RS-03-201, Additional Information for the Review of the License Renewal Applications for Quad Cities and Dresden Stations

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Additional Information for the Review of the License Renewal Applications for Quad Cities and Dresden Stations
ML033010396
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 10/15/2003
From: Simpson P
Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-03-201
Download: ML033010396 (17)
v • d • e


Text

ExekenM Exelon Generation www.exeloncorp.com Nra 4300 Winfield Road Warrenville, IL 60555 10 CFR 54 RS-03-201 October 15, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket No. 50-237 and-50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Additional Information for the Review of the License Renewal Applications for Quad Cities Nuclear Power Station, Units 1 and 2 and Dresden Nuclear Power Station, Units 2 and 3

References:

(1)

Letter from J. A. Benjamin (Exelon Generation Company, LLC) to U. S. NRC, 'Application for Renewed Operating Licenses,"

dated January 3, 2003 (2)

Letter from Tae Kim (USNRC) to John Skolds (Exelon Generation Company, LLC), "Request for Additional Information for the Review of the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Unit 1 and 2, License Renewal Application,"

dated August 7, 2003 (3)

Letter from Patrick Simpson (Exelon Generation Company, LLC) to U. S. NRC, 'Additional Information for the Review of the License Renewal Applications for Quad Cities Nuclear Power Station, Units 1 and 2 and Dresden Nuclear Power Station, Units 2 and 3," dated October 3, 2003.

Exelon Generation Company, LLC (EGC) is submitting the additional information requested in A D97 Reference 2. This additional information provides a response to RAI 3.1-9, which was inadvertently left out of Reference 3, to support the NRC review of Reference 1.

p q i

October 15, 2003 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions, please contact Al Fulvio at 610-765-5936.

I declare under penalty of perjury that the foregoing is true and correct.

Respectfully, Exec~ted dn' A

Patrick R. Simpson

-Manager - Licensing

Attachment:

Response to Request for Additional Information cc:

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station Illinois Emergency Management Agency

Attachment Response to Request for Additional Information

RAI 3.1-9 (a)

In Section 3.1.1.1.5 of the LRA, the applicant states that thermal stratification, thermal cycling and thermal stripping, thermal transients, and flow accelerated corrosion are potential aging mechanisms for small-bore piping. The LRA also states that a review of the Dresden and Quad Cities Risk Informed Inservice Inspection (RI-ISI) Evaluations on degradation mechanism assessment demonstrated that only Dresden had a high failure potential on a small bore pipe due to thermal fatigue. The inspection will consist of an ultrasonic exam on one of the two-inch drain lines off the Dresden main steam header. These lines are Class 1 and within the scope of License Renewal. The staff has the following comments:

1.

Identify all Class 1, small bore piping in all Units (Dresden, Units 2 and 3, and Quad Cities, Units 1 and 2). Include the pipe sizes, material and type of weld (i.e., butt or socket).: If there are no UT-inspectable full penetration butt welds within scope, then socket welds that are replaced due to modifications should be destructively tested to confirm the effectiveness of the existing AMPs. This is consistent with NUREG-1801,Section XI.M32, which allows a plant-specific destructive examination of replaced piping in lieu of NDE that permits inspection of the inside surfaces of the piping.

2.

As currently written, 10 CFR Part 54 does not allow the staff to accept the elimination of SSCs from aging management based on risk-informed arguments. Therefore, RI-ISI evaluations can be used to select susceptible SSCs locations,. but can not eliminate SSCs from being inspected for a one-time inspection program.. A sampling of butt welds from each unit should be developed, that is consistent with the ASME Code, and is sufficient to confirm the effectiveness of existing AMPs and/or to confirm that there is no need to manage aging-related degradation for the period of extended operation. Inspecting one weld, in one unit is not a sufficient sample size. Provide a sampling plan with a suitable sample size and an explanation of the selection process. This plan should also include a discussion regarding expansion of the inspection sample size and locations for follow up of unacceptable inspection findings as required by NUREG-1801, Section XL.M32. This plan is to be reviewed by the staff on a plant-specific basis, as required by NUREG-1801, Section XL.M32.

3.

Section 3.1.1.1.5 of the LRA does not specify an inspection program for stress corrosion cracking (SCC) as an aging mechanism in small bore piping. What programs will be used to manage SCC in small bore piping?

(b)

The applicant stated that, for this AMP, the one-time inspection program for small-bore Class 1 piping less than 4 inches will consist of an ultrasonic exam on one of the two-inch drain lines off the Dresden main steam header. These lines were identified as part of a review of the Dresden and Quad Cities Risk Informed Inservice Inspection (RISI) degradation mechanism assessments on Class 1 piping. The aging mechanisms cited by the report'for these lines are thermal stratification, cycling, and stripping (TASCS), thermal transients (TT), and flow accelerated corrosion. Nuclear industry service experience, documented in several industry and NRC reports, has shown that the majority of reported piping leaks occur in small bore piping less then 4-inch NPS. A significant number of 1I

these failures have been reported in reactor coolant system, main steam system, feedwater system, and auxiliary systems in BWR plants. Also, a large portion of the reported Class 1 small bore piping failures occurred in piping 1-inch NPS and less that were caused primarily by mechanical vibration, thermal fatigue/turbulent penetration, stress corrosion cracking, and erosion-corrosion aging mechanisms.

