ML20155E988

Forwards Rev to Attachment I of Re GDC 51, Including Feedwater Lowest Svc Metal Temp Change,Feedwater Check Valve Cover Matl Change & Replacement Feedwater Check Valve Matl Info

ML20155E988
Person / Time
Site:	Beaver Valley
Issue date:	04/11/1986
From:	Carey J DUQUESNE LIGHT CO.
To:	Harold Denton, Tam P Office of Nuclear Reactor Regulation
References
2NRC-6-036, 2NRC-6-36, NUDOCS 8604210081
Download: ML20155E988 (26)

Text

-

'Af ouquesneuct Nuclear Construction Devision

" Telecopy

==

NNP' 55 April 11, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation S UBJECT: Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 General Design Criterion 51 REFERENCE : 2NRC-3-087, dated November 14, 1983 Gentlemen: f

\

The referenced letter provided a summary of the fracture toughness _

properties of the containment pressure boundary components with respect to O General Design Criterion 51 (GDC 51). It reported a Lowest Service Metal Temperature (LSMT) value of 120*F for the feedwater system piping between the reactor containment penetration and the feedwater isolation val ve. This temparature was based on steam generator hydrostatic testing. Subsequently, it has been determined that during startup and shutdown the LSMT is 70*F.

The feedwater check value covers were the only components affected by this lower LSMT. The check valve covers have been replaced as described in the following attachments:

1.) This attachment is a revision of Attachment I of the referenced letter and includes the feedwater LSMT change and the feedwater check valve cover material change.

2.) This attachment encloses the replacement feedwater check valve cover material CMTRs, which supersede the cover material CMTR information contained in Section 13 of l Attachment II of the r>ference letter.

Compl i an ce with GDC51 has been accordingly maintained.

J 8604210001 860411 2 PDR ADOCK 0500 iI l

United States Nuclear R:gulatory Commission Mr. Peter Tam, Project Manager Grand Design Criterion 51 Page 2 DUQUESE LIGHT COMPANY By J. JMarey Vice President JJS/jdw JJS/NRC/GDC51 Att ent AR cc: Mr. P. Tam, Project Manager (w/a)

Mr. J. M. Taylor, Director (3) (w/a)

Mr. W. Troskoski, Sr. Resident Inspector (w/a)

Mr. L. Prividy, Resident Inspector (w/a)

INP0 Records Center (w/a)

NRC Document Control Desk (w/a)

S IBED AND RN T BEFORE E THIS DAY OF , 1986.,

f/J/ i 561&f Notary Public MilM N. FATTORE, NOTARY PUBUC Nf!PPl.iGPORT #7310. BEAYER COUNTY NY COWissl0*1 CP!P.iS CCT. 23,1933 H:?oer. Pensyt*L 13 ec.auen sf.;;mr g I

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Attachment I

, TECHNICAL

SUMMARY

GDC-51 BEAVER VALLEY P0iiER STATION - UNIT 2 DUQUESNE LIGHT COMPANY

1. Lowest Service Metal Temperature i The lowest service metal temperature (LSMT) for appurtenances of the containment liner, feedwater piping and valves, equipment hatch, and personnel airlock is identified as +70*F during normal operating maintenance.

The LSMT for the main steam piping and valve is 120*F. The LSMT in this evaluation applies during hot hydrostatic testing. The 120*F is a minimum value for hot hydrotest of the system and the actual test temperature would be higher to assure that the minimum is not violated.

2. Containment Pressure Boundary Materials The materials of the containment pressure boundary reviewed within the context of GDC51 were:

i a. Equipment Hatch; Personnel Airlocks Equipment hatch bolt flange, 5 1/2 in. SA 516 Gr. 60 normal-ized, is identified as a limiting material. Summer 1977 addenda of ASME Class 2 rules would assign as Tndt of O'F a'nd an LPSMT of +58'F. However, CMTR indicates that the material was DW tested to a measured NDT of -10'F, which would assign a lowest permissible service metal temperature (LPSMT) of

+48'F to the material, allowing adjustment for thickness.

