ML18025A629
| ML18025A629 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/31/1978 |
| From: | Curtis N Pennsylvania Power & Light Co |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18025A629 (38) | |
Text
NRC ~octa'~ LL5 NV~~H RlKCUQATCRY ~WSSICN CCCXRT NVI48eR I2.78) '
I I 4E iQLlhlseR NRC OISTR tBUTlON mR PART GC OOCKE7 i4tATER)AL
'TQ: FRahl: QJtTB Cr oocuMKNT Mri Olan D, Parr .
PP&L 03 31 78 Allentown,. PA 18101 CAiTK RecaIV'EC N W Curtis 04 05 78 i~4KTTKR QNOTCRIZSC:. I t4ttlT Ir 4 R114. NUAI88R orr C Pf~~ R8CZIVKCI
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48SCRI P71 4th Response to NRC ltr dtd 12/06/77 ' ~
I Furnishing responses to the "Questionaire I
for Fracture Toughness Properties of Older Reactor Vessels", consiting of:
1 ' Updated response for Unit 1, indluding copp content for Q121 ~ 2(1), & quantified respons to Q121.2(3)..
2 ~ Complete response for Unit 2~
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ppaL TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEME t215) 821-5151 tMR s> 1978 MlIIEilNItIdeas rlLBtlP(g 17 ~
Vl M'r . Olan D. Parr, Chief C,g C
Light Water Reactors Branch No. 3 CD Division of Prospect Management U.S. Nuclear Regulatory Commission CD Washington, DC 20555 237'OCKET SUSQUEHANNA SES PRESSURE VESSEL FRACTURE TOUGHNESS PROPERTIES ER 100450 PLA-FILE 840-2 AND NOS.
50-388 50-387
Dear Mr. Parr:
Attached.. are complete responses. to the "Questionaire for Fracture Toughness Properties of Older Reactor"Vessels" contained in your December 6, 1977 letter. A partial response had. been sent to you in our. February 16, 1978 letter (PLA-218), since all of the data requested by you.was. not available at that. time The attached. information consists of:"
- 1. An updated response for Unit. 1. This response now includes the copper content for Q121.2(1), and. a quantified. response to Q121.2(3).
2.. A complete response for Unit 2. This information is very similar to Unit 1 but is submitted as a separate response.
Very truly yours, N. W. Curtis VP-Engr. 5 Construction NWC:KMM Attachment PENN SYLVAN IA POWER 8 L I GH T COMPANY
~ .
1
~ 'SES UNIT 1 UESTIQN:
121.0 - MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121 ..1 Provide the purchase order date for your reactor vessel, identify the firm or firms with whom the purchase order was placed, the vessel fabricator, and applicable edition of the.
ASME Code requirement pursuant to 10CFR Part 50.55a(c).
RESPONSE
121. 1'hefrom S'usquehanna CBl No.
- Nuclear 1 reactor pressure vessel Company, was purchased August 5, 1968. This vessel was fabricated to Section III of the, ASME Boiler and Pressure Vessel Code as revised. by the following:
Section III Nuclear Vessels - 1968 Edition with Addenda to and including Summer 1970 Addenda and Paragraph NB-3338.2(d)(4) of the Winter 1971 addenda shall supercede Paragraph I-613(d) of the 1968 edition.. Paragraph HB-2400 of the 1971 Edition shall apply for all fabrication performed at the Susquehanna. Site.
JW: csc/7D1
l SSES UNIT 1 gUESTION:
121.2'dentify each material (plate, and/or forging and weld metal) in the beltline region (as defined by paragraph II. H, Appendix G, 10CFR Part 50) and provide a sketch showing the location of these materials in the reactor vessel. Provide the-fo11owing information for each material:
(1) Chemical analyses; particularly those elements known to affect irradiation sensitivity and degrade the upper shelf fracture energy (Cu, P, and S).
(2) Unirradiated fracture toughness properties (T T, RTNOT and upper shelf fracture energy) as required li Appendix G, 10CFR Part 50, identifying the limiting material in the- ractor vessel beltline region.