Since Class 1 small bore piping 1-inch NPS and less are exempt from NDE examinations in ASME Section Xl, these lines will typically receive only periodic VT-2 visual examination. In addition, many RI-ISI evaluations do not include Class I piping 1-inch NPS and less in their evaluation scope and specific degradation mechanism assessments are not performed for these lines. Therefore, it is not clear that the applicant's proposed one-time inspection program for small-bore piping will be representative of all Class 1 piping 1-inch NPS and less with full penetration butt welds (socket welds are excluded).

The applicant is requested to clarify whether the Dresden and Quad Cities Risk Informed Inservice Inspection (RI-ISI) degradation mechanism assessments included Class 1 piping 1-inch NPS and less with full penetration butt welds. Also describe how the proposed one-time inspection program will confirm that the aging mechanisms associated with the Class 1 small-bore 'piping 1-inch NPS and less with full penetration butt welds at Dresden and Quad Cites are either not occurring and/or there is no need to manage age-related degradation for the period of extended operation.

Response

(a)

1. The following tables provide'a listing of the ASME Class 1, NPS <4" piping for Dresden Units 2 & 3 and Quad Cities Units 1 & 2. As there are full penetration butt welds that can be UT-inspected at Dresden and Quad Cities, no destructive examinations will be performed of the socket welds.

Unit System Line No.

Material Weld Drawing (Coordinates)

Type and Comments D-2 Reactor 2-020A-28" A Stainless Steel Butt LR-DRE-M-26-2 (C-7)

Recirculation 3" Branch to Decon Conn.

Only, D-2 Reactor 2-020B-28" A Stainless Steel' Butt LR-DRE-M-26-2 (C-2)

Recirculation 3" Branch to Decon. Conn.

D-2 Reactor 2-0203B-4" A Stainless Steel Butt LR-DRE-M-26-2 (D-3)

Recirculation 4 x 3" and 3" flange only D-2 Reactor 2-0203A-4" A Stainless Steel Butt' LR-DRE-M-26-2 (D-5)

Recirculation 4 x 3" and 3" flange only D-2 Nuclear Boiler 2-0304-2%" A Stainless Steel Butt LR-DRE-M-26-1 (A-4/6)

Instrumentation Also includes Test line tap D-2 Standby Liquid 2-1102-1%" A Stainless Steel Butt LR-DRE-M-26-1 (E-7)

Control and 2" and 2" section only at Nozzle N-12 Socket D-2 Nuclear Boiler 2-0284-1" RV Stainless Steel Butt LR-DRE-M-26-1 (B/D-4/6)

Instrumentation and From Nozzle N-13A Line Socket contains 3" Dia. Condensing 2

Unit System Line No.

Material Weld Drawing (Coordinates)

T and Comments Chamber and Reservoir D-2 Nuclear Boiler 2-0285-1" RV Stainless Steel Butt LR-DRE-M-26-1 (B/D-617)

Instrumentation and From Nozzle N-13B Socket Line contains 3" Dia.

Condensing Chamber and Reservoir D-2 Nuclear Boiler 1" Instrument Stainless Steel Butt LR-DRE-M-26-1 (C-5)

Instrumentation Line from Nozzle and N-16A Socket D-2 Nuclear Boiler 1" Instrument Stainless Steel Butt LR-DRE-M-26-1 (C-7)

Instrumentation Line from Nozzle and N-16B Socket D-2 Main Steam 2-3007-2" B Carbon Steel Butt LR-DRE-M-12-1 (E-3/4) and LR-DRE-M-12-2 (E-8)

Socket D-2 Feedwater 2-32169-%" C Carbon Steel Socket LR-DRE-M-14 (E-3)

Covers both lines D-2 Feedwater

/4" Carbon Steel Socket LR-DRE-M-14 (F-3)

Covers both the test and hose connections.

D-2 Core Spray 2-1451-3/4" A Stainless Steel Socket LR-DRE-M-27 (C/D-3)

D-2 Core Spray 2-1452-3/4" A Stainless Steel Socket LR-DRE-M-27 (C/D-4)

D-2 Core Spray 2-1411-3/4" ECCS Carbon Steel Socket LR-DRE-M-27 (C-2)

D-2 Core Spray 2-1413-4" ECCS Carbon Steel Socket LR-DRE-M-27 (C-5)

D-2 Core Spray 3/4" Bypass lines Stainless Steel Socket LR-DRE-M-27 (E-2, Detail A) around 2-1402-9A/B D-2 Isolation 2-1358-3/4" A Stainless Steel Socket LR-DRE-M-28 (C-10)

Condenser D-2 Isolation 2-1305-/4" A Stainless Steel Socket LR-DRE-M-28 (C-9)

Condenser D-2 Isolation Instr. Lines to Stainless Steel Socket LR-DRE-M-28 (E-8)

Condenser DPIS 2-1349 D-2 Isolation Drain Line to Vlv.

Stainless Steel Socket LR-DRE-M-28 (E-8)

Condenser 2-1301-604 D-2 Isolation Vent Line to Vlv.

Stainless Steel Socket LR-DRE-M-28 (E-7)

Condenser 2-1301-601 D-2 Reactor Water 2-12126-2" A Stainless Steel Socket LR-DRE-M-30 (A-3)

Clean-Up D-2 Reactor Water 2-12116-/2" A Stainless Steel Socket LR-DRE-M-30 (A-3)

Clean-Up D-2 Reactor Water 2-1233-1" A Stainless Steel Socket LR-DRE-M-30 (BA)

Clean-Up' D-2 Reactor Water Drain line to Vlv.

Stainless Steel

  • Socket LR-DRE-M-30 (B-3)

Clean-Up 2-1299-11 D-2 Shutdown Drain Lines A, B, Carbon Steel Socket LR-DRE-M-32 (A, C & E-9)

Cooling

& C to RBEDT (B) 3

Unit System Line No.