Personnel airlock head ring, 5 1/2 in. SA516 Gr 70 quenched and tempered, is identified as a limiting material. CMTR indicates that the material was DW tested to a measured NDT of -10*F. Summer 1977 addenda of ASME Class 2 rules would assign an LPSMT of +48'F to the material, allowing adjustment for thickness.

b. Sleeves (1) SA 333 Gr. 6 is applied in penetration sleeves with a max wall of.0.937 in., (18 in. electrical penetration). CMTR indicates that the material was normalized and DW tested to a measured Tadt of -10'F. Summer 1977 addenda ~ of ASME Class 2 rules would assign an LPSMT of +20'F to the material.

(2) SA 155 KCF60, 1/2 in. thick, (pens. 90 and 91) is exempted from testing as the materia' is less than 5/8 in. in thickness.

I

(3) SA 537 C1. 2, 1 1/4 wall thickness (pens 73, 74, 75) is identified as a limiting material. CMTR indicates the

-material was quenched and tempered and DWT tested to a measured Tndt of -10*F. Summer 1977 addenda of ASME Class 2 rules would assign an LPSMT of +20*F to the material.

c. Flued Heads SA 508 Class 1, max axial thickness of 9 in. main steam, is identified as a limiting material. CMTR indicates that the material was normalized and quenched and tempered and DWT tested to a measured Tadt of -30*F. Summer 1977 addenda Class 2 rules would assign an LPSMT of +45*F to the material allowing adjustment for thickness.

SA 508 Class 1, max axial thickness of 7 in. feedwater, is identified as a limiting material. CMTR indicates that the material was DW tested to a measured Tndt of -40*F. Summer 1977 addenda Class 2 rules would assign an LPSMT of +27*F, allowing adjustment for thickness.

d. Process Pipe Process pipes are integral with flued head forgings in flued head penetrations.

Process pipes, penetrating and welded to liner, were reviewed

• as sleeves with max wall of .432 in.

e. Multiple Penetration Header Plate Limiting material is identified as SA 350 Gr. LF2, 2 1/4 in.

thickness. CMTR indicates that the material was quenched and tempered and DW tested to a measured Tndt of -10*F. Summer l 1977 addenda ASME Class 2 rules would assign an LPSMT of

+20*F to the material.

f. Main Steam / Main Feedwater Systems  ;

I (1) Main Steam System (MK MSS 169/170/171-1 169/170/171-3) l l

Piping: j l

SA106, 30 in. x 1.875 in, wall, by Cameron, normalized I with no CVN. NUREG 0577 Fig. B.7, given that the material normalized, would place the Tndt in that population at or below the Table 4.4 NDT of +40*F.

Summer 1977 addenda ASME Class 2 rules would assign an l LPSMT of +70*F to the material.  !

2 l

?

Fittings: (MK MSS 169/170/171-2 TYP)

Tee: SA234 WPCW, 30 in. x 1.875 in. minimum wall, applying SA106 Gr. C fittings quenched and tempered no CVN. NUREG 0577 Fig. B.7 would assign the material a Tadt in that population below +40*F (Table 4.4). Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of

+70*F to the material.

Bosses: SA105, normalized, -2 1/2 in. max thickness-typical. NUREG 0577 Table 4.4 assigns a (NDT +1.3T)NDT of -5*F. Summer 1977 Addenda ASME Class 2 rules would assign an LPSMT of +25 F.

Headers (Relief Valve) MSS 105/106/107-1 SA106 Gr C, 35.945 nominal OD x 30.000 in. minimum I.D.

l x 2.750 in, wall by Cameron, normalized. NUREG 0577

- Fig. B.7 would assign an NDT in that population at or i l

below 40*F of Table 4.4, given that the material is normalized. Summer 1977 addenda ASME Class 2 rules )

! would assign an LPSMT of +75"F, allowing adjustment for  :

thickness. .)

Header Cap:

SA234 WPC, 36 in. OD x 2.75 in. minimum wall, applying SA106 Gr.C with no CVN normalized. NURN 1577 Fig. H.7 1 would assign an NDT in thr.t population at or below +40 F l of Table 4.4. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of +75 F, allowing adjustment for thickness.

