ML042040274

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Supplemental Response to Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking in BWR Austentic Stainless Steel Piping
ML042040274
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/21/2004
From: Abney T
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-88-001
Download: ML042040274 (25)


Text

July 21, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of )

Docket No. 50-259 Tennessee Valley Authority )

BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 1 - SUPPLEMENTAL RESPONSE TO GENERIC LETTER 88-01, NRC POSITION ON INTERGRANULAR STRESS CORROSION CRACKING IN BWR AUSTENTIC STAINLESS STEEL PIPING This letter provides a supplemental response to Generic Letter (GL) 88-01 regarding Intergranular Stress Corrosion Cracking (IGSCC) for BFN Unit 1. As requested in the GL, this response includes:

(1) Plans regarding long-term mitigation of IGSCC, (2) A discussion of the inservice inspection program, (3) A verification of the adequacy of the BFN Technical Specifications, (4) Confirmation of leakage detection methods, and (5) Reporting requirements to NRC for flaws.

In addition, to assist NRC review, TVA has provided a comparison between the welds and categorization proposed for Unit 1 and those approved by NRC for Units 2 and 3.

The following piping is considered susceptible to IGSCC according to the guidelines given in GL 88-01:

Reactor Recirculation from the recirculation inlet and outlet nozzles to the connections with residual heat removal; Residual Heat Removal (RHR) from the recirculation system to the first isolation valve outside of the drywell penetration; Reactor Water Cleanup (RWCU) from its connection to the RHR system to first isolation valve outside of the drywell penetration;

U.S. Nuclear Regulatory Commission Page 2 July 21, 2004 Core spray from the core spray inlet nozzles to the drywell penetration, including the core spray inlet safe ends; and Jet pump instrument safe ends.

The measures being taken on Unit 1 to mitigate IGSCC are summarized below:

Inspections using nondestructive examination equipment, qualified examiners and qualified techniques are being used.

Weld crown reduction is also being employed to enhance the quality of the examination.

Repair of IGSCC indications is being performed by using replacement piping. Replacement piping materials utilized are resistant to IGSCC as defined in GL 88-01.

Where practical, mechanical stress improvement of susceptible piping and replacement piping is being performed.

A reduction in the number of welds is being achieved by using designs which employ integral bends and branches in replacement piping where possible.

Hydrogen water chemistry is being implemented to reduce susceptibility to IGSCC.

The replacement of piping susceptible to IGSCC with piping resistant to IGSCC is more extensive in BFN Unit 1 than the piping replacements in Units 2 or 3. A general description of the piping replaced in Unit 1 and a comparison with Unit 2 and 3 pipe replacement efforts is provided in the enclosure.

The program to mitigate IGSCC on Unit 1 is ongoing. Examinations are being performed using nondestructive examination equipment, weld crown reduction, qualified examiners and qualified techniques. Repair of IGSCC indications are being performed by using replacement piping with IGSCC resistant materials. A reduction in the number of welds is being achieved by using designs which employ integral bends and branches in replacement piping where possible.

The scope of IGSCC susceptible piping at BFN was previously described in References 1 through 3. In Reference 4, the NRC agreed that TVAs visual inspection program was in compliance with GL 88-01.

U.S. Nuclear Regulatory Commission Page 3 July 21, 2004 There are no new regulatory commitments associated with this submittal. If you have any questions about this submittal, please contact me at (256) 729-2636.

I declare under penalty of perjury that the foregoing is true and correct. Executed on July 21, 2004.

Sincerely, Original signed by:

T. E. Abney Manager of Licensing and Industry Affairs

References:

1.

TVA letter, R. Gridley to NRC, dated August 1, 1988, Browns Ferry Nuclear Plant (BFN) - Response to Generic Letter (GL) 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, dated January 25, 1988.

2. TVA letter, M. J. Ray to NRC, dated June 30, 1989, Browns Ferry Nuclear Plant (BFN) - Supplemental Response to Generic Letter (GL) 88-01 (TAC 61094).
3. TVA letter, O. J. Zeringue to NRC, dated November 25, 1992 Browns Ferry Nuclear Plant (BFN) - Request for NRC Approval of Alternate Methods for the Reactor Water Cleanup (RWCU) and Residual Heat Removal (RHR) Inservice Inspections Required by Generic Letter 88-01.
4. NRC letter, F.J. Hebdon to M.O. Medford, dated February 18, 1993, Alternate Inservice Inspection Methods for the Reactor Cleanup and Residual Removal Systems - Browns Ferry (TAC Nos. M85070, M85071, AND M85072).

