ML20154B373

Forwards Correspondence from Licensee Re Questions Asked by NRC Staff & Answers from Licensee with Respect to Submittal for Approval of Alternate 17R Insp Re GL 88-01, Intergranular Stress Corrosion Cracking Commitments

ML20154B373
Person / Time
Site:	Oyster Creek
Issue date:	09/29/1998
From:	Eaton R NRC (Affiliation Not Assigned)
To:	NRC
References
GL-88-01, GL-88-1, NUDOCS 9810050186
Download: ML20154B373 (8)

Text

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Septemtier 29, 1998 i

MEMORANDUM TO: File FROM: Ronald B. Eaton, Senior Project Manager Original signed by Project Directorate 1-3 Division of Reactor Projects - 1/II

SUBJECT:

CORRESPONDENCE FROM GPU NUCLEAR, INC., PROVIDING THE .

QUESTIONS ASKED BY THE NRC STAFF AND THE ANSWERS FROM THE LICENSEE WITH RESPECT TO THEIR SUBMITTAL FOR APPROVAL OF ALTERNATE 17R INSPECTIONS RELATED TO GENERIC LETTER 88-01, INTERGRANULAR STRESS CORROSION CRACKING COMMITMENTS Please place the attached subject correspondence received on September 21, 1998, in Docket file 50-219.

Docket No. 50-219

Attachment:

As stated DISTRIBUTION w/ attach:

- Docket File PUE>LIC REaton DISTRIBUTION w/o attach:

PDl-3 Reading File TClark /[

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h DOCUMENT NAME: G:\EATON\ma2417.rai To receive a copy of this document, indicate in the box: "C" = Copy without attachment /enclosur$ ,"E" = Copy with attachment / enclosure "N" = No copy

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9810050186 980929 PDR ADOCK 05000219 P PDR ,

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, 4 Oyster Creek 17R IGSCC Inspection Scope Deferral Questions (1) Identify the fit up welds (the last weld that was performed in a piping run) among the welds requested for inspection deferral.

None of the welds in the current 17R scope is a piping run closure weld. In the Isolation Condenser and RWCU systems, the closure weld is at the drywell penetration which was performed in 13R (1992). In the Core Spray system, the closure weld was at the reactor vessel nozzle safe end weld which was made during original construction. The closure weld for the Shutdown Cooling system was the weld on the downstream side of the valve (NU-4-3 is the weld in the 17R scope and is the weld of the Tee to the upstream side of the valve). Lastly, the Recirculation closure weld was the weld upstream of tre vessel inlet safe end weld during construction.

(2) Confirm the assumption of the welding process used during initial construction (i.e., shielded metal are/ submerged are welds vs. gas tungsten are welds and gas metal-arc welds).

A review of a sample of the weld records showed that all the welds in the sample, both shop- and field-welds, were EB inserts for the root and SMAW fills. Therefore, for conservatism, we assume all the welds were either SAA or SMAW welds.

(3) Provide weld configuration types (i.e. pipe-pipe, pipe-elbow, etc.) and if significantly different thicknesses are present at the weld location also provide the wall thicknesses (based on UT if available).

See attached table forjoint configuration and thickness. Most of the thicknesses are based on UT. For a few, we took nominal dimensions f rom drawings. On joints involving valves and pumps, the weld thickness at the toe of the weld on the fitting side is about the same as that on the pipe side; however, there is a transition to the thicker body of the valve / pump casing (usually about 30 - 45 ).

(4) What locations are used for taking oxygen samples?

Recirculation Loops A & B; we primarily use A. Taps are located at the pump suction side.

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(5) Was any in-situ ECP tests done (i.e., during the flydrogen Water Chemistry mini-test)?

There were no in-situ measurements (e.g., recirc line decon flange). Measurements were performed in the autoclave which is tapped off the A Recire line, pump suction side.

(6) Which Table I welds (if any) have recordable UT indications?

See attached table.