Header W/N Flanges SA105, 6 in. x 1500 lb, normalized per CMTR. NUREG 0577 Table 4.4 assigns a (NPT +1.3T) NDT of -5*F. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of i +25*F.

Main Steam Isolation Valve (HYV-101A/B/C) i Body: SA350 Gr. LF2: normalized, quenched, and tempered with a 2.28 in. minimum design thickness. NUREG 0577 Table 4.4 would assign a Todt in the population below

-28*F, given that the material was quenched and tem- j pered. Summer 1977 addenda ASME Class 2 rules would  ;

assign an LPSMT of +19*F, allow adjustment for i thickness.

Bonnet: SA350 Gr. LF2, normalized, quenched, and tempered, 6.5 in. minimum design thickness. NUREG 0577 Table 4.4 would assign a Tadt in the population below

-25*F, given that the material was quenched and 3

?, -

l tempered. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of +37*F, allowing adjustment for thickness.

Ball: Exempt -

fabricated from austenitic stainless steel Bolting: NA Reducers: Ht216492 also applied for the- bonnet, thus the reducers have the same heat treat as bon-net. The minimum design thickness is 1 7/8 in. Therefore the bonnet is limiting.

(2) Main Feedwater (105/106/107-1)

Pipe: SA106 Gr. C, 16 in. Sch. 80 (0.843 in. wall thickness) by Phoenix Steel. No heat treat nor CVN.

However, Phoenix practice (as developed from Salem 2 review) discharges pipe to cooling at or above AR 3.

Material can reasonably be characterized as normalized.

NUREG 0577, Fig. B.7 would assign the material a NDT in that population at or below the NDT of +40 F of Table 4.4. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of +70"F.

Fittings Fittings: 3/4, 1 1/2, and 2 in. X3000 lb socket weld bosses of SA105 normalized with a wall thickness less than 2 1/2 in. NUREG 0577 Table 4.4 assigns a (NDT +1.3T) NDT of -5*F.

Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of +25*F.

Feedwater Check Valve (VCW-06082V305/306/307)

Body: SA 216 Gr WCB, 1.094 in. minimum wall design thickness, normalized, and tempered. NUREG 0577 Fig. B.2 data would locate the Tndt of the material in the population at or below the Table 4.4 NDT of +35*F, taking into account the size effort. Summer 1977 addenda, ASME Class 2 rules would assign an LPSMT of +65 F.

Disc: SA 216 Grade WCB,- less than 2 1/2 thick, normalized and tempered. LPSMT same as as check valve body.

Cover: SA 516 Gr. 70, 3 1/2 in.^ thick,. normalized.

CMTR indicates that the material was normalized and DWT tested to a measured Tndt 4

of -10'F. Summer 1977 Addenda, ASME Class 2 rules would assign an LPMST of +35'F, allowing adjustment for thickness.

Bolts and Nuts: The bolts and nuts used in assembly of the check valve are SA-193 B7 and SA-194 2H respectively. NUREG 0577 Table 4.6 cate-gorizes the material. as having the least susceptibility to brittle fracture.

Feedwater Islation Valve (2FWS-HYV157 A/B/C)

Body: SA 105, 22.1/2 in. dia x 1.008 in. wall, normalized. NUREG 0577 Table 4.4 assigns a (NDT +1.3T) NDT of -5*F. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of

+25'F.

Bonnet: SA 105, 2.935 in. in thickness, normalized.

NUREG 0577 Table 4.4 assigns a (NDT +1.3T)'

NDT of -5'F. Summer 1977 addenda ASME Class 2 rules would assign an LPSMT of +35 F, allowing adjustment for thickness.

Neck: SA 105, 1.015 in. in thickness, normalized.

NUREG 0577 Table 4.4 assigns a (NDT +1.3T)

NDT of -5'F. Summer 1977 . addenda ASME Class 2 rules would assign an LPMST of +25'F.

