ML18150A464

Risk-Informed ISI (RI-ISI) Pilot Program Submittal.

ML18150A464
Person / Time
Site:	Surry
Issue date:	10/27/1997
From:	Mcneill A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18150A465	List: ML18150A464 ML18153A393
References
PROC-971027, NUDOCS 9711120104
Download: ML18150A464 (215)

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{{#Wiki_filter:* VIRGINIA POWER '**:;_) INSERVICE INSPECilON PROGRAM CHANGE / ISSUE APPROVAL FORM STATION: 'S(Jif',:'. UNIT NO.: i INTERVAL NO. : 3 SUBMITTAL TITLE: CHANGE NO.: ~---~T/-A~~~- SECTION NO.: Al/A: REVISION: (IF APPLICABLE)

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SUPERVISOR - MATERIALS/IS! ENGINEERING {CORPORATE) REVIEWED AND r ~ // / APPROVED: /_hJ~t:::d.- DATE: Jo/z7/q7 SUPERVISOR - TEST~ and INSPECTION (STATION) REVIEWED AND APPROVED: u# f ~

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DATE: I I ()/:.)7/ 1 I .

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STATION NUCLEAR SAFETY AND OPERATING COMMITTEE {SNSOC) REVIEWED AND ~Q~~ APPROVED: ~. ~ ~ DATE: 4Pµ7/?7

         ==================~=============================' =:z=====.

AFTER APPROVAL, RETURN TO: Joyce A. Lawler, IN-3NW Virginia Power, 5000 Dominion Blvd., Glen Allen, VA 23060

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( DISTRIBUTION NO.: FORM7-"'-1.5_WE5

                    - 9711120104 971031 --,..--r--*----.,_

PDR ADOCK 05000280 DISTRIBUTION DATE: P PDR

SURRY POWER STATION UNIT 1 RISK-INFORMED INSERVICE INSPECTION (RI-ISi) PILOT PROGRAM SUBMITTAL

• Surry Power Station Unit 1 Risk-Informed lnservice Inspection Program Plan Table of Contents

1. Introduction/Relation To Draft NRC Reg. Guide DG-1061

2. Proposed Alternative to ASME Section XI lnservice Inspection Program

3. Risk-Informed ISi Process 3.1 Scope of Program 3.2 Segment Definitions 3.3 Consequence Evaluation 3.4 Failure Probability Assessment 3.5 Risk Evaluation

• 3.6 3.7 3.8 Expert Panel Categorization Identification of High Safety Significant Segments Structural Element and NOE Selection 3.9 Program Relief Requests 3.10 Change in Risk, Defense-In-Depth, and New Information

4. Implementation and Monitoring Program

5. Proposed ISi Program Plan Change

6. References/Documentation Attachment 1 Compliance with EPRI PSA Application Guide Attachment 2 Segment Drawings Attachment 3 Example Expert Panel Minutes Attachment 4 RI-ISi Program Examinations Attachment 5 Currently Scheduled ISi-Program Examinations

• 1. Introduction/Relation To Draft NRC Reg. Guide DG-1061 Introduction Virginia Power was approached to be a pilot plant in late 1995 to support the WOG risk-informed inservice inspection (RI-ISi) methodology on piping. Surry had previously been studied for probabilistic safety assessment (PSA) in earlier work for NUREG-1150. Additionally, initial ISi application work using PSA insights performed for the U.S. Nuclear Regulatory Commission by Pacific Northwest National Laboratories was conducted at Surry. Virginia Power committed to the USN RC to be a pilot for this application on April 8, 1996. The Surry Pilot Project is limited to Surry Unit 1.