(7) Rank the 38 Category D RWCU svelds inside containment by susceptibility to IGSCC based on stress, environment, materials, inspection experience, etc.

We have provided all the information we have on these welds. With regard to ranking in terms of susceptibility, we have reached the conclusion that they are all susceptible.

Ilowever, we also conclude that the industry has no means of predicting initiation of cracking in individual weldments, or even within a particular system. For example, in the Attachment

,8., M.

, OC Isolation Condenser system piping outside the drywell, we had cracking in about h 25% of the about 120 welds. We attempted to correlate the cracking with many known variables (e.g., carbon content, environment, operating stresses, etc. and could draw no statistically valid conclusions with regards to the probability of one weld's developing j cracking versus another's. We concluded that this was most likely due to the existence and extent of unknown variables, such as degree of sensitization, amount of residual stress from welding, heat input, starts and stops, etc..

Operating primary stresses (pressure + deadweight) and thermal secondary stresses

, (without Stress Intensificatio.1 Factors) for the RWCU welds are listed in Table 1.

Environment The only difference m environment is the temperature. The RWCU inlet, off the l Recirc system (ND-1), temperature is 520 F; the return line (ND-10) temperature

(; is 412 F. Both lines are considered fully protected by llWC.

Materials - Records from the 1960s were reviewed. The base material is Type 316, l- mostly with a carbon content greater than 0.03%.

Inspection results - No IGSCC has been detected in any RWCU weld. The attached table shows those RWCU welds with recordable indications.

(8) Review past IHSI application data (e.g., temperature gradients, etc.) for the welds in the 17R inspection scope and confirm application effectiveness and conformity to the process

! specifications (especially for complex weld joints).

i L Weld NZ-3-39 was the only Core Spray weld in the 17R scope that had IHSI apolied i outside the recommended parameters. Tne deviation was that the actual through-wall temperature differential (AT) was 263 C vs. the 275 C required by the procedure. An

! engineering anlysis, including finite element analysis, showed that favorable residual p stresses occurred at temperature differentials as low as 208 C. Therefore, it was l concluded that the deviation was technically acceptable. A review of recire weld NG-E-13's records has determined that no Material Non-Conformance Reports (MNCR's) were written against NG-E 13 in 1986. Therefor it is concluded that IIISI was done in j accordance with procedure that in turn was in accordance with Ills! guidelmes. I l

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Table i Oyster Creek 17R Scope Inspection History Page I of 5 System: Closure Head 7 g.

Weld IIR 12R 13R 14R 15R Insp 16R 17R UP DOWM 17R Cat Weld Number Config SI In5P InsP Insp Insp- Insp Results Insp Insp S M NW MV-5-001 F-T 0.52 0.35 No No u Yes No Yes NRI No Yes D MV-5-00l A T-R 0.43 0.34 No No Yes Yes No Yes NR1 No Yes D MV-5-002 T-R 0.44 0.31 No No Yes Yes No Yes NR1 No Yes D NR022-576 N-F 1.64 1.20 No No Yes Yes No Yes NRI No Yes D NR024-570 N-F l.50 1.56 No No No Yes No Yes NRI No Yes D NR026-576 N-F l.16 1.20 No No Yes Yes No Yes NRl/R No Yes D RHC-HS-002 F-R 0 62 0.48 No No No Yes No Yes NRI No Yes D System: Core Spray T T Weld llR 12R 13R l 14R Insp 15R Insp 16R 17R Weld Number Config STR M S SI InsP insp Insp ' Insp Results insp Results Insp Insp NZ-3-039 P-E 0.52 0.52 !2R No Yes No Yes NR1 No No Yes C NZ-1-040 E-P 0.50 0.50 12R Yes N es No Yes NRI No No Yes C NZ-3-042 P-E 0.50 0.50 12R Yes Yes No Yes ISG No l No Yes C NZ-3-082 V-E NA 0.48 No Yes No Yes No Yes NRI l No Yes D NZ-3-Ob3 E-P 0.52 0.52 No Yes No Yes No Yes NR1 '

