ML18024A089

Letter Replying to the Questionnaire Contained in the December 6, 1977 Letter and Attaching an Updated Response for Unit 1 and a Complete Response for Unit 2

ML18024A089
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: ML18024A089 (31)

Text

NRC FOE~M 196 UM NUC~CR RSQULATORY C~ISSION OOCIi: B IS-7B)

'PC OISTRlBUTlON -oR PART 50 DOCKET MATERlAL FI ~tsb4sa TO:

Mri Olan Di Parr FROM:

'P&L '3 OATt OF OOCUMSNT 31 78 Allentown, PA 18101 DATG RBCSIVBO N W Curtis 04 05 78

~LETTS R QNOTORIZSCt INPUT FORM. NUMBSR OF COPIBS RBCBIVBD ORIGINAL liBCINCLASSIF I SO QCOPY DESCRIPTION Response to NRC ltr dtd 12/06/77 ~ ~ ~

Furnishing responses to the "Questionaire 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 ~

1p 19p SEQUEHANNA UNITS 1 & 2

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FOR ACTION/INFORM/IATION EWMONIIENTAL ASSIGaIED AD-CH CHME- BRANCK CHI:F.

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B'. HARLESS INTERNALOISTRI BUTION.

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TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEME {215) 821-5151 P '!

MAR 01 1978 tIEtJMRi)~ ogj(p ~~p Ir C7~

~CO Mr. Olan D. Parr, Chief Light Water Reactors Branch No. 3 ~g

<<CQ Division of Prospect Management I]

U.S. Nuclear Regulatory Commission CD Washington, DC f'o 20555 SUSQUEHANNA SES DOCKET NOS. 50-387 PRESSURE VESSEL FRACTURE TOUGHNESS PROPERTIES AND 50-388 ER 100450 FILE 840-2 PLA- 237

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 l. 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. & Construction NWC:KMM Attachment PENNSYLVANIA POWER 8 LIGHT COMPANY

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SSES UNIT 1 gUESTION:

121. 0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121. 1 Provide the purchase order date for your reactor vessel, identi.fy 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. The Susquehanna reactor pressure vessel

- Nuclear Company, August 5, 1968. This purchased 1 No. 1 was from CBI. 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 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.

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4 4" SSES UNIT 1 gUESTION:

121. 2 Identify 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 following 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, RTRUT and upper shelf fracture energy) as required (

Appendix 0, 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 fluence at the inner wall for the materials in the K EOL beltline region of the reactor vessel.

RESPONSE

121.2 Materials in the reactor pressure vessel beltline region are identified as listed below and as shown on the attached sketch:

Vessel Beltline Material Identification A. Lower Shell Course (CBIN Dwg R-l, Rev. 4, Contract No.'83331)

1. Plates PC ¹ ID ¹ MELT ¹ SLAB ¹ 21 CB5083 21 C0770 21 C0814

2. Welds 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.

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/702

SSES UNIT 1 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 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 L307A27AD SMAW Electrode Type 8018 C115A27A 402C4371 SMAW Electrode Type 8018 J417B27A 412P3611 B. Lower Intermediate Shell Course

1. Plates PC ¹ ID ¹ MELT ¹ SLAB ¹ 22 C0803 22 C0776 22 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 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 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 SMAW Electrode Type 8018 C115A27A 402C4371 SMAW Electrode Type 8018 J417B27AF 412P3611 JW:csc/703

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~ SSES UNIT 1

RESPONSE

121.2(l) Vessel Plate Material Mn P S Cu Si Ni Mo Values are shown sn percent Lower Shell PC 21-1, Melt ¹ B5083, .21 1 27 .010 .019 14 .25 .48 . .51 Slab ¹1 PC 21-2, Melt ¹C0770, .22 1.23 .008 .016 .14 .19 .50 .49 Slab ¹2 PC 21-3, Melt ¹C0814, .20 1.36 .Oll .016 .13 .26 .51 .51 Slab ¹2 Lower Intermediate Shell PC 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 .48 Slab ¹1 PC 22-3, Melt ¹C2433, . 18 1 30 .009 .015 .10 .23 .63 .57 Slab ¹1 Note: "N/R - Not Reported P S Cu Si Ni Mo Cr Vn are shown in percent)

Weld Type SMAW 'Values Material Electrode 8018 Lot ¹ and Heat ¹ Lot ¹B504B27AE .05 1.18 .013 .012 .03 .37 1.04 .56 .03 .02 Ht ¹401S0371 Lot ¹629616 .05 1.17 .015 .018 . 04 .44 .99 .55 .05 .02 Ht ¹L320A 27AG

. 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 .50 .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 Lot ¹J417B27A F .07 1.10 .016 .019 .03 .36 .93 .47 .03 .02 Ht ¹ 412P3611 JW: csc/7D4-