(3), Estimate the maximum anticipated change" in RT and upper shelf fracture energy as a function of 5$ EOI fluence at. the inner wall for the materials in the beltline. region of. the reactor vessel.
RESPONSE
121.2. Materialss in the, reactor pressure'essel beltline region are identified; as, listed below. and as shown on the- attached sketch:
Vessel BeltTiner Material Identification A. Lower SheT1 Course (CBIN Owg R-l, Rev 4, Contract No.'683331) 1 Plates ID ¹ a MELT ¹ SLAB ¹'
21 CB5083 21'1 C0770 2 C0814 2 2., Wel ds The vertical welds and girth weld for this shell course were completed in the "field". Records were not kept on whi ch of, the electrodes, i denti fi ed by heat and lot numbers, were used. in the weld up of the specific field welds of this shell assembly.
is assumed that any of the SMAW electrodes - type It 8018 released for field welding could have been used on any or all of the associated seams in the beltline region.
JW: csc/7DZ
SSES UNIT 1 RESPONSE: - (Cont'd) 121. 2 El'ectrodes released for the field welding of these plates are as follows:
~Te Lot No. Heat No.
SMAW Electrode Type 8018 B504B27AE 401S0371 SMAW Electrode Type 8018 629616 L320A27AG SMAW Electrode Type 8018 402K9171 K315A27AE SMAW Electrode Type 8018 411L3071 L311A27AE SMAW Electrode Type 8018 494K2351 L307A27AO SMAW Electrode Type 8018 C115A27A 402C4371 SMAW Electrode Type 8018 J417B27A 412P3611 B. Lower Intermediate Shel,l Course
- 1. Plates PC ¹ ¹: MELT ¹ SLAB 22 C0803 22', 2 C0776 2'elds'D IF'he
Records were not, kept on which of the electrodes, identified by heat and lot numbers, were used in the. weld-up of the specific field welds of the shelT assembly. It is assumed that any of the SMAW electrodes (type 8018) released for field welding could have been used on any or all of the associated seams in the beltline region.
Electrodes released for- the field. welding of these plates are as follows:
~Te Lot No. Heat No.
SMAW Electrode Type 8018 B504B27AE 401 S0371 SMAW Electrode Type 8018 629616 L320A27AG SMAW Electrode Type 8018 402K9171 K315A27AE SMAW Electrode Type 8018 411L3071 L311A27AF SMAW Electrode Type 8018 494K2351 L307A27AO SMAW Electrode Type 8018 C115A27A 402C4371 SHAM Electrode Type 8018 J417B27AF 412P3611 JW:csc/7D3
0 I'
SSES UNIT 1
RESPONSE
121.2(l) Vessel Plate Material Mn P S Cu Si Ni Mo Values are shown 1n percent Lower Shell PC 21-1, Melt ¹ B5083, .21 1.27 .010 .019 14 .25 .48 . .51 Sl ab- ¹1 PC 21-2, Melt ¹C0770, l. 23, . 008 . 016 .14 .19 .50 .49
¹2
.22'lab PC. 21-3, Melt ¹C0814, .20 1.36 .Oll .016 .13 .26 .51 .51 Slab ¹2 Lower Intermediate Shell'C, 22-.1, Melt ¹C0803, .21 1.30 .009 .019 .09 .24 .53 .52 Slab ¹1 PC, 22-2, Melt. ¹C0776, .22 1.34 .010 .010 .12 .27 .48 Slab. ¹1 .48'.30 PC.'2-.3', Mel t,". ¹C2433'.18: .009'015: .10 .23; .63 .57 Slab= ¹1 Note: *N/R Not Reported P' Cu'i. Ni Mo Cr V are shown in percent)
Weld Material Type SMAW Electrode 8018 Lot ¹ and Heat ¹ Lot ¹B504827AE .05 1. 18 .013 .012 .03 .37. 1.04 .56 .03 .0 Ht ¹401S0371, Lot ¹629616 .05 1.17 .015 .018 .04 .44 .99 .55 .05 .0 Ht ¹L320A 27AG
