ML19329F599

Forwards Summary Status of Reg Guides Reviewed 760924 by Matls Engineering Branch & Addl Discussion of Individual Reg Guides

ML19329F599
Person / Time
Site:	Midland
Issue date:	08/17/1977
From:	Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Boyd R Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.002, RTR-REGGD-01.014, RTR-REGGD-01.031, RTR-REGGD-01.034, RTR-REGGD-01.036, RTR-REGGD-01.043, RTR-REGGD-01.044, RTR-REGGD-01.050, RTR-REGGD-01.065, RTR-REGGD-01.066, RTR-REGGD-01.071, RTR-REGGD-1.002 4097, NUDOCS 8007020754
Download: ML19329F599 (7)

Text

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,,b Consumars 90"nr y*

• Stephen H. Howell Vice President oeneral Offices: 1945 West Parnell Road. Jackson, Michigan 49201

• Area Code 517 788-0453 August 17, l' TT ,

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Director of Juclear Reactor Regulation b 22 ib '-

Attn: :h- Rocer Joyd, Lirector u'*' 7eTQncourog ,

Livision of Project I.anagement g N :. N U3 I!uclear Regulatory Cornission -

,5 Uasnington, DC 20555 /

q V,2 1.IIDLA.;D PROJ2CT I DOCJ. T ;ios 50-329, 50-330

iA'L:. RIAL 3 E:iGIL'ZRI;iG EVALUATIOi; 0F REGULATORY GUIDE POSITIO::3 FILd: 0505 S:, RIAL : 4097 Mr 3 A Varca's September 24, 1976 letter transmitted the IIRC Staff evs.lut. tion of the Consumers Pcuer Coq:any position on Regulatory Guides 1.2,1.14, J. 31 1.34, 1.36, 1.43, 1.44, 1 50, 1.65, 1.66 and 1.71 relative to the !!idland Plant.

Subsequent to your review some of our positions have changed, or require addi-tional clarification due to reinterpretation of Re6ulatory Guide contents. Also, ue wish to advise you of our intended action in those areas where the Staff's position is interpreted to be different from the Consurer's position.

Attack Ant 1 is a Sun. ary Status of each Regulatory Guide reviewed in tne Eaterials "ngineering category. Attachnents 2 thru 4 provide additional discussio1 of indi-vidual Regulatory Guides.

The attached =aterial is for inforIJ.ation only since iiRC evaluation of the final Midicad Plant Regulatory Guide positions vill be perforced during review of the Final 3afety Analysis Report which is scheduled for subnittal on September 1,1977

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_m~k 3Xii/jbg CC: Cu:ahaney, tynchturc THIS DOCUMENT CONTMNS RLCastlederry, A' POOR QUAUTY PAGES 8007020

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S120!ARY STATUS

- Regulatory Guide Comment 1.2 NRC agrees with the Midland position 1.14 See Attachment 2 1.31 NRC agrees with the Midland position -

1.34 ,

.NRC agrees with the Midland position 1.36 Midland project is complying fully 1.43 NRC agrees with the Midland position 1.44 See Attachment 3 .

1.50 NRC agrees with the Midland position 1.65 NRC agrees with the Midland position 1.66 See Attachement 4 1.71 NRC agrees with the Midland position 4

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2 Regulatory Guide 1.14 - Reactor Coolant Pump Flywheel Integrity

. (Safety Guide 14, 10/27/71)

In accordance with the suggestion expressed in the NRC staff's comments on the Midland implementation of this guide, a flywheel overspeed spin test has been conducted (at 125% of normal speed) on one of the eight Midland Unit 1 and 2 reactor coolant pump flywheels, for the purpose of providing additional assurance of flywheel integrity.

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Att chment 3 Regulatory Guide 1.44 - Control of the Use of Sensitized Stainless Steel (May 1973)

The NRC Staff evaluations contained the following statement:

"The NRC staff recommends that Positiens C.3 and C.6 of Regulatory Guide 1.44 be conformed with by B&W and Bechtel: 1) for procurement of the remaining austenitic stainless steel components of B&W and of the balance of plant, 2) for welding installation of the B&W com-ponents, and 3) for the remaining welding installation of the balance of plant components. In regard to Position C.3, nonsensitization of the material should be verified by using ASTM A262-70 or the Strauss Test whenever the materials specification does not require water quenching from the solution temperature.