Material Weld.

Drawing (Coordinates),

Type and Comments D-2

. Shutdown Vent Line to Vlv.

Carbon Steel Socket LR-DRE-M-32 (C-9)

Cooling 2-1001-47A (B)

D-2 Shutdown 1" Line to Relief Carbon Steel Socket LR-DRE-M-32 (C-9)

Cooling Vlv. 2-1099-29 (B)_'

D-2 Shutdown 2-1020A-3/4" B Carbon Steel Socket LR-DRE-M-32 (B-9)

_ C ooling D-2 Shutdown Line to Vlv. 2-Carbon Steel Socket LR-DRE-M-32 (C-9)

Cooling 1001-200 (B)

D-2 Shutdown Vent Line to Viv.

Carbon Steel Socket LR-DRE-M-32 (D-9)

Cooling 2-1001-47B (B)

D-2 Shutdown 2-1020B-%" B Carbon Steel Socket LR-DRE-M-32 (D-9)

Cooling D-2 Standby Liquid 2-1102-1%" A Stainless Steel Socket LR-DRE-M-33 (D-3)

Control D-2 High Pressure 2-2346-3/4" B Carbon Steel Socket LR-DRE-M-51 (D-1)

Coolant Injection D-2 Control Rod 2-0314-1" Stainless Steel Socket LR-DRE-M-34-2 (D-10)

Drive Hydraulic D-2 Control Rod 2-0341-%"

Stainless Steel Socket LR-DRE-M-34-2 (D-9)

.___._ Drive Hydraulic D-2 Control Rod 2-0342-%2 Stainless Steel Socket LR-DRE-M-34-2 (D-10)

Drive Hydraulic D-2 Control Rod 2-0336-Ye" Stainless Steel Socket LR-DRE-M-34-2 (C/E-9)

Drive Hydraulic D-2 Control Rod' 2-0317-2" Stainless Steel Socket LR-DRE-M-34-2 (C/D-10)

Drive Hydraulic D-2

. High Pressure 1" Instr. Lines to Stainless Steel Socket LR-DRE-M-51 (DIC-112)

Coolant DPT 2-2352 to Drawing shows this as a 3/"

Injection

. Vlv. 2-2301-26 line and 27 D-2 Reactor 2 1" Lines to FT Stainless Steel Socket LR-DRE-M-26-2 (D-1/3)

'Recirculation' 2-261-6C D-2 Nuclear Boiler 8 - Ye" and 1" Stainless Steel Socket LR-DRE-M-26-1 (D-5).

Instrumentation lnstr. Lines from Nozzle N-20A D-2 Nuclear Boiler Ye" and 1" Stainless Steel Socket LR-DRE-M-26-1 (D-5)

Instrumentation Instrument Line JP 6 (upper)

D-2 Nuclear Boiler

%" and 1",

Stainless Steel Socket LR-DRE-M-26-1 (D-5)

Instrumentation Instrument Line JP I (upper)

D-2 Nuclear Boiler Ye" and 1" Stainless Steel Socket LR-DRE-M-26-1 (D-5)

Instrumentation Instrument Line JP 1 (lower)

D-2 Nuclear Boiler Ye" and 1" Stainless Steel Socket LR-DRE-M-26-1 (E-5)

Instrumentation Instrument Line 4.

Unit System Line No.

Material Weld Drawing (Coordinates)

.____.___,___Tjype and Comments JP 6 (lower)

D-2 Nuclear Boiler 8 - 3/4" and 1" Stainless Steel Socket LR-DRE-M-26-1 (D-7)

Instrumentation Instrument Lines from Nozzle N-20B D-2 Nuclear Boiler 3/4".and 1".

Stainless Steel Socket LR-DRE-M-26-1 (D-7)

Instrumentation Instrument Line JP 16 (upper)

D-2 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-26-1 (D-7)

Instrumentation Instrument Line JP 11 (upper)

D-2 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-26-1.(D-7)

Instrumentation Instrument Line JP 11 (lower) -_._.

D-2 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-26-1 (E-7)

Instrumentation Instrument Line JP 16 (lower).

D-2 Nuclear Boiler 1" Core Plate DP Stainless.Steel Socket LR-DRE-M-26-1 (E-5)

Instrumentation Lines D-2 Nuclear Boiler 2-0260-1/2" A Stainless Steel Socket LR-DRE-M-26-1 (B-5)

Instrumentation D-2 Reactor Vessel 2-0214-2" H Stainless Steel Socket LR-DRE-M-26-1 (B-7)

Head Vent LR-DRE-M-12-1 (E-5)

D-2 Nuclear Boiler 2-0299A-%" A Stainless Steel Socket LR-DRE-M-26-1 (C-5)

Instrumentation LR-DRE-M-26-3 (F-8)

D-2.

Nuclear Boiler 2-0299B-1/2" A Stainless Steel Socket LR-DRE-M-26-1 (C-7)

Instrumentation LR-DRE-M-26-3 (F-1)

D-2 Nuclear Boiler 2-0299A-3/4" A Stainless Steel Socket LR-DRE-M-26-1 (E-5)

Instrumentation D-2 Nuclear Boiler 2-029983-3/4" A

. Stainless Steel.