, Lot ¹402K9171 .06 1.15 .015 .016 .03 .36 .98 ,53 .05 .0 Ht '¹K315A27AE Lot. ¹411L3071 .05 1.20 .016 .019 .03 .46 .93 .50 .04 .0 Ht ¹L311A27AF JW:csc/7D4"'alues Lot ¹494K2351 Ht ¹L307A27AD
.05 1.18 .015 '017 .04 .37 1. 10 .57 .04 .0 Lot ¹C115A27A . 033 1. 22 . 009 . 014 .02 .49 . 92 . 57 N/R N/
Ht ¹402C4371 Lot ¹J417B27A F .07 T. 10 .016 .019 .03 .36 .93 .47 .03 .0
¹ Ht 412P3611
l
'0 SSES UNIT 1
RESPONSE
121.2(2) Unirradiated fracture. toughness properties (T r, RTNT and upper shelf fracture energy) as required by A Andix 0, 10CFR Part 50, identifying. the limiting material in the reactor vessel beltline regl on The Susquehanna 1 reactor pressure vessel was ordered prior to the issuance of Appendix G, 10CFR.Part 50. The ferritic material for the pressure boundary was qualified by drop weight testing for the shell plate material and both drop weight and'harpy V notch testing for the weld material. The test results, along with the specific requirements prevai ling at the time of vessel ordering, are summarized in the tables which follow.
Impact Properties of SA533,. Grade B, Class 1 Plate Material in Beltline Region Location: Plates. Dro Mt. NDTT F Lower shell course 21-1 -10 F 21-2 -30 F 21;3. 30oF Lower, intermediate. 22-1'2-2 -10 F shell course: -10 F 22 3 -50 F Impact'roperties: of Meld Materials Employed In the Bel,tlipe Region Meld Material Charpy "V" Test Drop Mt Identi ficati on Ft/lb T~em . oF ~Re uired N01T oF Lot¹ B504B27AE, 57, 58; '62 -20 30 ft/lbs -80 Ht ¹40150371'ot at10 II II F
¹629616 51, 52 +10 70 Ht ¹L320A27AG'ot
¹402K9171 58, 58 +10 -70 Ht ¹K315A27AE Lot ¹411L3071 51, +10 "70 Ht ¹L311A27AF 67'7, Lot ¹494K2351 96 +1 -80 Ht ¹L307A27AD 0'10 Lot ¹C115A27A II II 82,, 84, 92 Ht ¹402C4371 Report Lot N417B27AF 52, 65, 69 -20 II II 80 Ht ¹412P3611 JM: csc/7D5
k SSES UNIT l.
RESPONSE
I21.2 (3) Estimated, maximum changes in RT 0 and upper shelf fracture energy as a,function o) khe end of life (EOL) fluence at the I/4T depth of the vessel beltline materials are listed below. The predicted peak EOL fluence a/sthe 1(4T depth of the vessel beltline is 1.37 x 10 n/cm after 40 years of service. Tran-sition temperature changes and changes in upper energy were calculated in accordance with shelf'racture the rules of Regulatory Guide 1.99. Reference tempera-tures. were established in accordance with the- instruc-tions in Branch Technical Position MTEB No. 5-2.
Limiting, Plate Material (Cu = .14K, P = .OlOX) Plate 21-1 Transition- Temperature Change (per Regulatory Guide 1.99) 42 F Reference Temperature (Drop Weight NDTT) -10 F Adjusted Reference Temperature at EOL 32 F Change in Upper Shelf Energy (per Regulatory Guide 1.99)
Limiting, Weld= Material, (Cu. = .03K, P: = .016K) Lot'11L3071 Heat L311A27AF Transition Temperature Change (per-. Regulatory Guide 1.99) 30 F Reference. Temperature (per MTEB No. 5-2) 10 F, Adjusted Reference Temperature at EOL. 40'F Change in Upper Shelf Energy (per Regulatory Guide 1.99) ~-IOX JW:csc/7011"'
(
~ SSES UNIT 1 gUESTION:
121 .3 Describe the survelliance program for the reactor vessel(s)-,
list the. materials (plate, and/or forging and weld metal) and justify their selection. State any deviation from
- Appendixes G and H, 10CFR.Part 50.