In regard to position C.6, both B&W and Bechtel should perform intergranular corrosion tests for sufficient welding procedures to cover the complete ranges of the welding parameters (i.e., material thickness, etc.) that will be involved in component fabrication and installation."

The Midland project has taken the following steps to comply with Positions C.3 and C.6 for procument, under new purchase orders, issued after April 1, 1977

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of the remaining balance-of-plant austenitic stainless steel components addressed in Item 1 above, a) To comply with Position C.3, all austenitic stainless steel material for the remaining balance-of-plant components is re-quired to be cooled to below 800F in less than 3 minutes fol-lowing solution heat treatment.

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, Atttchment Con t ' d) b) To comply with Position C.6, material having a carbon content of less than 0.03% is specified for use. In cases where this is not practical qualification of the welding procedure to. ASTM A262-70 is required. -

c) No B&W components remain to be purchased, thus no action is required.

To comply with Items 2 and 3 above, Bechtel has performed intergranular corrosion tests in accordance with Position C.6, for sufficient welding procedures to cover the range of welding parameters that will be involved in field welding of stainless steel components. Welding procedures used for field welding of stainless steel safety-related components during NSS erection will be qualified in accordance with Position C.6 of the Regulatory Guide. '

One point which we wish to clarify is the degree of compliance to Regulatory Guide 1.44 for additional quanities such as valves and pipe added to existing l

purchase orders. As these additional quantities are added to established purchase orders with previously approved welding procedures, the degree of

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l compliance for these added quantities will be as described in the previously l submitted Midland position accepted for components already procured.

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sAttret'. it 4

.v Regulatory Guide 1.66 -_ Nondestructive Examination of Tubular Products The NRC Staff evaluation accepted the Midland Position for previously procurred components in the B&W and balance-of-plant scope of supply, and recommended compliance to either Regulatory Guide 1.66 or the non-destructive examination requirements of the summer 1974 addenda of ASME Section III for procurement of the remaining components.

In response to this NRC recommendation, and as required by the Code,Ithe requirements of the Summer 1974 addenda of ASME Section III and/or subsequent addenda in effect on the date of procurement of the remaining balance-of-plant tubular products have been met. As all B&W scope of supply equipment has been previously purchased, no action on B&W supplied components

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is required.

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NRC P:Ry 195 U.S. NUCt.EA3 KEGUL.ATO73v COMMISSit mat NUM89 (2-75: .. 75B - 329 / O

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, NRC DISTRIBUTION PCR PART 50 DOCKET MATERIAL / PSAR/FSAR AMDT DIST.

TO: FROM: Cart oP occuMENT Consumers Power Company 8/17/77 Mr. Roger Boyd Jackson, Michigan c4TE RECsivEo Stephen H. Howell 8/22/77 Gt.sTTaR O NOTORIZE D PRCP INPUT PORM NUMBER OF COPIES RECEIVED EDRIGIN A L. M(JNg t,A33 g p g g D Cecry , fygg OE'SCRIPTION EN CLCSU R E

/G 64)~ Q-ly Y' Attachmentr1.) ,

Summary Status of each Regulatory Guide E,.....,.

reviewed in the Materials Engineering category. o h.,....,*-s-+

Attachment 2 thru 4.)

Additional discussion of individual Regulatory Guides..

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K 1. . . . . . .' . v s C PLANT NAME:

Midland Units 1 & 2 RJL 8/22/77 (1-P) (5-P)

FOR ACTION /INFORMATION _

ASSIGNED AD: (LTR)- VD4/4 O BRANCH CHIEF: (AI' val #A A

- _*rCT . ~ Ac m i LICE?"'I'*C fr T T' I

i i i [ T INTERNAL DISTRIBUTION I ( REG TTlr LAINAS

!  ! -- .- o R IPPOLITO I I ICE (2) l F. ROSA OELD (LTR) GAMMILL (2)

P. COLLINS VOLL>ER (LTR)

HOUSTON BUNCH I i HELTEMES J. COLLINS l l CASE (LTR) 1 KREGER j

! MIPC (LTR) i KNIGHT fLTR1 BOSNAK l SIHWEIL PAWLICKI I ROSS (LTR)

NOVAK ROSZTOCZY CHECK TEDESCO (LTR) 1 BENAROYA EXTERNAL DISTRIBUTICN CONTROL NUMBER I LPDR: N //)/ A A 4 7 N/Cf/ l Q

l TIC 1 NsTC ACRS 16 CYS SENT CATEGdRY /3 I

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