam isolation valve (MSIV) RCPB materials will meet the fracture toughness requirements of NB-2332 of the Summer 1972 Addenda to the 1971 ASME Code.

(a)

Indicate the diameter and nominal wall thickness of the connecting pipes.

(b)

Indicate the material specification, material type, material

supplier, heat treatment received by the material, minimum design wall thickness and CVN impact test results for all ferritic RCPB materials used in the MSIV bodies,

covers, discs, stems and bolting.

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(c) If CVN impact data can,not be provided from each of these materials, provide CVN impact data from other materials which were fabricated from the same material specification and type, by same material supplier and heat treated to an equivalent metallographic condition as the MSIV materials.

121.16 There are six weld heats in response to g 121.2 and 121.1 whose composition cannot be found'in the list of weld metal compositions.

They are (Location/Type/Heat/Lot):

(a)

Ring 21BA/RACOlNMM/3P49U/1214 or 3PA966/1214" (b)

Ring 21BB/E8018NM/C3L46C/J020827A (c)

Ring 21BC/E8018NM/19L853/AlllA27A (d)

Ri ng 21BC/E8018NM/C3L46C/J020A27A (e)

Ring 21BD/E8018NM/C3L46C/J020A17A (f)

Ring 21BD/E8018NM/C91046/D217A27A or C4P046/D217A27A" Indicate the chemical composition (particularly the copper, phosphorus and sulfur content) of these weld metals.

121.17 Indicate which reactor vessel beltline weld metals were utilized for root passes and are within the first quarter of the weld thickness.

121.18 If the chemical composition of the weld metals in g 251.6 are not known and the weld metals are not located within the first quarter of weld thickness, utilize the upper limit curves in Regulatory Guide 1. 99 to determine the predicted adjusted reference temperature (BRTNDT)

Indicate the end of 1 ife ARTNDT for these materi al s and recalculate the pressure temperature limit curves if these weld metals become limiting during reactor vessel life.

121.19 Indicate the inside diameter and minimum wall thickness of the reactor vessel beltline.

One of these are typographical errors.

A 1'II b'