SSES UNIT 1

RESPONSE

121.2(2) Unirradiated fracture toughness properties (T , 'RTN and upper shelf fracture energy) as required by A lndix%~T 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 'he material for the pressure boundary was qualified by drop ferritic weight testing for the shell plate material and both drop weight and Charpy V notch testing for the weld material. The 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 1 Plate Material in Beltline Region Location Plates Dro Wt. NDTT 'F Lower shell course 21-1 -10 F 21 "2 -30 F 21 "3 -30 F Lower intermediate 22-1 -10 F shell course 22-2 -10 F 22-3 -50 F Impact Properties of Weld Materials Employed In the Beltline Region r

Weld Material Charpy "V" Test Drop Wt Identi fi cati on (Ft/lb) ~Tem . oF Recluired N017 oF Lot¹ B504B27AE, 57, 58, '62 -20 30 ft/lbs -80 Ht ¹401S0371 at10 F Lot ¹629616 51, 52 +10 II II 70 Ht ¹L320A27AG

'ot ¹402K9171 58, 58 +10 -70 Ht ¹K315A27AE Lot ¹411L3071 51, 67 +10 -70 Ht ¹L311A27AF Lot ¹494K2351 87, .96 +1 -80 Ht ¹L307A27AD 0'10 Lot ¹C115A27A 82, 84, 92 II II No Ht ¹402C4371 Report Lot ¹J417B27AF 52, 65, 69 -20 II II 80 Ht ¹412P3611 JW:csc/7D5

C' SSES UNIT 1

RESPONSE

121.2 (3) Estimated maximum changes in RT and upper shelf fracture energy as a.function o) D the end of life (EOL) fluence at the 1/4T depth of the vessel beltline materials are listed below. The predicted peak EOL fluence a/Bthe 1(4T depth of the vessel beltli ne 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 temper a-tures were established in accordance with the instruc-tions in Branch Technical Position MTEB No. 5-2.

Limiting Plate Material (Cu = .14%,

P = .010~) Plate 21-1 Transition Temperature Change (per Regulatory Guide 1.99) 42 F Reference Temperature (Drop Weight NDTT) 10oF Adjusted Reference Temperature at EOL 32oF Change in Upper Shelf Energy (per Regulatory Guide 1.99)

Limiting Weld Material (Cu = .03K, P = .016K) Lot 411L3071 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) ~-lOX JW:csc/7011"'

( ~ ;0 SSES UNIT 1 QUESTION:

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 the FSAR.

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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 1ncluding Summer 1970 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.

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SSES UNIT 2

()UESTIGN:

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 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 I, RTNUT and upper shelf fracture energy) as required L Appendix 0, 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$ EOL fluence at the inner wall for the materials in the beltline region of the reactor vessel.

RESPONSE

121.2 Materials in the reactor pressure vessel beltline region are identified as listed below and as shown on the attached sketch:

Vessel Beltline Material Identification A. Lower Shell Course

1. Plates PC IG¹ MELT ¹ SLAB ¹ 21-1 6C956 l-l 21-2 21-3 6C980 l-l 6C1053 1-1

2. Welds 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 SMAW electrodes - type 8018 released for field welding could have been used on any or all of the associated seams in the beltline region.

JW:csc/7D2

D I'I t L I

SSES VNIT 2 RESPONSE: - (Cont'd) 121. 2 Electrodes released for the field welding of these plates are as follows:

Lot No. Heat No.

SMAM Electrode Type 8018 B504B27AE 401S0371 SMAW Electrode Type 8018 629616 L320A27AG SHAW Electrode Type 8018 402K9171 K315A27AE SMAW Electrode Type 8018 411 L3071 L311A27AF SHAW Electrode Type 8018 494K2351 L307A27AD SHAM Electrode Type 8018 C115A27A 402C4371 SHAW Electrode Type 8018 J417B27A '12P3611 SMAM Electrode Type 8018 C109A27A 09M057 SHAM Electrode Type 8018 E204A27A 624263 SMAM Electrode Type 8018 F414B27AF 659N315 B. Lower Intermediate Shell Course Plates PC IO¹ MELT ¹ SLAB ¹ 22-1 C2421 22-2 C2929 22" 3 C2433

2. Melds 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 is 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.

'I Electrodes released for the field welding of these plates are as follows:

Lot No. Heat No.

SMAM Electrode Type 8018 B504B27AE 401S0371 SMAM Electrode Type 8018 629616 L320A27AG SMAM Electrode Type 8018 402K9171 K315A27AE SHAM Electrode Type 8018 411L3071 L311A27AF SHAW Electrode Type 8018 494K2351 L307A27AD SHAW Electrode Type 8018 C115A27A 402C4371 JM:csc/7D3

SSES UNIT 2

~Te Lot No. Heat No.