RESPONSE
The survelliance program of the reactor pressure vessel materials is described in Section 5.3.1.6 of'he FSAR.
t bent,i f 0 CAP
SSES UNIT 2
-(:
QUESTION:
121.0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121.1 Provide the purchase order date for your reactor vessel, identify the firm or firms with whom the purchase order was placed, the vessel fabricator, and applicable edition of the ASME Code requirement pursuant to 10CFR Part 50.55a(c).
RESPONSE
121. 1 The Susquehanna No. 2 reactor pressure vessel was purchased from CBI - Nuclear Company, August 5, 1968. This vessel was fabricated to Section III, of the ASME Boiler and Pressure Vessel Code as revised. by the following:
Section III Nuclear Vessels - 1968 Edition with Addenda to- and sncluding Summer l970 Addenda and Paragraph NB-3338.2(d)(4) of the Minter 1971 addenda shall supercede Paragraph I-613(d) of the 1968 edition. Paragraph NB-2400 of the 1971 Edition shall apply. for all fabrication performed at. the Susquehanna Site; JM:csc/7D1
h SSES UNIT 2 QUESTION:
121. 2 Identify, each material (plate, and/or forging and weld metal) in the beltline region (as defined by paragraph II. 11, Appendix G, 10CFR Part 50) and provide a sketch showing the location of these materials in the reactor vessel. Provide the following information for each material:
(1) Chemical anal'yses; particularly those elements known to affect irradiation sensitivity and degrade the upper shelf,'racture energy (Cu, P, and S)..
(2) Unirradiated fracture toughness properties (T T, RTNDT and upper shelf fracture energy) as required (
Appendix G, 1OCPR Part 50, identifying the limiting material in the ractor vessel beltline region.
(5)- Estimate the maximum anticipated change in RT and upper" shel'f frac'ture energy as a function of 5$ EOL, fluence at the inner wall for the materials in the beltline region of the reactor vessel RESPONSE".
121'.2; Materials. fn the reactor pressure vessel beltline region are identified: as li'sted,'below and. as shown. oa the attached. sketch:
Vessel Beltline. Material I'dentification A. Lower Shell Course-1 Plates.
PC IDP MELT@ SLAB P 21 "1 6C956 1-1 21-2 6C980 L-L 21-3. 6C1053, 1-1.
2 Mel ds The vertical welds and girth weld. for this shell course were completed in the "field". Records were not kept on which of the electrodes, identified by heat and lot numbers, were used in the weld up of the specific field welds of this shell assembly. It is assumed. that any of the SMAM electrodes - type 8018 released f'r field welding could have been used, on any or all of the associated seams in the beltline region.
JM:csc/702
Ai
'0 SSES UNIT 2 RESPONSE: - (Cont'd) 121.2.- Electrodes released for the field welding of these plates are as follows:
~Te Lot No. Heat No.
SMAW Electrode Type 8018 8504827AE 401S0371
-SMAW Electrode Type 8018 629616 L320A27AG SMAW Electrode Type 8018 402K9171 K315A27AE SMAW Electrode Type 8018 411L3071 L311A27AF.
SMAW Electrode Type 8018 494K2351 L307A27AD SHAW Electrode Type 8018 C115A27A 402C4371 SHAW Electrode Type 8018 J417827A 412P3611 SHAW Electrode Type 8018 C109A27A 09M057 SMAW Electrode Type 8018 E204A27A 624263 SMAW Electrode Type 8018 F414827AF 659 N315 B. Lower Intermediate Shell Course 1., Plates PC'D¹ MELT ¹ SLAB ¹ 22-.1 C2421 22-2'2-,3 C2929 C2433:
2'. Welds The vertical welds and the. girth weld for this shell course were completed. in the "field"..