cc: See Page 4

U.S. Nuclear Regulatory Commission Page 4 July 21, 2004 (Via NRC Electronic Distribution)

U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

U.S. Nuclear Regulatory Commission Page 5 July 21, 2004 SMK:BAB cc (Enclosure):

A. S. Bhatnagar, LP 6A-C M. J. Burzynski, BR 4X-C D. F. Helms, BR 4T-C J. E. Maddox, LP 6A-C R. F. Marks, PAB 1C-BFN R. G. Jones, NAB 1A-BFN J. R. Rupert, NAB 1A-BFN K. W. Singer, LP 6A-C M. D. Skaggs, POB 2C-BFN E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C EDMS WT CA - K S:lic/submit/subs/GL 88 01 Rev. 2.doc

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWN FERRY NUCLEAR (BFN) UNIT 1 SUPPLEMENTAL RESPONSE TO NRC GENERIC LETTER 88-01 NRC POSITION ON INTERGRANULAR STRESS CORROSION CRACKING IN BWR AUSTENITIC STAINLESS STEEL PIPING Nondestructive examination, repair, stress improvement and pipe replacement with corrosion resistant materials are being implemented on BFN Unit 1. These activities are being performed to reduce the potential for Intergranular Stress Corrosion Cracking (IGSCC) and are consistent with the NRC positions in Generic Letter (GL) 88-01 and prevailing BWR industry practice.

This enclosure provides a supplemental response to GL 88-01 regarding IGSCC for BFN Unit 1. As requested by the GL This response includes:

(1) Plans regarding long-term mitigation of IGSCC, (2) A discussion of the inservice inspection program, (3) A verification of the adequacy of the BFN Technical Specifications, (4) Confirmation of leakage detection methods, and (5) Reporting requirements to NRC for flaws.

In addition, to assist NRC review, TVA has provided a comparison between the welds and categorization proposed for Unit 1 and those approved by NRC for Units 2 and 3.

1.0 PLANS REGARDING LONG-TERM MITIGATION OF IGSCC The measures being taken on Unit 1 to mitigate IGSCC are summarized below:

Inspections using nondestructive examination equipment, qualified examiners and qualified techniques are being used.

Weld crown reduction is also being employed to enhance the quality of the examination.

Repair of IGSCC indications is being performed by using replacement piping. Replacement piping materials utilized are resistant to IGSCC as defined in GL 88-01.

E1-2 Where practical, mechanical stress improvement of susceptible piping and replacement piping is being performed.

A reduction in the number of welds is being achieved by using designs which employ integral bends and branches in replacement piping where possible.

Hydrogen water chemistry is being implemented to reduce susceptibility to IGSCC.

1.1 SCOPE OF IGSCC SUSCEPTIBLE PIPING The scope of susceptible piping at BFN was previously submitted to NRC in References 1 through 3. As discussed therein, the following wrought austenitic stainless steel piping systems and components are considered susceptible to IGSCC according to the guidelines given in GL 88-01:

Reactor Recirculation from the recirculation inlet and outlet nozzles to the connections with residual heat removal; Residual Heat Removal (RHR) from the recirculation system to the first isolation valve outside of the drywell penetration; Reactor Water Cleanup (RWCU) from its connection to the RHR system to first isolation valve outside of the drywell penetration; Core Spray from the core spray inlet nozzles to the drywell penetration, including the core spray inlet safe ends. The piping within and upstream of the penetration is not considered susceptible due to the low operating temperature, generally 130ºF or less; and Jet pump instrument safe ends.

The head spray system is not included because it will be removed from Unit 1 prior to restart. Similarly, the control rod drive return and recirculation discharge valve bypass piping have been removed from Unit 1 and so are not considered here.

1.2

SUMMARY

OF INSPECTIONS IGSCC susceptible weldments are being inspected or are being removed from service and replaced. TVA plans to inspect inaccessible welds were previously described in Reference 3. In Reference 4, NRC agreed that TVAs visual inspection program is in compliance with GL 88-01.

E1-3 A weld-by-weld table, including weld numbers and findings, is provided in Table 1.

1.3

SUMMARY

OF REPLACEMENTS The following piping is being replaced:

Reactor recirculation inlet and outlet safe ends are being replaced due to concerns of crevice corrosion attack. The replacement safe ends utilize an improved design employing resistant material and a crevice-free configuration.