Socket LR-DRE-M-26-1 (E-7)

Instrumentation D-2 Nuclear Boiler 2-0308-3" A Stainless Steel Socket LR-DRE-M-26-1 (E-7)

Instrumentation D-2 Low Pressure 2-1537-%3/4" A -

Stainless Steel Socket LR-DRE-M-29-1 (B-4)

Coolant Injection D-2 Low Pressure 2-1538-3/4" A Stainless Steel Socket LR-DRE-M-29-1 '(B-6)

Coolant Injection D-2 Low Pressure 2-1519-3/4" A

Stainless Steel Socket LR-DRE-M-29-1 (B-3)

Coolant Injection D-2 Low Pressure 2-1506-3/4" A Stainless Steel Socket LR-DRE-M-29-1 (B-7)

Coolant Injection D-2 Nuclear Boiler 2-0296B-Y2" A Stainless Steel Socket LR-DRE-M-26-3 (D/E-2-5)

Instrumentation D-2 Nuclear Boiler 4 -

3/4" and 1".

Stainless Steel Socket LR-DRE-M-26-2 (F-5)S 5

Unit System Line No.

Material Weld Drawing (Coordinates)

Type and Comments Instrumentation Instrument Lines through Penetration X-146 D-2 Nuclear Boiler 4 - 3/4" and 1" Stainless Steel Socket LR-DRE-M-26-2 (F-4)

Instrumentation Instrument Lines through Penetration X-208 D-2 Reactor 10- 3/4" Decon Stainless Steel Socket LR-DRE-M-26-2 (E-4)

Recirculation Taps D-2 Reactor 2-0390-A/4". A Stainless Steel Socket LR-DRE-M-26-2 (8-7)

Recirculation D-2 Reactor 2-02100A-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (B-6)

Recirculation D-2 Reactor 2-0204A-2" L Carbon Steel Socket LR-DRE-M-26-2 (B-6)

Recirculation D-2 Reactor 2-0225A-3/4" L Carbon Steel Socket LR-DRE-M-26-2 (D-6)

Recirculation D-2 Reactor.

2-0231A-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (D-5)

Recirculation D-2 Reactor 2-0228A-3/4" L Carbon Steel Socket LR-DRE-M-26-2 (C-5)

Recirculation D-2 Reactor 2" line around for Stainless Steel Socket LR-DRE-M-26-2 (C-5)

Recirculation valve

._ 2-0202-9A D-2 Reactor 2-0220A-3/4" L Carbon Steel Socket LR-DRE-M-26-2 (C-5)

Recirculation D-2 Reactor 2-021 00B-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (B/C-2)

Recirculation and Carbon Steel D-2 Reactor 2-02102-3%" A Stainless Steel Socket LR-DRE-M-26-2 (E-2)

Recirculation D-2.

Reactor 2-0233-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (E-2)

Recirculation D-2 Reactor 2-02258-Y4" L Carbon Steel Socket LR-DRE-M-26-2 (D-3)

Recirculation D-2 Reactor 2-0231 B-%e" A Stainless Steel Socket LR-DRE-M-26-2 (D-3)

Recirculation D-2 Reactor 1" Lines to DPT: Stainless Steel Socket LR-DRE-M-26-2 (8-3)

Recirculation 2-261-513 D-2 Reactor 2-0207-2" A Stainless Steel Socket LR-DRE-M-26-2 (D/C-4)

Recirculation D-2 Reactor Water

.2-1265-2" A Stainless Steel Socket LR-DRE-M-26-2 (D/C-4)

Cleanup LR-DRE-M-30 (A-3)

D-2 Reactor 2-02288-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (C-3)

Recirculation D-2 Low Pressure 3/4" Bypass lines Stainless Steel Socket. LR-DRE-M-29-2 (B-6, Detail Coolant around 2-1501-25 A) 6

Unit System Line No.

Material Weld Drawing (Coordinates)

. and Comments Injection A&B D-2 Reactor 2-0220B-3/4" A Stainless Steel Socket LR-DRE-M-26-2 (C-3/4)

Recirculation D-2 Nuclear Boiler 2-0299A-12" A Stainless Steel Socket LR-DRE-M-26-3 (D-7)

Instrumentation D-2 Nuclear Boiler 2-0299B-Yz" A Stainless Steel Socket LR-DRE-M-26-3 (D-3)

Instrumentation D-2 Reactor Vessel 2-0214-2" B Carbon Steel Socket LR-DRE-M-12-1 (D-4/5)

Head Vent LR-DRE-M-26-1 (B-617)

D-2 Nuclear Boiler 2-0392-1/2" A Stainless Steel Socket LR-DRE-M-26-1 (B-5/6)

Instrumentation D-2 Nuclear Boiler 1" Line from Carbon Steel Socket LR-DRE-M-26-1 (AIB-516)

Instrumentation Nozzle N-8 through the condensing chamber D-2 Reactor Vessel 2-0215-2" A Stainless Steel Socket LR-DRE-M-26-1 (AIB-6/7),

Head Vent D-2 Reactor 1" Lines to the Stainless Steel Socket LR-DRE-M-26-2 (B-6/7)

Recirculation DPT 2-261-5A D-2 Reactor 1" Instrument Stainless Steel Socket LR-DRE-M-26-2 (D-6/8)

Recirculation Lines to FT 2-261 -6A D-2 Nucle'ar Boiler 2-0296A-12" A' Stainless Steel Socket LR-DRE-M-26-3 (D/E-6-8)

Instrumentation D-2 Isolation Instr. Lines to Stainless Steel Socket LR-DRE-M-28 (C-9/10)

Condenser DPIS 2-1350 D-2 Control Rod 2-0338-1" Stainless Steel Socket LR-DRE-M-34-2 (E/D-9/10)

.____ Drive Hydraulic, D-2 Main Steam 2-3007A-1%" B Carbon Steel Socket LR-DRE-M-12-1 (E-4)

D-2 Main Steam 2-30071-1 2" B Carbon Steel Socket LR-DRE-M-1 2-1 (D-4)

D-2 Main Steam 2-3007C-1% B Carbon Steel Socket LR-DRE-M-12-1 (C-4)

D-2 Main Steam 2-3007D-1%" B Carbon Steel Socket LR-DRE-M-12-1 (A-4)

D-2 Main Steam 2-3009- %" D Carbon Steel Socket LR-DRE-M-12-1 (E-3)

D-2 Main Steam 1" Instr. Line Stainless Steel Socket LR-DRE-M-12-1 (A/E-4)

From Flow Elem.