Virginia Power's Surry Power Station is located on the James River in Surry County, Virginia near the city of Williamsburg. The construction permits for Surry Units 1 and 2 were issued on June 25, 1968. At that time, the ASME Boiler and Pressure Vessel Code covered only the construction of nuclear vessels. Piping was generally constructed to the rules of United States Standards Committee document 831.1 and applicable nuclear code cases. Surry Unit 1 started commercial operation on December 22, 1972 and Surry Unit 2 started commercial operation on May 1, 1973. The units are Westinghouse designed 3-loop pressurized water reactor (PWR) steam supply systems each rated at 2546 MW thermal and approximately 855 MW electric. The Surry units use a subatmospheric containment design. Currently both units perform ISi inspections on piping to the requirements of the ASME Boiler and Pressure Vessel Code Section XI, 1989 Edition. The units are both currently in the third inspection interval as defined by the Code for Program B. As Surry Power Station was designed and *constructed prior to the origination of the ASME code classifications (Class 1, 2, and 3), the system classifications for inservice inspection (ISi) are based upon the guidance found in Regulatory Guide 1.26, Revision 3 (February 1976), " Quality Group Classifications and Standards for Water-, Steam-, and Radioactive Waste-Containing Components of Nuclear Power Plants" and 10 CFR 50.55a - Title 10, "Code of Federal Regulations - Energy." Pursuant to 10 CFR 50.55a(g)(1) requirements are assigned within the constraints of our existing design basis. In August 1991 a PSA of Surry Nuclear Power Station was completed in response to Generic Letter 88-20 which had requested holders of operating licenses to perform an Individual Plant Examination (IPE) of their plants for severe accident vulnerabilities. The study included a Level 1 PSA for internal

• • events and internal flooding and a Level 2 analysis to identify the Containment Building performance and the potential source terms. The work was performed by a joint project team of Virginia Power and NUS (Scientech) personnel. Surry 1

received a SE on the IPE in 1993. The PSA model has been revised several times to incorporate some plant configuration and procedural changes as well as enhancing the mechanics for running the model. Based on the latest PSA model, the point estimate core damage frequency at Surry from internal events is 7 .2E-05 per year and the point estimate large early release frequency is 1.1 E-05 per year. The point estimate core damage frequency from internal flooding is calculated to be 2.5E-05 per year. Each initiating event's point estimate contribution to the overall core damage frequency is shown in Table 1-1. The dominant accident sequences in the model include:

• Loss of switchgear room cooling and failure of the alternative cooling which leads to loss of all switchgear and subsequent core damage from the unit blackout. The dominant contributors to failure are failure of the operator to establish cooling from the other unit and failure to load shed according to procedure.
• Loss of offsite power with at least one diesel generator available at Units 1 and 2. The auxiliary feedwater.(AFW) and feed and bleed are unavailable. The dominant contributors to this sequence are the common cause failure of the AFW discharge check valves .

Small LOCA initiator with the failure of high pressure injection and the failure of core cooling recovery.

• Steam generator tube rupture sequence which involves the failure of the operator to achieve early cooldown and depressurization followed by failure to achieve late cooldown using secondary heat removal.

Other than fire and seismic events, the contribution of all the other external event hazards to core damage frequency have been qualitatively screened out. The fire-induced CDF is 6.28E-06 per year. The estimation of the seismic events contribution to CDF is currently being finalized. The risk informed process used in this submittal is described in Westinghouse Owners Group WCAP-14572, Revision 1, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping lnservice Inspection Topical Report," and generally conforms with the framework described in ASME Code Case N-577, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method A." Many examples are provided in WCAP-14572, Revision 1, from the Surry

• 2
• pilot program and important results are reiterated here. Additional examples and plans are also provided to support our submittal.

Relation To Draft NRC Reg. Guide DG-1061 WCAP-14572, Revision 1, provides in Table 1.4-1 the key steps and principles relating to Draft NRC Reg. Guide DG-1061. The steps and principles are reiterated here in Table 1-2 with the additional corresponding section listings of this submittal .

• 3

Table 1-1 Surry Plant PSA Core Damage Frequency Percent Contribution by Initiator Initiating Event  % Contribution to Overall Plant PSA CDF Loss of Emergency Switchgear Room Cooling 22.5% Small LOCA (3/8" to 2j 18.4% Steam Generator Tube Rupture 13.0% Loss of Offsite Power 10.6% No Diesels Available Loss of Offsite Power 10.4% One Diesel Available Medium LOCA (2" to 6") 7.3% Large LOCA {> 6") 6.5%