Reactor recirculation piping is being replaced. This includes the 28 pump suction and discharge piping, the 12 risers and 22 ringheader. The replacement piping is 316NG stainless which is less susceptible to IGSCC. Improved construction methods and bent pipe result in fewer welds. The ring header design eliminates the ringheader crosstie valves.

Core Spray and RHR piping inside the containment are being replaced. The replacement piping is 316NG stainless for the RHR and ASTM SA-333 Gr6 high toughness grade of carbon steel for CS which is less susceptible to IGSCC.

Reactor water cleanup piping is being replaced both inside and outside containment as discussed in Reference 5. This replacement included the penetration process piping and, as such, eliminated the uninspectable weld located inside the penetration. The replacement material utilized is resistant to IGSCC. 316NG stainless steel is being used for all piping operating above 200ºF.

Jet pump instrumentation nozzle safe ends and seal assemblies are being replaced to remove cracking and overlays. The replacement assemblies are an improved design, fabricated from IGSCC resistant materials.

Details concerning the replacement welds are included in Table 1.

It is noted that the new/replacement welds numbers are contained in Table 1, Part 1, while welds removed/replaced are contained in Table 1, Part 2.

1.4

SUMMARY

OF REPAIRS Welds containing indications of cracking were replaced with 316NG IGSCC resistant material.

E1-4 2.0 INSERVICE INSPECTION PROGRAM PLANS Future inspections performed on piping within the scope of the GL 88-01 will conform to the NRC staff positions on methods, personnel, schedules and expansion plans. The BFN Unit 1 ISI program plan has been configured to ensure this objective.

Surveillance Instruction 1-SI-4.6.G, Inservice Inspection Program Unit 1, Section 7.11.6, identifies the requirement to categorize and inspect the weldments in accordance with the requirements contained in GL 88-01. Table 8.3 will be revised to list the Unit 1 welds that will be required to be examined per GL 88-01.

2.1 ISI PLANS FOR UNIT 1 CYCLE 7 REFUELING OUTAGE To address the requirements for inspection schedules and expansion plans, the BFN susceptible weldments have been categorized according to NUREG-0313, Revision 2, Section 5 Table 1. This categorization is listed in Table 1. The ISI plans for Cycle 7 refueling outage are to inspect the welds as required by BFN Technical Requirement 3.4.3.

3.0 CONFORMANCE TO THE ISI REQUIREMENTS OF GL 88-01 GL 88-01 requested a change to the Technical Specifications to include a statement in the section on ISI that the ISI program for piping covered by the scope of this letter will be in conformance with the staff position on schedule, methods and personnel. A Technical Specification change to allow conformance with this requirement was previously submitted to NRC on December 9, 1988 as TS 262 and approved on May 19, 1989 as Amendments 166, 165, and 137 for Units 1, 2 and 3, respectively.

Since that time, TVA submitted Units 1, 2, and 3 Technical Specifications Change 362 - Improved Technical Specifications (ITS) (Reference 6). This change was TVAs proposed conversion package from Custom Technical Specifications to ITS. NRCs approval of the ITS for BFN Units 1, 2 and 3 was documented in Reference 7. Technical Specification requirements for the ISI program are no longer part of ITS or the BFN Technical Specifications. This evolution was foreseen and discussed on Page 3 of GL 88-01. As discussed in the GL, the requirements regarding schedule, methods and personnel will be included in the Unit 1 ISI program.

E1-5 4.0 TECHNICAL SPECIFICATION ON CONFORMANCE TO STAFF POSITIONS ON LEAK DETECTION Technical Specification conformance with this requirement was previously submitted to NRC on December 15, 1986 as TS-222 and approved on August 26, 1982 as Amendments 137, 133, and 108 for Units 1, 2 and 3, respectively.

Since that time, TVA submitted Units 1, 2, and 3 Technical Specifications Change 362 - Improved Technical Specifications (ITS) (Reference 6). This change was TVAs proposed conversion package from Custom Technical Specifications to ITS. NRCs approval of the ITS for BFN Units 1, 2 and 3 was documented in Reference 7. Technical Specification requirements for the Reactor Coolant System leakage limits are included in Technical Specification 3.4.4. Technical Specification requirements for the Reactor Coolant System leakage detection instrumentation are included in Technical Specification 3.4.5.

5.0 PLANS TO NOTIFY NRC OF FLAWS As in the past, NRC has been notified of the inspection results, flaw evaluations and repair mitigation measures associated with BFN units through a comprehensive report submitted before plant startup. This report covers Unit 1 activities. After the IGSCC mitigation work scopes have been fully implemented, reports will be made only in the event of the discovery of new flaws or a change found in the condition of flaws previously detected. In these instances, a full report of the flaw evaluation and strategy and technical justification for repair or continued operation will be submitted.