Retainer: SA 105, less than 2 1/2 in. in thickness, normalized. NUREG 0577 Table 4.4 assigns a (NDT +1.3T) NDT of -5*F. Summer 1977 addenda ASME Class 2 rules'would assign an LPSMT of

+25 F.

Gate: SA 351 Gr. CF8M, 10 in. x 1500 lb gate, casting. This is an austenitic stainless steel material and exempt from testing.

I I

5

• 'I PROJECT: Beaver Valley Power St'azion - Unit No. 2 p, f GDC-51 Fracture Prevention of Containment Pressure Boundary (Criterion SI)

Component Item Thick. Heat Impact Nureg NgTT LRMST Lg!ST System (In) (In) Material Treatment Type 0577 ( F) (*F) ( F)

.See Note Equip. Bolt SI SA 516 DWT Hatch Flange GR 60 Normalized -10 F NA -10 +70 l +48 Personnel Head 5% SA 516 Quenched DE NA -10 +48 +70 Air Lock Ring GR 70 Tempered -10 F

~

Sleeves Elect. 0.937 SA 333 Normalized NA -10 +20 +70 Pent. GR 6 DWT,F

-10 18 ".

Pen 90 0.500 SA 155 Exempt -

less than 5/8" wall hickness

& 9i KCF 60 i Pen.73 2I SA 537 Quenched & NA -10 +20 +70-74.75 CL 2 Tempered DWT,F

-10 j ,

Flued Main 9(axial: SA SOS Wormalized DWT NA -30 +45 +70 Heads Steam CL 1 Quenched -$0 F Tempered Feed 7(axial: SA 508 Normalized DW NA -40 +17 +70 Water CL I Quenched -40 F Tempered Process Integ2 al with flued l' ends -

see flued h tads Welded 0.432 (See Ele ctrical Per etracio s for l imitin g Case:

221tiple Herdnr 2% SA 350 Quenched DW NA -10 +20 +70 Penetration PliAs GR LF2 Tempered -;10 F Main Piping 1.875 SA 106 Normalized NA Fig.B.7 +40 +70 Steam GR C Table 4.J'

+120 6 i Tee 1.875 SA 234 Quenched NA Fig.B.7 +40 l +70 l

, Fitting WPCW Tempered Tbl.4.4 l +120 t- i Boss 2% Max. SA 105 Normalized NA iTbl.4.4 -5 +25' I

Fitting

+120 9

-- , ,m, ,=g- ,. - --,-eg,~ ,-e ,, -.>w ,,,--,-----,,.~-w-.--..- , , - , - - - , , , , , - - - . - - - , , , - -,--,,e,ew,.wn,--, - - , , - , - , - . - , - o- , ,---n-,

PROJECT: Beaver Valley Power Station - Unit No. 2 p,g, 7 GDC-51 Fracture Prevention of Containment Pressure Boundary (Criterion 51) s Component Item Thick. Heat Impact Nureg 5]TT L{MST LgST System (In) (In) Material Treatment Type 0577 ( F) ( F) ( F)

See Note Main Header 2.75 SA 106 Normalized NA Fig.B.7 +40 +75

[ Relief GR. C - Tb1 4.4 Stesa y,gy ) .

+120 (Cont)

Header 2.75 SA 234 Normalized NA Fig.B.7 +40 +75 l Tb1 4.4 *120 Cap WPC l

Header 3.25 SA 105 Normalized NA Tbl4.4 -5 +3n i Weld

)

Neck l Flange +120 l l

1 Isola- 2.28 SA 350 Normalized NA [bl 4.4 -28 +19 l tion GR. LF2 Quenched +;20. i Valve reapered Body Isola- 6.5 SA 350 Normalized NA Tb1 ,4.4 -25 +37 tion GR LF2 Quenched + 120 Bonnet Tempered Isola-tion Exampt -

faliricated from auste mitic s tainle ss stee l valve Ball Isola-1 7/8 Same r eat as bont et, the re f o fe bonnet is limiting

. tion i Valve +120 Reduc- -

ers Main Feed "

Water Piping 0.843 SA 106 Normalized NA Fig.B.7 +40 +70 *70 GR. C. Tbl4.4

_ _ . - - . _ . , , _ .- , , , . . _ . , , - - . , - , - - . - _ - . - . - , - . ~ . - . . . . . - - . - . .

l PROJECT: Beaver Valley Power Station - Unit No. 2 p, g l i

l GDC-51 Fracture Prevention of Containment Pressure Boundary (Criterion 51)

~ \

i Thick. Hest Impact Nureg 'J ST Component Item (In) (In) Material Treatment 8 Type 0577 NgTT

( F)

L{MST

( F) (j F)

System

- I -.