LR-DRE-M-12-2 (A/E-8) 2-261-1A;B,C & D to DPIS 2-261-2 D-2 Main Steam 1" MSIV Test Carbon Steel Socket LR-DRE-M-12-2 (Detail B at F-connection to 6)

Valve 2-220-10A, B, C, and D Unit System Line No.

Material Weld Drawing (Coordinates)

Type and Comments D-3 Nuclear Boiler.

3-0304-22' A.

Stainless Steel Butt LR-DRE-M-357-1 (F-4/6)

Instrumentation Also includes Test line tap.

D-3 Reactor Decon Conn 3"

- Stainless Steel Butt LR-DRE-M-357-2 (C-6) 7.-

Unit System Line No.

Material Weld.

Drawing (Coordinates)

Type and Comments Recirculation AM D-3 Reactor Decon Conn 3" Stainless Steel Butt LR-DRE-M-357-2 (D-3)

Recirculation AM D-3 Reactor Decon l Stainless Steel Butt LR-DRE-M-357-2 (D-4)

Recirculation Connection 3" AM D-3 Reactor Decon Conn 3" Stainless Steel Butt LR-DRE-M-357-2 (D-4)

Recirculation AM D-3 Reactor Decon Stainless Steel Butt LR-DRE-M-357-2 (D-4/5)

Recirculation Connection 3" AM D-3 Standby Liquid 3-1102-1%"2A Stainless Steel Butt LR-DRE-M-357-1 (A-5)

Control and 2" and

.2" section only at Nozzle N-12 S o c k e t D-3 Nuclear Boiler 3-0285-1" RV Stainless Steel Butt LR-DRE-M-357-1 (DIE-2/4)

Instrumentation and From Nozzle N-13B Line Socket contains 3" Dia. Condensing Cham ber and Reservoir D-3 Nuclear Boiler 3-0284-1" RV Stainless Steel Butt LR-DRE-M-357-1 (DIE-5/7)

Instrumentation and From Nozzle N-13A Line' Socket contains 3" Dia. Condensing C ham ber and R eservoir D-3 Main Steam 3-3007-2" B Carbon Steel Butt LR-DRE-M-345-1 (BIF-718) and LR-DRE-M-345-2 (E-7/8)

__._ __._ _ _._ S o c k e t D-3 Nuclear Boiler 1" Instrument Stainless Steel Butt LR-DRE-M-357-1 (D-4)

Instrumentation Line from Nozzle and

.__ N-1 6B Socket D-3 Nuclear Boiler 1" Instrument Stainless Steel Butt LR-DRE-M-357-1 (D-5) instrumentation Line from Nozzle and N-16A Socket D-3 Main Steam 3-3007D-1%" B Carbon Steel Socket LR-DRE-M-245345-1 (E-7)

D-3 Main Steam 1" Instr. Line Stainless Steel Socket LR-DRE-M-345-1 (BIF-618)

From Flow Elem.

LR-DRE-M-345-2 (B/E-8) 3-261-lA,BC.& D to DPIS 2-261-2 D-3 Main Steam 3-3007A-1 %" B Carbon Steel Socket LR-DRE-M-345-1 (B-7)

D-3 Main Steam 3-3009- %" D Carbon Steel Socket LR-DRE-M-345-1 (B-8)

D-3 Main Steam 3-3007B-1%" B Carbon Steel Socket LR-DRE-M-345-1 (C-7)

D-3 Reactor Vessel 3-0214-2" B Carbon Steel Socket LR-DRE-M-345-1 (C-7)

Head Vent LR-DRE-M-357-1 (E-4)

D-3 Main Steam 3-3007C-11/2" B Carbon Steel Socket LR-DRE-M-345-1 (D-7)

D-3 Main Steam 1" MSIV Test Carbon Steel Socket LR-DRE-M-345-2 (Detail B at connection to F-5)

Valve 3-220-10 A,.

B, C, andD D-3 Feedwater 3-32169-3/4" C Carbon Steel Socket LR-DRE-M-347 (E-3)

C o vers b o th line s.

D-3 Feedwater Y/4" Carbon Steel Socket LR-DRE-M-347 (F-3)

C overs both the test and hose 8...

Unit System Line No.

Material Weld Drawing (Coordinates)

Type and Comments

_ connections.