No Yes D FZ-3-084 P- P 0.52 0.52 12R No Yes No Yes NRI No No Yes C l NZ-3-086 E-P 0.48 0.48 12R No Yes No Yes NRI No No Yes C l NZ-3-083 E-E 0.50 0.52 12R Ne Yes No Yes NRI No No Yes C 1

4 Table 1 Oyster Creek 17R Scope Inspection History Page 2 of 5 Syst m: Isolation Condenser ,

Weld IIR 12R 13R 14R ISR insp 16R 17R Weld Number Config St InSP Insp Insp msp Insp Results Insp insp STR E NE-2-032 E-P 0.51 0.54 ISR No No Yes No Yes NRI No Yer C8

- NE-2-053 P-E 0.51 0.55 ISR Yes No Yes No Yes NRI No Yes Cl N E-2-054 E-P 0.55 0.54 ISR No No Yes No Yes NRI No Yes Cl N E-2-054A P-l' O 54 0.54 15R No No Yes No Yes NRI No Yes CI P-E 0.54 0.59 15R No No Yes No Yes NR1 No Yes Cl-

- NE-2-0$$ No No No Yes CI NE-2-056 E-P 040 0.54 15R No Yes Yes N RI NE-2-057 P-E 0.54 0 64 I5R No Yes Yes No Yes NRI No Yes Cl NE-2-058 E-P 0.62 0.60 ISR No Yes Yes No Yes NRI No Yes Cl N E-2-058A P-P 0.56 0.56 15R No Yes Yes No Yes NR1 No Yes Cl N E-2-059 P-E 0.56 0.66 15R No No Yes No Yes NRI No Yes Cl ,

NE-2-060 E-P 0.58 O.55 ISR No No Yes No Yes NRI No Yes Cl N E-2-061 P-V 0.54 0.593 ISR No Yes Yes No Yes NRI No Yes Cl N E-2-062 V-P 0.593 0.58 ISR N-2 No Yes No Yes NRI No Yes Cl N E-2-063 E-P 0 60 0.60 15R No Yes Yes No Yes NRI No Yes Cl N E-2-06TA P-B 0 60 NA 15R Yes No Yes No Yes NRI No Yes Cl N E t 16 P-P 0.55 0.60 15R Yes No Yes No Yes NRI No Yes Cl NE-2-i l7 P-E 0.52 0.61 15R No No Yes No Yes NR1 No Yes CI NE-2-Il 8 E-P 0.60 0.60 15R No Yes Yes No Yes NRI No Yes Cl NE-2-I l9 P-E 0.56 0.60 ISR No Yes Yes No Yes NRI No Yes Cl ME-2-120 E-P 0.60 0.56 ISR No Yes Yes No Yes NRI No Yes Cl N E-2-121 P-E 0.49 0 60 ISR No No Yes No Yes NRI No Yes CI N E-2-122 E-P 0.60 0.54 ISR Yes No Yes No Yes NR1 No Yes Cl NE-2-l23 P-P 0 60 0.58 ISR No No Yes No Yes NRI No Yes Cl NE-2-124 P-V 0.56 0.64 15R No Yes Yes No Yes NRI No Yes Cl NE-5-20 t P-E 0.56 0.64 15R Yes No Yes No Yes NRI No Yes Cl N E-5-209 E-E 0.76 0.92 15R No No Yes No Yes No Yes Cl k