1 Main Feed"Fitt ; 2% sax. SA 105 Normali' zed NA Tbl4.4 -5 +25 + 70 Water ings l

Check 1.094 SA 216 Normalized NA Fig.B.2 +35 +65 Valve GR WCB Tempered Tbl4.4 ' 70 Body Check 2% sax SA 216 Normalized NA Fig.B.2 +35 +65 Valve GR 70 Ibl4.4 +70 Disc i Check 3% sax. SA 516 Normalized DWT -0 +35 +70 NA Valve GR 70 -10*F _

Cover O

i Tbl4.0 Least Husceptibity Check 1 3/8 SA 193 NA NA j valve max. B7 to Fai: .ure -

i Bolts SA 194 j 4 Nuts 2H j i

l Isola- 1.008- Sa 105 Normalized NA Tbl4.4 -5 +25 j J tion Body +70 Isola- 2.935 SA 105 Normalised NA Tbl4.4 -5 +35 tion Valve Bonnet '70 Isola- 1.015 SA 105 Normalized NA Tbl4.4 -5 +25 tion +70 Neck l

' \

Isola- Less SA 105 Normalized NA Tbl4.4 -5 '

+25 i

, tion than +O s

(' valve 2%  !

L' Re tain-. I er

- - - - - - . - , , ., ,. ,- - , , . , . . - _ . , . . , , - ,-,,- - .-m.. . - . - . , -

-e--,-, . . . ,

PROJECT: Beaver Valley Power Station - Unit No. 2 p,g, 9 )

GDC-51 Fracture Prevention of Containment Pressure Boundary (Criterion 51)

.. m __

1

~

Component Item Thick. Heat I= pact Nureg NgTT LjMST ' UjST System (In) (In) Material Treatment Type 0577 ( F) ( F) ( :)

Main Isola- SA 351 Exempt - Stainle ss Mate rial Feedwater tion GR CF8M j 7alve Gate l

. l 1

l 1

l 1

i Note 1 The 120 F for the main steam is a minimum for hot hydrotest of the system and the actual temperature would be higher to assure that the minimr.s is not violated.

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ATTACHMENT II i

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I CMTRs

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FOR l REPLACEMENT i

FEEDWATER CHECK VALVE C0 VERS l

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• VALVE ANC FLOW CCNTACL ECuiPVENT SX!OAUSTS

, PCWER PLANT, CfL & GAS INCUSTRY & INCUSTR'Ai SERVCZ M ADV00DsMORRILLCO INC.

OEStoNERS AND MANUPACTURERS SINcE 1900 dlx .

285 CANAL STREET SALEM. MASSACHUSETTS 01970 617 744-5690 TELEX 94-0299 TNX 710 347-C220 September 30, 1985

, Mr. Karl Luuri 245/8 STONE & WEBSTER ENGINEERING CORP.

P.O. Box 2325 Boston, MA 02107

Subject:

Drop Weight Testing for Covers S&W P.O. 12241-2BV-20 A&M 24169-01 Dear Mr. Luuri; Please find enclosed a corrected documentation package for the above referenced parts. The package has been ammended to include Drop Weight

. Testing as required by your specification.

i' Should you need more assistance please contact me directly.

Very truly yours,

%. ( Qt w -

ATWOOD & MORRILL CO., INC.