Records were not kept on which of the electrodes, identified by heat and lot numbers, were used in the weld-up of the specific field welds of the shell assembly. It's assumed that any of the SHAW electrodes (type 8018) released for field welding could have been used on any or all of the associated seams. in the beltline region.
Electrodes released for the field welding of these plates are as follows:
Lot Mo. Heat Mo.
SMAW Electrode Type 8018 8504827AE 401 S0371 SMAW Electrode Type 8018 629616 L320A27AG SHAW Electrode Type 8018 402K9171 K315A27AE SHAW Electrode Type 8018 411L3071 L311A27AF SMAW Electrode Type 8018 494K2351 L307A27AD SHAW Electrode Type 8018 C115A27A 402C4371 JW:csc/7D3
SSES UNIT 2
~Te Lot No. Heat No.
SMAM Electrode Type 8018 J417B27AF 412P361 SMAM Electrode. Type 8018 09M057 1'109A27A SMAM Electrode Type 8018 E204A27A 624263 SMAM Electrode Type 8018 F414B27AF 659N315 JM: csc/7D4
C' SES UNIT 2
RESPONSE
121.2(l) Vessel Plate Material Mn P S Cu Si Ni Mo Values are shown 1n percent Lower Shell PC, 21-1, Melt ¹6C956 .18 1.43 .012 . .006 .11 .22 .55 .52 Slab ¹1-1 PC 21-2, Melt ¹6C980 .19 1 35 .011 .006 .10 .22 .56 .51
.Slab ¹1-1 PC'. 21 "3, Melt ¹6C1053 .18 1. 37' 012' 010 .10 .30 . 58 . 50 Slab ¹1-1 Lower Intermediate Shell PC- 22"1, Melt ¹C2421, .19 1.22'007'011 .13 .25 .68 .55 Slab ¹3 PC 22-2, Melt ¹C2929, .20 l. 27 . 006 . 015 . 13.. 22 . 64* . 56.
Slab ¹1 PC 22"3:, Melt ¹C2433. $ 8 1'. 30 .009.. 015 . 1Q . 23' 63, . 57 Slab, ¹Z.
Note: "N/R Not Reported Mn- P S Cu Si Ni- Mo Cr Vr Values are shown 1n percent Meld Material Type SMAM Electrode
¹" and Heat ¹ 8018'ot Lot ¹B504B27AE .05 1.18 .013 .012 .03 .37 1.04 .56 .03 Ht ¹401S0371 .0'04 Lot'629616 .05 1. 17 .015 .018 .44 .99 .55 .05 .0~
Ht ¹L320A27AG
. Lot ¹402K9171 .06 1.15 .015 .016 .03 .36 .98 .53 .05 .02 Ht '¹K315A27AE Lot ¹411L3071 .05 1.,20 .016 .019 .03 .46 .93 .5Q .04 .02 Ht ¹L311A27AF
.Lot .¹494K2351 .05 1.18 .015 .017 .04 .37 1.10 .57 .04 .02 Ht ¹L307A27AD Lot ¹C115A27A .033 1.22 .009 .014 .02 .49 .92 .57 N/R N/r",
Ht ¹402C4371.
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. ~
ES UNIT 2 P S Cu Si Ni Mo Cr Vr Values are shown in percent Lot ¹J41?B2?A F .07 1.10 .016 .019 .03 .36 .93 ..47 .03 .0~
Ht ¹412P3611 Lot ¹C109A2?A .063 1.18 .009 .021 .03 .47 .89 .53 N/R N/R Ht ¹09M057 Lot'E204A42?A . 051'. 08 . 010 . 023' 06 . 38.. 89 . 50 N/R N/F.
Ht ¹ 624263 N/"
Lot ¹F414B27AF .05 1.14 .015 .013: .04 .35, 1.00 .49 .05 Ht ¹659N315 Note: N/R-- Not Reported JM:csc/706
~I SES UNIT 2
RESPONSE
121.2(2) Unirradiated fracture toughness properties (T , RTN T and upper shelf fracture energy) as required by Appendix !F, 10CFR Part 50, identifying the limiting material in the reactor vessel beltline region.