• Transients with Main Feed 1.5%

Initially Available Interfacing LOCA 2.2% Loss of Circulating Water 1.8% Loss of RCP Seal Injection and Thermal 1.1% Barrier Cooling Transients with Recoverable Main Feed 0.7% Following Isolation Non-recoverable Loss of DC Bus 18 1.3% Non-recoverable Loss of DC Bus 1A 1.3% Transients with Non-recoverable 0.6% Main Feed Loss ATWS at Power Above 40% 0.5% Reactor Vessel Rupture 0.4% ATWS at Power Below 40% 0.0% Steam Line Break Outside Containment 0.0% Steam Line Break Inside Containment 0.0%

• 4
• Table 1-2 Relationship To Draft NRC Regulatory Guide DG-1061 Key Steps/Principle WCAP Section Va. Power Submittal Define the orooosed change 1.1 2 Perform engineering analysis 3 3 Define implementation and monitorina oroaram 4 4 Submit orooosed chanae 1.1 Submittal The proposed change meets the current regulations 1.1 2 Defense-in-deoth is maintained 3.7, 4 3.8, 3.10, 4 Sufficient safetv marains are maintained 3.7 3.8 Proposed increases in risk, and their cumulative effect, are small and do not cause the 3.6, 3.7, 3.8, 3.10 NRC Safety Goals to be exceeded 4.4 Performance-based implementation and monitoring strategies are proposed that 4 3.8, 4 address uncertainties in analysis models and data and provide for timely feedback and corrective action
  • 5
• 2. Proposed Alternative to ASME Section XI lnservice Inspection Program ASME Section XI Categories B-F, B-J, C-F-1 and C-F-2 currently contain the requirements for examining (NOE) piping components. This current program is limited to ASME Class 1 and Class 2 piping. There is no current NOE examination program for ASME Class 3 or nonclass piping components in ASME Section XI. The alternative risk-informed inservice inspection (RI-ISi) program for piping is described in WCAP-14572, and ASME Code Case N-577. The RI-ISi program will be substituted for the current examination program on piping in accordance with 10 CFR 50.55a(a)(3)(i) by alternatively providing an acceptable level of quality and safety. Additionally, the alternative program will not be limited to ASME Class 1 or Class 2 piping encompassing the high safety significant piping segments regardless of ASME Class. Other nonrelated portions of the ASME Section XI Code will not be affected. WCAP-14572 and Code Case N-577 provide requirements defining the relationship between the risk-informed examination program and the remaining unaffected portions of ASME Section XI.
• 6

3. Risk-Informed ISi Processes The processes used to develop the Surry Power Station Unit 1 RI-ISi program are consistent with the methodology described in WCAP-14572, Revision 1.

The process that is being applied, involves the following steps:

• Scope Definition - This step involves identifying the fluid systems, portions of systems and interfaces that are addressed by the risk-informed process. The selected systems include those modeled in the PRA and systems inspected in accordance with ASME Section XI requirements.
• Segment Definition - The segments define a portion of piping with the same consequence of failure and include piping structural elements between major discontinuities such as pumps and valves.
• Consequence Evaluation - The consequences given failure of a piping segment are established by application of the plant PRA with additional considerations based on engineering evaluation and operations reviews. Plant walkdowns are performed to identify indirect effects of pipe failures to supplement information from other related plant evaluations (e.g., hazards evaluation, flooding analysis)
• Failure Probability Assessment - The studies evaluate failure data of piping systems augmented by application of a simplified SRRA tool to estimate failure probabilities at important locations within each piping segment.
• Risk Evaluation - Risk importances are calculated for each pipe segment within the systems of interest based on core damage frequency (GDF) with additional considerations given to large early, release frequency (LERF), resulting from pipe segments only.
• Expert Panel Categorization - A plant expert panel evaluates the risk results along with other deterministic information and insights, and determines for each piping segment whether it is either high safety-significant or low safety-significant.
• Element/NOE Selection - A focused ISi engineering team comprised of materials, ISi and NOE expertise selects the structural elements for inspection and determines the method and frequency of inspection for each structural element within each high safety-significant pipe segment.
• Implement Program - the risk-informed ISi program is implemented by changing any plant documents, procedures, etc .
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• Feedback Loop - a reevaluation is performed periodically based on changes such as: 1) plant design and operational changes; 2) industry experience; 3) plant ISi experience; and 4) plant PSA model changes. This allows for shift of emphasis to areas of concern over time.