6.0 DIFFERENCES BETWEEN UNIT 1 PROGRAM AND PROGRAM PREVIOUSLY APPROVED FOR UNITS 2 AND 3 The replacement of piping susceptible to IGSCC with piping resistant to IGSCC is more extensive in BFN Unit 1 than the piping replacements in Units 2 or 3. Unit 1 has replaced more piping (i.e. Recirculation system piping in drywell was completely replaced versus partial replacement on Units 2/3, which in conjunction with the Core Spray and RHR piping similar to Units 2/3, has eliminated weld overlays (Units 2 and 3 both contain a relatively small number of weld overlays). A general description of the piping replaced in Unit 1 and a comparison with Unit 2 and 3 pipe replacement efforts follows:

E1-6 Reactor Water Recirculation piping in Unit 1 is being completely replaced with resistant materials versus a partial replacement scope for this system in Units 2 and 3. Recirculation riser piping was replaced in Unit 2 and the riser piping, header arms and crosses were replaced in Unit 3. The Unit 1 replacement piping material is the same material as used on Unit 3.

RWCU piping is also being completely replaced in Unit 1, including the containment penetration piping, similar to the replacement effort scope in Unit 3. Unit 2 piping was partially replaced inside the drywell, penetration piping and a portion of the piping adjacent to valve FCV 69-01, in conjunction with replacement of RWCU piping outside the drywell. The Unit 1 replacement piping material is the same material as used on Unit 3.

Core Spray piping replacement scope inside the drywell for Unit 1 extends to the containment penetration piping. The Unit 2 and 3 Core Spray piping replacement inside the drywell extended to the inboard containment isolation valve. One loop of the Unit 1 Core Spray pipe replacement also included replacement of a piping section containing a weld overlay outside containment between the penetration and an outboard containment isolation valve. The Unit 1 replacement piping material is the same material as used on Unit 3.

RHR piping replacement inside the drywell for Unit 1 extends to the containment penetration piping for the two injection lines and the shutdown cooling suction line.

The RHR piping on Unit 3 was replaced between the manual isolation valves (3-HCV-74-55 and 69) for the two injection lines and the tie-in to the Recirculation tee connection for the 24 inch piping. The Unit 2 RHR piping was not replaced. The Unit 1 replacement piping material is the same material as used on Unit 3.

7.0 REFERENCES

1. TVA letter, R. Gridley to NRC, dated August 1, 1988, Browns Ferry Nuclear Plant (BFN) - Response to Generic Letter (GL) 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, dated January 25, 1988.
2. TVA letter, M. J. Ray to NRC, dated June 30, 1989, Browns Ferry Nuclear Plant (BFN) - Supplemental Response to Generic Letter (GL) 88-01 (TAC 61094).

E1-7

3. TVA letter, O. J. Zeringue to NRC, dated November 25, 1992 Browns Ferry Nuclear Plant (BFN) - Request for NRC Approval of Alternate Methods for the Reactor Water Cleanup (RWCU) and Residual Heat Removal (RHR) Inservice Inspections Required by Generic Letter 88-01.
4. NRC letter, F.J. Hebdon to M.O. Medford, dated February 18, 1993, Alternate Inservice Inspection Methods for the Reactor Cleanup and Residual Removal Systems - Browns Ferry (TAC Nos. M85070, M85071, AND M85072).
5. TVA letter, M. J. Ray to NRC, dated May 22, 1989, Browns Ferry Nuclear Plant (BFN) - TVAs Response to NRC Inspection Report (IR) No. 89-05 on Generic Letter 88-01
6. TVA letter, T.E. Abney to NRC, dated September 6, 1996, Browns Ferry Nuclear Plant (BFN) - Units 1, 2 and 3 - Technical Specification (TS) Change TS-362 - Request to Convert Current TSs to Improved Standard TS (ISTS) Consistent with NUREG-1433, Revision 1.
7. NRC letter, L. Raghavan to J.A. Scalice, dated July 14, 1998, Amendment Nos. 234, 253 and 212 to Facility Operating License Nos. DPR-33, DPR-52 and DPR-68: Regarding Conversion to Improved Standard Technical Specifications for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 (TAC Nos. M96431, M96432 and M96433).