The Susquehanna 1 reactor pressure vessel was ordered prior to the issuance of Appendix G, 10CFR Part.50. The ferritic material for the pressure boundary was qualified by drop weight testing for the shell plate material and both drop weight ands Charpy V notch testing for the weld material. 'he test results, along with the specific requirements prevailing at the time of vessel ordering, are summarized in the tables which follow.
Impact Properties of SA533, Grade B, Class I Plate Material in Beltline Region Location Plates Dro Wt. NDTT DF Lower SheI1 Ring 21-1 -20 F 21 "2 20oF 21-3 +10'F Lower- Intermediate 22-1 -10 F 22-.2 "ZO~F.
She11. Ring.
22-3 -30 F Impact Properties, of Weld Materials Employed In the Beltline Region Charpy "V" Test Drop Wt Weld Material 'F.
Ft/lb . 'sF ~eceuired NDTT Identification T~em Lot¹ B504B27AE, 57, 58, 62 -20 30 ft/lbs "80 Ht ¹401S0371 at10 F II- II "70 Lot, ¹629616 51ir 52 +10'10 Ht'L320A27AG "70 Lot ¹402K9171 58, 58 Ht ¹K315A27AE +10. <<70 Lot ¹411L3071 51, 67 Ht ¹L311A27AF +10 -80 Lot ¹494K2351 87, 96 Ht ¹L307A27AD +10 N/R Lot ¹C115A27A 82, 84, 92 Ht ¹402C4371 "20 "80 Lot ¹J417B27AP 52, 65, 69 Ht ¹412P3611 JW:csc/7D7
~
(0 USES UNIT 2 Impact, Properties of Meld Materials Employed In the Beltline Region Meld Material Charpy "Y" Test Orop Mt Identification Ft/lb ~Tee . 'F ~Re uired ROTT 'F Lot ¹C109A27A't 43, 43, 44 +10
¹09M057 Lot ¹E204A27A 26 , 38 , 42 , 50, -20 -70 Ht 624263. 76 Lot ¹F414B27AF 74, 76, 77 -10 -80 Ht 659N315 JM:csc/708
SSES UNIT 2
RESPONSE
121.2 (3) Estimated maximum changes in RT and upper shelf fracture energy es a function othe O end of life at the 1/4T depth of the vessel beltline (EOL)'luence materials are. listed below. The predicted peak EOL fluence e$ >the 1]4T depth of the vessel beltline is 1.37 x 10 n/cm after 40 years of service. Tran-sition temperature changes and changes in upper shelf fracture energy were calculated in accordance with the rules of Regulatory Guide 1.99. Reference tempera-tures were established in accordance with the instruc-tions in Branch Technical Position MTEB No. 5-2.
Limiting, Plate Material'Cu = .13%,
P = .007%) Plate 22-1 Transition. Temperature Change (per Regulatory Guide 1.99) 34oF Reference Temperature (Orop Weight NDTT) -10 F Adjusted, Reference Temperature at. EOL 24oF Change.- in Upper Shel'f Energy (per Regul'atory Guide 1 99) ~-14K Limiting, Weld MateriaT (Cu = .03%,
P =..016%) Lot 411L3071 Heat L313A27AF Transition Temperature- Change (per Regulatory Guide 1.99) 300F Reference Temperature (per.MTEB No. '5-,2) 10 F Adjusted Reference Temperature at EOL 40 F Change: in Upper Shelf Energy (per Regulatory Guide 1.99) ~-10%
JW:csc/7D9
SSES UNIT 2 gUESTION:
121.3. Describe the surveillance program for the reactor vessel(s),
list the materi al s (pl ate, and/or forging and weld metal) and justi fy their selection. State any devi ation from Appendixes G and H, 10CFR Part 50.
RESPONSE
The survelliance program of the- reactor pressure vessel materials is described in Section S.3.1.6 of the FSAR.
JM: csc/7D10
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