3.1 Scope of Program Section 3.2, "Scope Definition," of WCAP-14572, Revision 1 provided the three system selection criteria as follows:

• all Class 1, 2 and 3 systems currently within the ASME Section XI program
• piping systems modeled in the PSA and
• various balance of plant fluid systems determined to be of importance (consistent with system determinations made for the implementation of the Maintenance Rule).

The systems included in the RI-ISi program were selected based on these criteria .

• The combination of the piping associated with the current ASME Section XI ISi program and the piping associated with the active components in the PSA model form the primary basis for inclusion of systems in the RI-ISi program. Additional piping systems determined to be of importance through the maintenance rule are also evaluated. Once these systems have been selected, the list is presented to an "expert panel" which consists of personnel who previously served on the Maintenance Rule working group, engineering and ISi personnel. The expert panel, using knowledge gained from the Maintenance Rule effort, makes the final determination of which systems are included within the scope of the RI-ISi program and which systems are excluded. The systems to be included in the Surry Unit 1 risked-informed ISi program are provided in Table 3.1-1.

The systems or portions of systems identified below were evaluated and excluded from system scope consideration in the RI-ISi program. Instrument Air (Compressed Air) The current Probabilistic Safety Assessment (PSA) used for the RI-ISi program was derived from the Surry Individual Plant Examination (IPE) 1 , previously submitted to the NRC. In the PSA model, the Instrument Air 8

                                                                             ~I (IA) system is divided into independent outside and inside containment

• subsystems. Loss of inside containment IA will not result in an automatic reactor trip, but could require a manual trip. This would be considered a long term effect and would be categorized by the PSA as a loss of feedwater (T2) transient. The only important function that would be disabled by a loss of inside containment instrument air is pressurizer spray, however, pressurizer spray is a non-safety-related control function.

The safety-related pressurizer power-operated relief valves (PORV) are air operated, and have compressed air bottles that serve as a backup to the inside containment IA system. Loss of outside containment IA is functionally equivalent to a loss of Feedwater transient with the addition of loss of Component Cooling Water (CCW) supply to the Reactor Coolant Pump (RCP) thermal barrier. The steam generator PORVs are also disabled by this event. Additionally, the loss of outside containment IA, in combination with additional systems, is treated as a contributor to the Loss of RCP Seal Cooling initiating event (T4). However, the frequencies associated with these events are not significant contributors to the loss of Feedwater or CCW events. The Surry PSA model does not consider the loss of the IA system a significant contributor to total risk, and consequently a fault tree model was not developed to address this condition. This conclusion was based on the following:

• compressed air bottles are provided for the pressurizer PORVs and
• the supply of IA can easily be recovered by re-routing air flow or by using portable air bottles.

Further, the ASME Code requirements for this system are limited to the containment penetrations, the rest of the system is designated as non-safety class. A similar conclusion was reached during implementation of the maintenance rule where certain systems have been included in a functional sense only. For example, the functional requirement of the IA system is to supply air at 90 psig. The performance of individual components within the IA system is not monitored, only the system function is monitored. Therefore, as long as the failure of an IA component does not cause the loss of the IA system function, it is not considered an IA failure by the maintenance rule. Furthermore, the system is a low pressure system having a design pressure of only 100 psig .

• 9

                                                                              -1 2

The frequency of loss of IA is derived from NUREG/CR-5472 . Our

• determination that the loss of the IA system is not significant is supported by the conclusions of NUREG/CR-5472 which include the following:

          "1. The IA system contribution to the total core melt frequency is generally much lower than that of front-line safety systems, and significantly lower at BWRs than at PWRs.