D-3 Reactor Vessel 3-0214-2" H Stainless Steel Socket LR-DRE-M-357 (E-4)

.__ Head Vent D-3 Nuclear Boiler 8 - 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (B/C-5)

Instrumentation Instrument Lines from Nozzle N-

-_ 20A D-3 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (8-4)

Instrumentation Instrument Line JP 16 (lower)

D-3 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (B-5)

Instrumentation Instrument Line

____________ JP 6 (lower)

D-3 Nuclear Boiler 1" Core Plate DP Stainless Steel Socket LR-DRE-M-357-1 (B-5)

Instrumentation Lines D-3 Nuclear Boiler 8 - 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (C-4)

Instrumentation Instrument Lines from Nozzle N-20B D-3 Nuclear Boiler 3/4" and I" Stainless Steel Socket LR-DRE-M-357-1 (C-A)

Instrumentation Instrument Line JP 16 (upper)

D-3 Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (C-4)

Instrumentation Instrument Line JP 11 (upper)

D-3

. Nuclear Boiler 3/4" and 1" Stainless Steel Socket LR-DRE-M-357-1 (C-4)

Instrumentation Instrument Line JP 11 (lower)

D-3. Nuclear Boiler and 1" Stainless Steel Socket LR-DRE-M-357-1 (C-5)

Instrumentation Instrument Line JP 6 (upper)

D-3 Nuclear Boiler

%" and 1" Stainless Steel Socket LR-DRE-M-357-1 (C-5)

Instrumentation Instrument Line JP 1 (upper)

D-3 Nuclear Boiler 3/4".and 1" Stainless Steel Socket, LR-DRE-M-357-1 (C-5)

Instrumentation Instrument Line JP 1 (lower)

D-3 Nuclear Boiler 3-0299B-62' A Stainless Steel Socket LR-DRE-M-357-1 (D-3)

Instrumentation

._._LR-DRE-M-357-3 (F-1)

D-3 Nuclear Boiler 3-0299A-Y2" A Stainless Steel Socket LR-DRE-M-357-1 (D-5)

Instrumentation LR-DRE-M-357-3 (F-8)

D-3 Nuclear Boiler 3-0260-%" A Stainless Steel Socket LR-DRE-M-357-1 (E-5)

Instrumentation D-3 Nuclear Boiler 3-0392-'2" A Stainless Steel.

Socket LR-DRE-M-357-1 (E-5/6)

Instrumentation D-3 Nuclear Boiler 2-0408-3" A Stainless Steel Socket LR-DRE-M-357-1 (E-7)

Instrumentation l D-3 Reactor Vessel 2-0215-2" A Stainless Steel Socket LR-DRE-M-357-1 (F/EA) 9

Unit System Line No.

Material Weld Drawing (Coordinates)

_Type and Comments Head Vent D-3 Nuclear Boiler 1" Line from Carbon Steel Socket LR-DRE-M-357-1 (F/E-516)

Instrumentation Nozzle N-8 through the condensing

. chamber D-3 Reactor 3-021 00B-3/4" A Stainless Steel Socket LR-DRE-M-357-2 (B/C-2)

Recirculation and Carbon S te e l D-3 Reactor 1" Lines to DPT Stainless Steel Socket LR-DRE-M-357-2 (B-3)

Recirculation 3-261-5B1 D-3 Reactor 3-021 00A-%" A Stainless Steel Socket LR-DRE-M-357-2 (B-6)

Recirculation D-3 Reactor 3-0204A-2" L Carbon Steel Socket LR-DRE-M-357-2 (B-6)

Recirculation D-3 Reactor 1" Lines to the Stainless Steel Socket LR-DRE-M-357-2 (B-6/7)

Recirculation DPT 2-262-1 OC D-3 Reactor 3-0390-3/4" A Stainless Steel Socket LR-DRE-M-357-2 (B-7)

Recirculation D-3 Reactor.

2-0217A-Y4 'A Stainless Steel Socket LR-DRE-M-357-2 (C-6)

Recirculation D-3 Reactor 3-0207-2" A Stainless Steel Socket LR-DRE-M-357-2 (D/C-4)

Recirculation D-3 Reactor Water 3-1265-2" A Stainless Steel Socket LR-DRE-M-357-2 (D/C4)

Cleanup LR-DRE-M-361 (A-3)

D-3 Reactor 2 1" Lines to FT Stainless Steel Socket LR-DRE-M-357-2 (D-1/3)

Recirculation 3-261-6C D-3 Reactor 3-0225B-3/4" L Carbon Steel Socket LR-DRE-M-357-2 (D-3)

Recirculation D-3

. Reactor 3-0231B-Y41" A Stainless Steel Socket LR-DRE-M-357-2 (D-3)

Recirculation D-3 Reactor 3-0231 B-%" A Stainless Steel Socket LR-DRE-M-357-2 (D-3)

Recirculation.

D-3 Reactor 3-0231A-3/4" A Stainless Steel Socket LR-DRE-M-357-2 (D-5)

Recirculation D-3 Reactor 3-0225A-3/4" L Carbon Steel Socket LR-DRE-M-357-2 (D-6)

Recirculation D-3 Reactor 1" Instrument Stainless Steel Socket LR-DRE-M-357-2 (D-6/8)

Recirculation Lines to FT 3-261-6A D-3 Reactor 3-02102-%" A Stainless Steel Socket LR-DRE-M-357-2 (E-2)

Recirculation D-3 Reactor 3-0233-Y 4" A Stainless Steel Socket LR-DRE-M-357-2 (E-2)

Recirculation D-3 Nuclear Boiler 4 - %" and 1" Stainless Steel Socket LR-DRE-M-357-2 (F-4)

Instrumentation Instrument Lines through.

.___ _Penetration X-10.

Unit System Line No.