E1-8 TABLE 1 BROWN FERRY NUCLEAR (BFN) UNIT 1 WELDS WITHIN SCOPE OF GENERIC LETTER 88-01 PART 1 WELDS WITHIN THE SCOPE OF GENERIC LETTER 88-01 / BWRVIP-75 SYSTEM WELD ID SIZE CONFIGURATION ISI STATUS MITIGATION CAT DISPOSITION NOTES CS CS-1-W002-020 10" Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD CS CS-1-W002-021 10" Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD CS CS-1-002-019 10" Safe End-to-Pipe PRESERVICE MSIP A

NEW WELD CS CS-1-002-022 10" Safe End-to-Pipe PRESERVICE MSIP A

NEW WELD CS CS-1-002-017 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-024 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-016 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-025 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-012 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-029 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-011 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-030 12" Pipe-to-Valve PRESERVICE MSIP D

NEW WELD CS CS-1-002-008 12" Pipe-to-Pipe PRESERVICE MSIP D

NEW WELD CS CS-1-002-033A 12" Pipe-to-Pipe PRESERVICE MSIP D

NEW WELD RWCU RWCU-1-001-001 6"

Branch-to-Valve PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-002 6"

Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-S001-005 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-S001-007 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-008 6"

Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-009 6"

Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-S001-010 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-S001-011 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-013 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-S001-016 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD

E1-9 SYSTEM WELD ID SIZE CONFIGURATION ISI STATUS MITIGATION CAT DISPOSITION NOTES RWCU RWCU-1-001-017 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-018 6"

Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWCU RWCU-1-001-019 6"

Pipe-to-Valve PRESERVICE MSIP A

NEW WELD RHR DRHR-1-3 24" Valve-to-Pipe PDI/IGSCC MSIP D

Limited accessibility RHR DRHR-1-3B 24" Flued Head-to-pipe N/A NONE G

Inaccessible located in penetration.

RHR RHR-1-012-001 24" Pipe-to-Elbow PRESERVICE MSIP D

NEW WELD RHR SW-TPRHR-1-3 24" Elbow-to-Elbow PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RHR RHR-1-012-006 24" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-012-007 24" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RHR RHR-1-012-026 24" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RHR SW-TPRHR-1-1 24" Elbow-to-Elbow PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RHR RHR-1-012-027 24" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-012-028 24" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RHR RHR-1-012-029 24" Pipe-to-Recirc PRESERVICE MSIP A

NEW WELD RHR DRHR-1-12 24" Valve-to-Pipe PDI/IGSCC MSIP D

Limited accessibility RHR DRHR-1-13B 24" Flued Head-to-pipe N/A NONE G

Inaccessible located in penetration.

RHR RHR-1-014-001 24" Pipe-to-Elbow PRESERVICE MSIP D

NEW WELD RHR RHR-1-014-S012 24" Elbow-to-Elbow PRESERVICE MSIP A

NEW WELD (Shop ID: SW-TPRHR-1-6)

RHR RHR-1-014-002 24" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-014-003 24" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RHR RHR-1-014-004 24" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RHR RHR-1-014-005 24" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-014-006 24" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RHR RHR-1-014-007 24" Pipe-to-Recirc PRESERVICE MSIP A

NEW WELD RHR RHR-1-013-006 20" Tee-to-Recirc PRESERVICE MSIP A

NEW WELD RHR SW-TPR-1-8 20" Tee-to-Elbow PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RHR RHR-1-013-005 20" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-013-004 20" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-013-003 20" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-013-002 20" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RHR RHR-1-013-001 20" Elbow-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-071 28" Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD

E1-10 SYSTEM WELD ID SIZE CONFIGURATION ISI STATUS MITIGATION CAT DISPOSITION NOTES RWR RWR-1-001-006 28" Safe End-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-005 28" Elbow-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-004 28" Pipe-to-Pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-003 28" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-002 28" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-22 4"

Pipe-to-branch nozzle PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-001-012 4"

Branch-to-Flange PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-18 28" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-001-001 28" Elbow-to-Pump PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-022 28" Pump-to-pipe PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-23 4"

Pipe-to-branch nozzle PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-001-023 4"

Branch-to-Cap PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-024 28" Pipe-to-Valve PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-025 28" Valve-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-027 28" Elbow-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-030 28" Pipe-to-Tee PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-040 22" Cross-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-S001-0xx 22" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-001-048 22" Cross-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-S001-0xx 22" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-001-042 12" Reducer-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-043 12" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-044 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-066 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-041 12" Pipe-to-Header PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-045 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-067 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-047 12" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-046 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-068 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-049 12" Pipe-to-Header PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-053 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-069 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-050 12" Reducer-to-pipe PRESERVICE MSIP A