I l I

Alan C. Smith Ouality Assurance R

A ACS/mf

, 7_,, _ , __

FORM N.2 N OR NPT CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES' As Required by the Provisions of the ASME Code, Section lit Division 1 Not To Exceed One Day's Production Po_ L_of 1

1. Manufactured and certmed my Atwood & MorriII Co.,Inc. 295 Canai Sereet, sa1em, Ma. 01970

- eae esnee. . e.w e.e a

2. Manufactured fo, Stone & Webster Corp. P.O. Box 2325e Boston, Ma. 02107 e ee ese seemse . e.i

3. Location of instalianon Beaver Valley Power Station- Unit No. 2 Shlopin gert, Pa.

Ingme cae es.eest a typ, 23997-C Rev.1 SA516-Gr.70 70,500 PSI N/A lo84 e,=. ,aso es.e .. =a e - .cah. .ee, e e

5. ASME Code. Section lu. 1974 Sumrner-74 2 N/A is.ee= essee ee. =ican oea ceae ae

6. Fabncated in accordance vnth Const. Spec. (Div. 2 only) N/A -

Revision N/A n ate N/A'

7. Remarks: Ref. A&M Soare Parts Reolacement Covers for orter Order No. 2h16o-01 A&M S.O. 11540-01 For 16" 600 lb.

Check Valves per Design & Spec.

2BVS-20 Add. 2 dated 12-114-31

8. Nom. thschnesa (in.) N/A Min. design theckness (in.) N/A Dia.10 (ft. & in.) N/A Length overall(ft. & in.) N/A

9. When applicable. Certificate Hoeders' data reports are attached for each item of this report:

Part or Appurterance National Part or Appurtenance National j Senal Num0er Soard No. Serial Number Board Number l In Numerical Order in Numencal Order (1) Heae Na. N/A (26)

(2) 901900h00 't10Cli6 (27)

(3) (28)

(4) S/N 1 (29)

(5) t/M ? (30)

(6) t/M 1 (31)

(7) (32)

(8) (33)

(9) (34)

(1 01 (35)

(11) (36)

(12) (37)

(13) (38)

(14) (39) l (15) (40)

(16) (41)

(17) (42)

(18) (43)

(19) (44)

(20) (45)

(21) (46)

(22) (47)

(23) (48)

(24) (49)

(25) (50)

10. Design pressure N/A ps: Temp. N/A oF. HWro. test pressure 2200 PSI ,, ,,,,, o p,

_ _ _ msorseeteens asesemeeererome.seseesesesseeseueneetImeese t'1 e t1.(2) _ _ _ enmessee2 ene 3 enseeseesmseenenseeseneeensheetE31 esse enene se _ ene numeer es eheses as eseeseos es eso of the lesse, ene i49 esem sheet shee es e.gnes De the C _ _ see.ser one the ANI.

(e/o31 the essen 40 00406 mise se seem the oeeer Gees AsesE. 349 s. 4hh se . New Test. N Y. teet?

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ATWO O D & M 0 R R I LL CO., INC. 0"dd Y **

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CERTIFICATE OF COMPLIANCE Date n.r..s., 16 togh Customer Stone & Webster Engineering Corp.

Customer P.Ot Number 12241-2W-20

• MM S.O. Number 24169

Description:

Item 01 (3) Covers Heat / Serial No. 801809490-B30546 S/N 1

• 5/N 2

5/N 3

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I We hereby certify that the product described above, shipped i against the subject order, conforms to all specifications and instructions in the contract to the best of our knowledge and belief.

u, . Customer ,

J n .ove F f\ cc: w/ shipment

M .a er of Ctfality Assurance Order File 24169 g a p N - > r- 7/y 4 ,

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<4 ATWOODoMORRILLCO INC.

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. 205 CANAL STREET SALEM, MASSACHUSETTS 01970. PHONE 617 744 5690 TELEX 94-0299 MATERIAL CERTIFICATI0tl STATEMENT

.A&M Sales order N N 'DI , BTSScl60GyctC-630f4fp Part COVERS Identification NN b' I-2-3 Atwood s Morrill Co., Inc. certifies that the above materials meet or exceed the requirements of the ID Edition, D mdttR h Addenda of the ASME Code.