Material Weld Drawing (Coordinates)

.__Type'__

and Comments 151 D-3 Nuclear Boiler 4 -%" and 1" Stainless Steel Socket LR-DRE-M-357-2 (F-5)

Instrumentation Instrument Lines through Penetration X-

.___ __141 D-3 Nuclear Boiler 3-0299A-Y1" A

Stainless Steel Socket LR-DRE-M-357-3 (BIC-213)

Instrumentation D-3 Nuclear Boiler 3-0296B-Y" A Stainless Steel Socket LR-DRE-M-357-3 (BIC-619)

Instrumentation D-3 Nuclear Boiler 3-0299B-Y2" A Stainless Steel Socket LR-DRE-M-357-3 (BIC-7/9)

Instrumentation D-3 NuclearBoiler 3-0296A-%" A Stainless Steel Socket LR-DRE-M-357-3 (B-2/4)

Instrumentation D-3 Core Spray 3-1451-%4" A Stainless Steel Socket LR-DRE-M-358 (CID-3)

D-3 Core Spray 3-1452-Y/4" A Stainless Steel Socket LR-DRE-M-358 (CID-4)

D-3 Core Spray 3-141 1-W" ECCS Carbon Steel Socket LR-DRE-M-358 (C-2)

D-3 Core Spray 3-1413-3/4" ECCS Carbon Steel Socket LR-DRE-M-358 (C-5)

D-3 Core Spray 3-1423A-%" A Stainless Steel Socket LR-DRE-M-358 (E-2, Detail A)

D-3 Core Spray 3-1423C-%" A Stainless Steel Socket LR-DRE-M-358 (E-2, Detail B)

D-3 Isolation 3-1305-3/4" A Stainless Steel Socket LR-DRE-M-359 (C-10)

Condenser D-3 Isolation 3-1302-3/4" A Stainless Steel Socket LR-DRE-M-359 (C-9)

Condenser D-3 Isolation Instr. Lines to Stainless Steel Socket LR-DRE-M-359 (C-9110)

Condenser DPIS 3-1350 D-3 Isolation.

3-1309-3/4" A Stainless Steel Socket LR-DRE-M-359 (E-7)

Condenser D-3 Isolation Instr. Lines to Stainless Steel Socket LR-DRE-M-359 (E-8)

Condenser DPIS 3-1349 D-3 Isolation 3-131OB-1/ A Stainless Steel Socket LR-DRE-M-359 (E-8)

Condenser D-3 Isolation 3-1301-3/4" A Stainless Steel Socket LR-DRE-M-359 (E-819)

Condenser D-3 Low Pressure 3-1519-1" A Stainless Steel Socket LR-DRE-M-360-1 (B-3)

Coolant Injection D-3 Low Pressure 3-1537-3/4" A Stainless Steel Socket LR-DRE-M-360-1 (B-4)

Coolant Injection D-3 Low Pressure 3-1538-34" A Stainless Steel Socket LR-DRE-M-360-1 (B-6)

Coolant Injection '

D-3 Low Pressure 3-1506-1" A Stainless Steel Socket LR-DRE-M-360-1 (B-7)

Coolant Injection D-3 Low Pressure :

" Bypass lines Stainless Steel Socket LR-DRE-M-360-2 (B-6, Detail Coolant around 3-1501-25

.A and B) 11

Unit System Line No.

Material Weld.

Drawing (Coordinates)

Type and Comments Injection.

A&B D-3 Reactor Water 3-12126-2" A Stainless Steel Socket.LR-DRE-M-361 (A-3)

Clean-Up D-3 Reactor Water 3-12120-%" A Stainless Steel Socket LR-DRE-M-361 (A-3)

Clean-U p D-3 Reactor Water.

3-1265-2" AM Stainless Steel Socket LR-DRE-M-361 (A-3)

Clean-Up D-3 Reactor Water.

3-1233-1" A Stainless Steel Socket LR-DRE-M-361 (B-4)

. Clean-Up D-3 Shutdown Drain Lines A, B, Carbon Steel Socket LR-DRE-M-363 (A, C & E-8).

Cooling

& C to RBEDT (B)

D-3 Shutdown 3-1020A-3 4" B Carbon Steel Socket LR-DRE-M-363 (B-9)

Cooling D-3 Shutdown Vent Line to Vlv.

Carbon Steel Socket LR-DRE-M-363 (C-9)

Cooling 3-1001-47A (B)

I D-3 Shutdown 1" Line to Relief Carbon Steel Socket LR-DRE-M-363 (C-9)

Cooling Vlv. 3-1099-29 (B)...

D-3 Shutdown 3-10130- W" B Carbon Steel Socket LR-DRE-M-363 (C-9)

Cooling D-3 Shutdown Vent Line to Vlv.

Carbon Steel Socket LR-DRE-M-363 (D-9)

Cooling 3-1001-47B (B)

D-3 Shutdown 3-1020B-%" B Carbon Steel Socket LR-DRE-M-363 (D-9)

Cooling D-3 Standby Liquid 3-1102-1 %" A Stainless Steel Socket LR-DRE-M-364 (D-2)

Control D-3 Control Rod' 3-0338A-1" Stainless Steel Socket LR-DRE-M-365-2 (C/D-112)

Drive Hydraulic D-3

. Control Rod 3-0314-1" Stainless Steel Socket LR-DRE-M-365-2 (C-1)

Drive Hydraulic D-3 Control Rod.

2-0336A-3/4" Stainless Steel Socket LR-DRE-M-365-2 (D/C-2)

Drive Hydraulic D-3 Control Rod 3-0342A-'/2" Stainless Steel Socket LR-DRE-M-365-2 (D-1)

Drive Hydraulic D-3 Control Rod 3-0317A-%"

Stainless Steel Socket LR-DRE-M-365-2 (D-1)

Drive Hydraulic D-3 Control Rod 3-0341A-y2" Stainless Steel. Socket LR-DRE-M-365-2 (D-2).