NEW WELD

E1-11 SYSTEM WELD ID SIZE CONFIGURATION ISI STATUS MITIGATION CAT DISPOSITION NOTES RWR RWR-1-001-051 12" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-052 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W001-070 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-031 28" Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-061 28" Safe End-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-058 28" Elbow-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-056 28" Pipe-to-Pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-001-054 28" Elbow-to-Valve PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-053 28" Valve-to-Pipe PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-24 4"

Pipe-to-branch nozzle PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-002-050 4"

Branch-to-Flange PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-20 28" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-048 28" Elbow-to-Pump PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-011 28" Pump-to-pipe PRESERVICE MSIP A

NEW WELD RWR SW-TPR-1-25 4"

Pipe-to-branch nozzle PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-002-011A 4"

Branch-to-Cap PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-012 28" Pipe-to-Valve PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-013 28" Valve-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-015 28" Elbow-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-017 28" Pipe-to-Tee PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-032 22" Cross-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-S002-0xx 22" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-002-044 22" Cross-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-S002-0xx 22" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD Plant ID to be assigned later.

RWR RWR-1-002-034 12" Reducer-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-035 12" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-036 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-026 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-033 12" Pipe-to-Header PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-037 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-027 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-045 12" Pipe-to-reducer PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-038 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-028 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD

E1-12 SYSTEM WELD ID SIZE CONFIGURATION ISI STATUS MITIGATION CAT DISPOSITION NOTES RWR RWR-1-002-043 12" Pipe-to-Header PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-039 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-029 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-042 12" Reducer-to-pipe PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-041 12" Pipe-to-Elbow PRESERVICE MSIP A

NEW WELD RWR RWR-1-002-040 12" Elbow-to-safe end PRESERVICE MSIP A

NEW WELD RWR RWR-1-W002-030 12" Safe end-to-nozzle PRESERVICE MSIP A

NEW WELD CRD RCRD-1-33 4"

Cap-to-nozzle PDI/IGSCC MSIP G

RPV RWR-1-W003-001 5"

Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD RPV RWR-1-W003-050 5"

Nozzle-to-Safe End PRESERVICE MSIP A

NEW WELD CRD RCRD-1-49 4"

Pipe-to-Valve (85-577)

PDI/IGSCC MSIP D

CRD RCRD-1-50 4"

Pipe-to-Valve (85-577)

PDI/IGSCC MSIP G

CRD RCRD-1-52 4"

Pipe-to-Valve (85-576)

PDI/IGSCC MSIP G

NOTES:

1. Piping installation is in process and this list will require revision to reflect the configuration and mitigation actions taken.
2. Preservice examinations will be performed following MSIP application.
3. Generic Letter 88-01/BWRVIP-75 categories will be revised following completion of mitigation efforts.

ABBREVIATIONS WELD ID Weld Identification Number SYSTEM CRD - Control Rod Drive CS - Core Spray RHR - Residual Heat Removal RPV - Reactor Pressure Vessel (associated piping)

RWCU - Reactor Water Cleanup RWR - Reactor Recirculating Water MSIP Mechanical Stress Improvement CAT Generic Letter 88-01/BWRVIP-75 category for weldments susceptible to IGSCC PDI/IGSCC Performance Demonstration Initiative/Intergranular Stress Corrosion Cracking

E1-13 PART 2 WELDS REMOVED IN THE CYCLE 6 RECOVERY OUTAGE WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES DCS-1-04 CS 12 Pipe-to-Pipe REMOVED Piping Replaced DCS-1-05 CS 12 Pipe-to-Valve REMOVED Piping Replaced DCS-1-06 CS 12 Elbow-to-Valve REMOVED Piping Replaced DCS-1-09 CS 10 Pipe-to-Safe End REMOVED Piping Replaced DCS-1-14 CS 12 Pipe-to-Valve REMOVED Piping Replaced DCS-1-15 CS 12 Elbow-to-Valve REMOVED Piping Replaced DCS-1-16 CS 12 Pipe-to-Valve REMOVED Piping Replaced DCS-1-17 CS 12 Elbow-to-Valve REMOVED Piping Replaced DCS-1-18 CS 10 Pipe-to-Safe End REMOVED Piping Replaced DSCS-1-01 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-04 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-05 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-06 CS 10 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-08 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-09 CS 10 Pipe-to-Pipe REMOVED Piping Replaced DSCS-1-10 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-11 CS 12 Elbow-to-Pipe REMOVED Piping Replaced DSCS-1-12 CS 12 Elbow-to-Valve REMOVED Piping Replaced DSCS-1-13 CS 10 Elbow-to-Pipe REMOVED Piping Replaced GR-1-01 RWR 28 Pump-to-Pipe REMOVED Piping Replaced