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4 cour.8s M /49-61 MILLS ALLOY STEEL COMPANY CERTIFICATE Twinsbu,s. oh;o 44o87 OF CONFORMANCE CUSTCMER Atwood & Morrill Company DATE 11/16/84 285 Cans 1 Screec Salaz ,MA 01970 OUR ORDER NO. 36612-N YOUR ORDER NO. E'J 97E, ITEM ITEM DESCRI.' TION ,

H EAT NUMB ER [

**,[*** ,',,*e*$,3 l ASMI SA-516 Grade 70 carbon sceal plate l

l 1 3 pes. A x 24-1/2 CD 8013094S0-330546 arrear or i

I /ApoROVED 7 % \ emirucAL & PHYSIC.H.

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l io Date IMIIIh 3 DATE /2-72 aY l 0 '

l <. ag C.s ATWOOD & MOAfL1LL CO. W t

This is to Certify that the matenal furr%sned for your order and Cescr:Ded aoove. complies to thw recutements c.

the apoticacie material specifications, as reported on the attached copies of the manuf acturer's certifiec material

• test reocris, and meets ail requirements of your purchase order.

irms foLLowneG AMtv A5 mecicAffoi =

i O This is to certify that tne material sucched for your order conforms to the recuirements of specificaoon;

& TP s is to certity tnat the material furrushed for your order was sucolied in accorcance with our ident.fication and verification program per the cuality requirements of ASME Section lit. Division 1. Sucarticle NCA Subsection 3800/NW3700%nd NC Class comoties ' .to 1983 the apo44catie Edition 'dinter. requirements.or L95 of ASME as scegified_3 Section 114 Addenca.

C This is to certify that repair by welding was not performed on the material cascrioed aoove.

O This is to certify that to the best of our knowledge this material, durmg the manuf acturing processes, tests and inspections. has not come into direct contact with toercury or any of its compouncs nor with any mercury containing devices employing a singte boundary of containment.

O This is to certify that your order was furnished in accoroance with the following specifications andict procedures: .

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MILLS ALLOY STEE rCOMPANY ASME QUAUTY SYSTEM CERTIFICATE

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• Ad (Materials) #CSC.324 8Y _C" Espires March 24.1987 p -

Lisa Reich -Documentation Secretary roamiasn a m

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<aset in., A. in-tti h[ BETHLEHEM $ TEEL CCRPCRATION mtTALLutGiCAL CEPAttMENT [](( ,  %.

@E SURNS HARaC' PLANT REPORT OF TESTS AND ANALYSES w.a == . c c. ci. .,

803-16377 9-16-84 XAPLAN TRLH J PAGE 1 )

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[ HMJimenez RJSwiderski (Fid Acct)

JLKoepfinger RCoupland JGProven WGLogan RRhein(ene) CSS 470/4 RCSchopper JFZagorski(ene) (44-12241-4460)

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Mr. R. J. Washabaugh ( ,. November 3, 1983 BV-2 Project Manager s Duquesne Light Company J.O.No. 12241 Robinson Plaza Bldg. No. 2 2DLS- 19156 Suite 210 LR8311030003 PA Route 60 Pittsburgh, PA 15205 BEAVER VALLEY POWER STATION - UNIT NO. 2 J.O.NO. 12241-0.F.E.NO. 10080-C.O.NO. 6289 FRACTURE PREVENTION OF CONTAINMENT BOUNDARY GDC-51 Attached is a summary of the fracture toughness properties of the contain-f ment boundary in accordance with General Design Criterion 51 (GDC-51). The g materials forming the BVPS-2 containment pressure boundary meet the requir,e-ments of GDC-51, Fracture Prevention of Containment Pressure Boundary.

It should be noted that the lowest permissible service metal temperature of the cover for the feedwater check valve is 122*F, whereas the lowest system service metal temperature is 120*F. We believe this is acceptable, as the 120*F is a minimum temperature for hot hydrotest of the system and under normal test conditions would be higher to assure the minimum is not violated.