Drive Hydraulic' D-3 High Pressure 3/4" Instr. Lines to Stainless Steel Socket LR-DRE-M-374 (D/C-1/2)

Coolant

. DPT 3-2352 to Injection Vlv. 3-2301-26

.___.and 27 D-3 High Pressure 3-2346-3/4" B Carbon Steel Socket LR-DRE-M-374 (D-1)

Coolant Injection 12

Unit System Line No.

Material Weld.

Drawing (Coordinates)

Type and Comments Q-1 Reactor Water 1-1265-3"A Stainless Steel Butt LR-QDC-M-35-1 (G-5)

Cleanup

.3" spool is not shown on drawing but exists between valve 1-0220-65 and the 6" RWCU line Q-1 Reactor 1-0202A-28"A Stainless Steel Butt LR-QDC-M-35-2 (E-2)

Recirculation A 3" Branch connection to a Decontamination Flange Q-1 Reactor 1-0202B-28"A Stainless Steel Butt LR-QDC-M-35-2 (E-9)

Recirculation A 3" Branch connection to a Decontamination Flange Q-1 Standby Liquid 1-1102-11/2" A Stainless Steel Butt LR-QDC-M-35-1 (C-4 and Control and 2" and Detail A) Butt welds on 2" Socket section only at Nozzle N-10.

Q-1 Nuclear Boiler 1-0300-2"A Stainless Steel Socket LR-QDC-M-35-1 (D-4)

Instrumentation At Nozzle N-12A Q-1 Nuclear Boiler 1-0299-2"A Stainless Steel Socket LR-QDC-M-35-1 (D-5)

Instrumentation At Nozzle N-12A Q-1 Nuclear Boiler 1-0207-2"C Carbon and Socket LR-QDC-M-35-1 (G-5)

Instrumentation Stainless Steel '

Q-1 Reactor Water 1-1 265-2"A Stainless Steel Socket LR-QDC-M-35-1 (G-5)

Cleanup LR-QDC-M-47-1 (C-5)

Q-1 Reactor 1-0209A-2"A Stainless Steel Socket LR-QDC-M-35-2 (D-5)

Recirculation Q-1 Reactor 1-0209B-2"A Stainless Steel Socket LR-QDC-M-35-2 (D-6)

Recirculation Q-1 Reactor 1-0204A-2"A Stainless Steel Socket LR-QDC-M-35-2 (E-3)

Recirculation Q-1 Reactor 1-0204B-2"A Stainless Steel Socket LR-QDC-M-35-2 (E-8)

Recirculation Unit System Line No.

Material Weld Drawing (Coordinates)

.Type-and Comments Q-2 Reactor Water 2-1265-3"A Stainless Steel Butt LR-QDC-M-77-1 (G-5)

'Cleanup 3" spool is not shown on drawing but exists between valve 1-0220-65 and the 6" RWCU line Q-2 Reactor 2-0202A-28"A Stainless Steel Butt LR-QDC-M-77-2 (E-2)

Recirculation A 3" Branch connection to a

.___ _Decontamination Flange Q-2 Reactor 2-0202B-28"A Stainless Steel Butt LR-QDC-M-77-2 (E-9)

Recirculation A 3" Branch connection to a Decontamination Flange Q-2 Standby Liquid 2-1102-1 z" A Stainless Steel Butt LR-QDC-M-77-1 (C-4 and Control and 2" and Detail A) Butt welds on 2" Socket section only at Nozzle N-10 Q-2 Nuclear Boiler 2-0300-2"A Stainless Steel Socket LR-QDC-M-77-1 (D-4)

Instrumentation At Nozzle N-12A 13

Unit System Line No.

Material Weld Drawing (Coordinates)

-________ Type and Comments Q-2 Nuclear Boiler 2-0299-2"A Stainless Steel Socket LR-QDC-M-77-1 (D-5)

Instrumentation At Nozzle N-12B Q-2 Nuclear Boiler 2-0207-2"C Carbon and Socket LR-QDC-M-77-1 (G-5)

Instrumentation Stainless Steel Q-2 Reactor Water 2-1265-2"A Stainless Steel Socket LR-QDC-M-77-1 (G-5)

Cleanup LR-QDC-M-88-1 (C-6)

Q-2 Reactor 2-0209A-2"A Stainless Steel Socket LR-QDC-M-77-2 (D-5)

Recirculation Q-2 Reactor 2-0209B-2"A Stainless Steel Socket LR-QDC-M-77-2 (D-6)

Recirculation.

Q-2 Reactor 2-0204A-2"A Stainless Steel Socket LR-QDC-M-77-2 (E-3)

Recirculation Q-2 Reactor 2-0204B-2"A Stainless Steel Socket LR-QDC-M-77-2 (E-8)

Recirculation (a)

2. The butt welds identified in the above tables will be evaluated based on risk and placed into high, medium and low risk categories consistent with the currently approved RI-ISI Program; A sample of 10% of the high and medium risk butt welds from each unit will be selected for volumetric examination. The sample expansion will be consistent with that described in Code Case N-578-1 Section 2430.
3. The B.1.2 "Water Chemistry" and B.1.23 "One-Time Inspection" [as amended in (a) 2. above] programs are credited with managing Stress Corrosion Cracking in small bore piping.

(b)

Neither Dresden nor Quad Cities have butt welds in ASME Class 1 piping 1-inch NPS and less. Therefore, this one-time inspection program does not apply to the 1-inch NPS and less piping.

14

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