E1-14 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES GR-1-02 RWR 28 Pipe-to-Valve REMOVED Piping Replaced GR-1-07 RWR 4

Cap-to-Pipe REMOVED Piping Replaced GR-1-08 RWR 28 Tee-to-Cross REMOVED Piping Replaced GR-1-09 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-10 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-12 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-13 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-14 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-15 RWR 12 Pipe-to-Reducer REMOVED Piping Replaced GR-1-16 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-17 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-18 RWR 22 Header-to-Cross REMOVED Piping Replaced GR-1-19 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-20 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-21 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-22 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-23 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-24 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-25 RWR 22 Header-to-Valve REMOVED Piping Replaced GR-1-26 RWR 22 Header-to-Valve REMOVED Piping Replaced GR-1-28 RWR 28 Pipe-to-Valve REMOVED Piping Replaced GR-1-29 RWR 28 Elbow-to-Valve REMOVED Piping Replaced GR-1-34 RWR 28 Pipe-to-Cross REMOVED Piping Replaced

E1-15 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES GR-1-35 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-36 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-37 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-38 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-39 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-40 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-42 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-43 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-44 RWR 22 Header-to-Cross REMOVED Piping Replaced GR-1-45 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-47 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-48 RWR 12 Pipe-to-Sweepolet REMOVED Piping Replaced GR-1-49 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-50 RWR 12 Pipe-to-Safe End REMOVED Piping Replaced GR-1-51 RWR 22 Header-to-Valve REMOVED Piping Replaced GR-1-52 RWR 22 Header-to-Valve REMOVED Piping Replaced GR-1-53 RWR 28 Pipe-to-Safe End REMOVED Piping Replaced GR-1-55 RWR 28 Pipe-to-Tee REMOVED Piping Replaced GR-1-59 RWR 28 Pipe-to-Safe End REMOVED Piping Replaced GR-1-62 RWR 28 Elbow-to-Valve REMOVED Piping Replaced GR-1-63 RWR 28 Pipe-to-Valve REMOVED Piping Replaced KR-1-02 RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-12 RWR 22 Header-to-Cross REMOVED Piping Replaced

E1-16 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES KR-1-13 RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-17 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-19 RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-24 RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-25 RWR 28 Pipe-to-Tee REMOVED Piping Replaced KR-1-33 RWR 22 Cross-to-Reducer REMOVED Piping Replaced KR-1-34 RWR 22 Header-to-Cross REMOVED Piping Replaced KR-1-35 RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-38 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-39 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-40 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-41 RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-43 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-44 RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-46 RWR 28 Pipe-to-Tee REMOVED Piping Replaced KR-1-47 RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-50 RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-51 RWR 28 Elbow-to-Pipe REMOVED Piping Replaced DRHR-1-02 RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-04 RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DRHR-1-06 RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-07 RHR 24 Elbow-to-Valve REMOVED Piping Replaced DRHR-1-09 RHR 24 Pipe-to-Tee REMOVED Piping Replaced

E1-17 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES DRHR-1-11 RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-13 RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DRHR-1-14 RHR 24 Elbow-to-Valve REMOVED Piping Replaced DRHR-1-16 RHR 24 Elbow-to-Valve REMOVED Piping Replaced DRHR-1-19 RHR 20 Pipe-to-Tee REMOVED Piping Replaced DRHR-1-21 RHR 20 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-22 RHR 20 Pipe-to-Valve REMOVED Piping Replaced DSRHR-1-01 RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-02 RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-03 RHR 24 Pipe-to-Pipe REMOVED Piping Replaced DSRHR-1-05A RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-06 RHR 24 Pipe-to-Pipe REMOVED Piping Replaced DSRHR-1-07 RHR 24 Pipe-to-Pipe REMOVED Piping Replaced DSRHR-1-08 RHR 6

Weldolet-to-Pipe REMOVED Piping Replaced TRHR-1-190 RHR 20 Elbow-to-Valve REMOVED Piping Replaced TRHR-1-191 RHR 20 Elbow-to-Valve REMOVED Piping Replaced JP-1-1A RPV 4