The criteria used to determine the lowest permissible service metal tempera-ture (LPSMT) values of the pressure boundary components are more stringent than those committed to by the BVPS-2 FSAR.

l These criteria are: j

1. The use of the Class 2 acceptance criteria from the summer 1977 addenda of the ASME code Section III. The code in effect for BVPS-2 is the ASME code, Division I,Section III, 1971 edition through and including the winter 1972 addenda which does not impose impacts criteria on the piping system, neither Charpy V-notch (CVN) nor Drop Weight Tests (DVr).

2. The use of the criteria in NUREG-0577 for determining the LPSMT is in lieu of the Charpy V-notch (CVN) data enclosed on the Certified Mill Test Reports (CMTR). The CVN data was not used due to Mr.

Halapatz's (of the NRC) opinion that CVN data does not represent a true Nil Ductility Transition Temperature (NDTT). The opinion I

l 1

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. $YONE s *EESTEa ENG% Eta NG C0asomarcs RJW 2 f-is based on a number of reports which document a wide range of CVN data for similar materials. Drop Weight Test data is used where available.

The summary of the properties for the materials, heat treatment methods,

'LPSMT, and the lowest service metal temperature are enclosed in Attach-ment I. Attachment II encloses the CMTRs for the information of Attach-ment I.

After your review of this material, we would be ready for a final review meeting with Mr. J. Halapatz of NRC.

Should you have any questions, please contact our P. W. Ward at (617) 589-5413.

t JW P. RaySircar "-

Project Engkneer Enclosures PW: es

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RCoupland JGProven WGLogan RRhein CSS 470/3(B4-12241-5846)

RCSchopper JFZagorski HMKrafft FSalmon ACMcIntyre-2/SEG PCTalbot JEWalsh LRicci/PE Bk Waters JENiland DWDenning-3 GMHughes BCKuechler General Files LFirestone-Ohio Ed. JSutton MLynch PM JJCarey N Mr. R. J. Washabaugh BV-2 Project Manager June 28,1984 Duquesne Light Company J.0.No. 12241 Robinson Plas:a Bldg. No. 2 ,

2DLS-21934 Suite 210 LR840(280004 PA Route 60 Pittsburgh, PA 15205 BEAVER VALLEY P0FER STATION - UNIT NO. 2 J.O.NO. 12241-0.F.E.NO. 10080-C.O.NO. 6289 FRACTURE PREVENTION OF CONTAINMENT BOUNDARY GDC-51

Reference:

SWEC letter 2DLS-19156 dated November 3,1983

\

The referenced letter stated that the BVPS-2 reactor containment pressure boundary materials met the requirements of 10CFR50, Appendix A, GDC-51.

l' This conclusion with respect to the feedwater system materials was based on the lowest service temperature of 120*F required for hydrotesting the steam generator. However, it has been subsequently determined that lower temperatures are expected during startup and shutdown.

A new lowest service temperature of 70*F is anticipated for the feedwater system between the reactor containment penetration and the feedwater iso-lation valve. This portion of the system includes two short lengths of pipe, a check valve, and the isolation valve.

The component with associated lowest permissible metal service temperatures (LPMST) determined in accordance with NUREG 0800, SRP-6.2.7, affected by the lower service metal temperature is the feedwater check valve cover. The existing covers are SA-515 Grade 70 with a LPMST of 122*F. The covers will be replaced with the following cost and schedule:

Three check valve covers at $1,750 each for a total of $5,250. Delivery 10-12 weeks after receipt of order. The covers will h.ve material drop

, weight tested to ensure a NDT of -10*F and LPMST of 45'F.

The plant systems can be operated to maintain a 70*F minimum operating temperature. These operating (rocedures will support a revised position on GDC-51 that, due to material repTatement, a lowest metal service temperature of 70*F for the main feedwater system components included in the reactor containment pressure boundary will be acceptable.

-e g, s7ONE & WEBSTE2 ENGINEERING COWoAATICN RJW 2 f~

A revision to the report, submitted by the referenced letter, will be for-warded upon receipt of material documentation for the feedwater check valve r replacement covers.

The cost of the replacement materials is included in Revised Estimate No. 7.

i i Nh ~

P. RaySircar

! Project EnSneer PW:cs

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