SMAW Electrode Type 8018 J417B27AF 412P3611 SMAW Electrode Type 8018 C109A27A 09M057 SMAW Electrode Type 8018 E204A27A 624263 SMAW Electrode Type 8018 F414B27AF 659N315 JW:csc/7D4

'iSES UNIT 2

RESPONSE

121.2(l) Vessel Plate Material Mn P S Cu Si Ni Mo Values are shown sn percent Lower Shell PC 21-1, Melt ¹6C956 .18 1.43 .012 ..006 .11 .22 .55 .52 Slab ¹l-l PC 21-2, Melt ¹6C980 .19 135 .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 1 27 .006 .015 .13 .22 .64- .56 Slab, ¹1 PC 22-3, Melt ¹C2433, .18 1.30 .009 .015 .10 .23 .63 .57 Slab ¹2 Note: "N/R - Not Reported P S Cu Si Ni Mo Cr Vn Values are shown sn percent Meld Material Type SMAM Electrode 8018 Lot ¹,and Heat ¹ Lot ¹B504B27AE . 05 1. 18 . 013 . 012 .03 .37 1. 04 .56 .03 . 02 Ht ¹401S0371 Lot ¹629616 .05 1.17 .015 . 018 .04 .44 .99 .55 .05 .02 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 .50 ..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.

JM:csc/7D5

ES UNIT 2 P S Cu Si Ni Mo Cr Vn Yalues are shown in percent Lot ¹J417B27A F .07 110'016 .019 .03 .36 .93 .47 .03 .02 Ht ¹412P3611 Lot ¹C109A27A . 063 1. 18 . 009 . 021 . 03 .47 . 89 .53 N/R N/R Ht ¹09M057 Lot ¹E204A427A .051 1.08 .010 .023 .06 .38 .89 .50 N/R N/R Ht ¹ 624263 Lot ¹F414B27AF . 05 1.14 . 015 . 013 . 04 . 35 1. 00 .49 . 05 Ht ¹659N315 Note: N/R - Not Reported N/R'W:csc/7D6

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SES UNIT 2

RESPONSE

121.2(2) Unirradiated fracture toughness properties (T>>~, RTNT and upper shelf fracture energy) as required by Agbndix 5, 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 and Charpy V notch testing for the weld material. The 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 1 Plate Material in Beltline Region Location Plates Dro Wt. NDTT ( F)

Lower Shell Ring 21-1 -20 F 21-2 -20 F 21-3 +10 F Lower Intermediate 22-1 -10 F Shell Ring 22-2 20oF 22-3 -30 F Impact Properties of Meld Materials Employed In the Beltline Region Meld Material Charpy "V" Test Drop Mt Identification Ft/lb ~Tee . eF ~Re uired NDTT eF Lot¹ B504B27AE, 57, 58, 62 -20 30 ft/lbs. "80 Ht ¹401S0371 at 10'F Lot ¹629616 51, 52 -70

+10'10 Ht ¹L320A27AG Lot ¹402K9171 58, 58 -70 Ht ¹K315A27AE Lot ¹411L3071 51, 67 +10 -70 Ht ¹L311A27AF Lot ¹494K2351 87, 96 +10 -80 Ht ¹L307A27AD.,

Lot ¹C115A27A 82, 84, 92 +10 N/R Ht ¹402C4371 Lot ¹J417B27AF 52, 65, 69 "20 -80 Ht ¹412P3611 JW:csc/707

~ SES UNIT 2 Impact Properties of Weld Materials Employed In the Beltline Region Weld Material Charpy "V" Test Drop Wt Identification 't/lb ~Tem . 'F ~Re uired NOTT eF Lot ¹C109A27A 43, 43, 44 +10 II II ~

N/R Ht ¹09M057 Lot ¹E204A2?A 26, 38, 42, 50, "20 -70 Ht 624263 76 Lot ¹F414B27AF 74, 76, 77 "10 -80 Ht 659N315 JW: csc/7D8

SSES UNIT 2

RESPONSE

121.2 (3) Estimated maximum changes in RT and upper shelf fracture energy as a function os D the end of life (EOL) fluence at the 1/4T 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 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 = e13X, P = .007X) Plate 22-1 Transition Temperature Change (per Regulatory Guide 1.99) 34 F Reference Temperature (Drop Weight NDTT) -10 F Adjusted Reference Temperature at EOL 24 F Change in Upper Shelf Energy (per Regulatory Guide 1.99) ~-14K Limiting Meld Material (Cu = .03K, P = .016K) Lot 411L3071 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)

JW:csc/7D9

SSES UNIT 2 UE STION:

121. 3 Describe the surveillance 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 the FSAR.

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UNIT 2

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