Nozzle-to-Safe End REMOVED Piping Replaced JP-1-1B RPV 4

Nozzle-to-Safe End REMOVED Piping Replaced N1B-SE RPV 28 Nozzle-to-Safe End REMOVED Piping Replaced N2A-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2B-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2C-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2D-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced

E1-18 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES N2E-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2F-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2G-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2H-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2J-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N2K-SE RPV 12 Nozzle-to-Safe End REMOVED Piping Replaced N5A-SE RPV 10 Nozzle-to-Safe End REMOVED Piping Replaced N5B-SE RPV 10 Nozzle-to-Safe End REMOVED Piping Replaced DRWC-1-01 RWCU 6

Pipe-to-Valve REMOVED Piping Replaced DRWC-1-04E RWCU 6

Pipe-to-Penetration REMOVED Piping Replaced DSRWC-1-01AX RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-02X RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-03X RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-04X RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-05 RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-06 RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced DSRWC-1-07 RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced TRWC-1-01 RWCU 6

Elbow-to-Pipe REMOVED Piping Replaced TRWC-1-02X1 RWCU 6

Elbow-to-Valve REMOVED Piping Replaced TRWC-1-04 RWCU 6

Pipe-to-Valve REMOVED Piping Replaced TRWC-1-04A RWCU 6

Pipe-to-Pipe REMOVED Piping Replaced CS-1-69(OL)

CS 12 Pipe-to-Valve REMOVED Piping Replaced DCS-1-07(OL)

CS 12 Pipe-to-Valve REMOVED Piping Replaced

E1-19 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES DCS-1-08(OL)

CS 12 Elbow-to-Valve REMOVED Piping Replaced GR-1-03(OL)

RWR 28 Elbow-to-Valve REMOVED Piping Replaced GR-1-27(OL)

RWR 28 Pump-to-Pipe REMOVED Piping Replaced GR-1-41(OL)

RWR 12 Pipe-to-reducer REMOVED Piping Replaced GR-1-46(OL)

RWR 12 Elbow-to-Pipe REMOVED Piping Replaced GR-1-54(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced GR-1-56(OL)

RWR 28 Elbow-to-Valve REMOVED Piping Replaced GR-1-57(OL)

RWR 28 Pipe-to-Valve REMOVED Piping Replaced GR-1-58(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced GR-1-60(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced GR-1-61(OL)

RWR 28 Pipe-to-Pipe REMOVED Piping Replaced GR-1-64(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-03(OL)

RWR 28 Pipe-to-Tee REMOVED Piping Replaced KR-1-14(OL)

RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-15(OL)

RWR 22 Cap-to-Header REMOVED Piping Replaced KR-1-16(OL)

RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-18(OL)

RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-20(OL)

RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-21(OL)

RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-22(OL)

RWR 12 Elbow-to-Pipe REMOVED Piping Replaced KR-1-36(OL)

RWR 12 Header-to-Sweepolet REMOVED Piping Replaced KR-1-37(OL)

RWR 22 Cap-to-Header REMOVED Piping Replaced KR-1-42(OL)

RWR 12 Header-to-Sweepolet REMOVED Piping Replaced

E1-20 WELD ID SYSTEM SIZE CONFIGURATION DISPOSITION NOTES KR-1-45(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-48(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced KR-1-52(OL)

RWR 28 Elbow-to-Pipe REMOVED Piping Replaced DRHR-1-05(OL)

RHR 24 Elbow-to-Valve REMOVED Piping Replaced DRHR-1-08(OL)

RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-15(OL)

RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-17(OL)

RHR 24 Pipe-to-Valve REMOVED Piping Replaced DRHR-1-18(OL)

RHR 24 Pipe-to-Tee REMOVED Piping Replaced DRHR-1-20(OL)

RHR 20 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-04(OL)

RHR 24 Elbow-to-Elbow REMOVED Piping Replaced DSRHR-1-05(OL)

RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-08A(OL)

RHR 24 Pipe-to-Pipe REMOVED Piping Replaced DSRHR-1-08B(OL)

RHR 24 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-09(OL)

RHR 20 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-10(OL)

RHR 20 Elbow-to-Pipe REMOVED Piping Replaced DSRHR-1-11(OL)

RHR 20 Elbow-to-Pipe REMOVED Piping Replaced DRWC-1-01A(OL)

RWCU 6

Pipe-to-Valve REMOVED Piping Replaced