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a-Table 1 Oyster Creek 17R Scope Inspection History Page 3 of 5 System: Reactor Water Cleanup Weld med hal M P llR 12R 13R I4R ISR insp 16R . 17R Weld Number Config tw/o SIF) 17R Cat MR STR M 51 hsp Insp Insp insp insp Resuhs insp Insp N D-I-001 8-P 0.48 - 0.42 6.8 10.1 No Yes No Yes No Yes NR11SG No Yes D ND-t-003 P-E 0.45 0.50 2.7 8.6 No Yes No Yes No Yes NRI No Yes D ND-t-uo4 E-P 0.50 0.55 2.9 8.6 No No Yes Yes No Yes NRI No Yes D ND-1-004A P-V 0.42 0.40 5.1 62 No No No Yes No Yes NRI No Yes D ND-t-0048 V-P 0.40 0.44 2.5 3A No No Yes Yes No Yes NRI No Yes D N D-1404C P-P 0.42 0.42 49 10.1 No No No Yes No Yes NRI No Yes D ND-t-005 P-E 0.46 0.52 4.8 17.7 No Yes No Yes No Yes NRI No Yes D ND t-006 E-V 0.44 NA 4.5 18.6 No Yes No Yes No Yes NRI No Yes D ND-t-007 V-P NA OAO 4.5 13A No No Yes Yes No Yes NR1 No Yes D ND-14x)8 P-E 0 42 0.45 4.5 4.4 No No No Yes No Yes NR1 No Yes D N D-I-009 E-P O 47 0.42 4.1 1.8 No No No Yes No Yes NR1 No Yes D N D-t-Ol0 P-E 0.42 PA4 4.5 13.7 No No Yes Yes No Yes NRI No Yes D ND-1-011 E-P O 19 0.43 4.8 17.9 No No No Yes No Yes NR1 No- Yes D ND-t-012 P-E O 43 0 49 4.8 18.1 No No No Yes No Yes NRI No Yes D ND-1-Ol 3 E-P 0.48 0.42 48 15.1  % No Yes Yes No Yes NRI No Yes D ND-t-020 P-E 0.42 0.46 6.4 5.6 No No Yes No Yes NRI No Yes D ND-I-021 E-P 0.45 0.43 5.9 7.1 No No Yes No Yes NRI No Yes D ND-l.023 P-T OA4 0.44 97 8.4 la No No Yes No Yes N RI No Yes D N D-t-024 T-P 0 44 0 46 42 8.3 No No No Yes No Yes NRI No Yes D ND-t-027 T-P 0.39 0.45 9.7 8.4 No No No Yes No Yes NRI No Yes D ND-I-027A P-P 0.48 0.42 6.5 4.7 No No No Yes No Yes NRI No . Yes D ND-t-028 P-E OA2 0.52 7.4 6.4 No No No Yes No Yes NRI No Yes D ND-I-029 E-V 0.50 NA 7.8 6.6 No No No Yes No Yes N RI No Yes D ND-10-001 P-B 0.52 0.55 5.5 11.1 No No Yes Yes No Yes NRI No Yes D N D-10-002 E-P 0.53 0.58 13 12.6 No No Yes Yes No Yes NRL ISG No Yes D ND-10wo03 E-E 0.50 OA8 1.2 12.9 No No No Yes No Yes NR1 No Yes D N D-10004 V-E NA 0.48 1.3 10.9 No No No Yes No Yes NRI No D Yes ND-lo 005 P-V 0.50 0.51 0.8 5.8 No No Yes Yes No Yes NRI No Yes D ND-10 006 P-P 0 45 0.45 0.5 3.0 No No Yes Yes No Yes NRI No Yes D i

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e Table 1 Oyster Creek 17R Scope Inspection History Page 5 of 5 System: Shutdown Cooling i Weld ilR 12R 13R 14R 15R Insp

' 16R 17R l Weld Number Config SI In5P insp Insp Insp insp Results 17R Cat STR S insp Insp NU-4-coi a-T Na i.iO i3R so ves Yes No ves NRieisc No Yes , ci NU-4-002 V-T 0.75 0.64 No No No Yes No Yes NRl/ISG No NU-4-003 T-V 0.73 Yes i D 0.75 ISR No No Yes No Yes NR1 No Yes i Cl E = Elbow NRI = No recordable Indications T = Tee ISG = Inside surface geometry P = Pipe R = Root condition V = Valve NA = Not Available (due tojoint configuration)

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