2. The total risk cannot be significantly reduced by modifications or reliability improvements to the IA system."

Also, based on the NUREG/CR-5472 findings problems related to IA have been primarily caused by contamination and human error during operations/maintenance activities, and the effects are more often characterized as misfunctions rather than malfunctions, (i.e .. the IA system often introduces a problem rather than fails to function). Based on the above discussion, we conclude that the IA system is a low risk, low safety significant system and need not be included in the RI-ISi program. Fire Protection System The Surry PSA does not explicitly credit the fire protection system as an accident mitigation system. As a conservatism, the operation of the fire protection system was not credited in the PSA that addresses the effects of fire, and is generally not credited in the Appendix R safe shutdown analyses. The ASME Code requirements for this system are limited to the containment penetrations, and the rest of the system is designated as non-safety class. Therefore, the fire-protection system is not considered risk significant. Certain sections of this system, however, are routed through the Auxiliary Building and have been assessed in the PSA model as having the potential to cause damage as a source offloading in the Auxiliary Building. They have been evaluated as part of the "indirect effects" portion of the methodology. The remaining piping segments in the system need not be considered. *

• 10

Containment Penetration Piping

• The ASME Code currently includes containment penetration piping as safety-class piping, even if the balance of the system is non-safety class.

These non-safety class systems were excluded from the RI-ISi program scope based upon their system non-safety-class designation and their exclusion from the PSA model system scope. Furthermore, the safety-class portion of piping penetrating containment is assured of structural integrity through the separate 10 CFR 50 Appendix J testing program in conjunction with Code pressure testing requirements. Maintenance Rule Program Revision The expert panel noted that the maintenance rule program has been recently revised. Any differences in system considerations between the Maintenance Rule program and the RI-ISi program will be addressed as part of the normal RI-ISi program update process. References

1. Virginia Electric and Power Company, "Probabilistic Risk Assessment for the Individual Plant Examination, Final Report, Surry Units 1 and 2,"

August 1991 .

2. NUREG/CR-5472, "A Risk-Based Review of Instrument Air Systems at Nuclear Power Plants," January 1990 .

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• System Description

1. AFW - Auxiliary Feedwater Table 3.1-1 Suny Unit 1 System Selection PSA Yes Section XI Yes 12

2. BD - Slowdown (S/G) Yes Yes

• 2

3. CC - Component Cooling Yes Yes 2

4. CH - Chemical & Volume Contror4 Yes Yes 2

5. CN - Condensate Yes Yes

6. CS - Containment Spray Yes Yes 2

7. CW - Circulating Water Yes Yes

8. EE - Emergency Diesel Fuel Oil Yes No 6 1

9. FC - Fuel Pit Cooling No Yes 2

10. FW - Feedwater Yes Yes 2

11. MS - Main Steam Yes Yes 2

12. RC - Reactor Coolant Yes Yes

13. RH - Residual Heat Removal Yes Yes

14. RS - Recirculation Spray Yes Yes

15. SI - Safety lnjection5 Yes Yes 2

16. SW - Service Water Yes Yes 7 12

17. VS - Ventilation Yes Yes

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18. AS - Auxiliary Steam No No Notes:

1. System is exempt from current ASME Section XI examination requirements (Volumetric, surface, visual (VT-3)).

2. Portions of this system are not included in the Section XI ISi program.

3. Suny combines the feedwater and auxiliary feedwater systems on the system drawings.

4. Portions of the chemical & volume control system work in conjunction with high head safety injection. *

5. Includes high head, low head, and the passive accumulator portions of safety injection.

6. Important during shutdown.

7. Cooling water to control room HVAC.

8. Considered only for indirect effects.

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• 3.2 Segment Definitions Once the systems to be included in the program are determined, the systems' piping is divided into defined segments. A segment is initially defined based on the direct consequences of a pipe failure. In general, the section of pipe for which a catastrophic failure would result in the same direct consequence is defined to be a segment. Consequence, as used here, means the impact on a fluid system, and is generally the loss of a system or train of a system. The magnitude of the consequence can later be evaluated by relating the segment to a component in the PSA model. A motor-operated or air-operated valve, or check valve can be credited for isolation of the pipe failure, and typically forms one boundary of a segment. The consequences for a segment are also defined with and without operator action. The operator action generally defines whether isolation of the failed pipe section is possible. The consequence associated with operator action usually determines the pipe segment. As a result, there are typically many segments with the same consequence if no operator action is assumed, but different consequences with assumed operator action.

Other aspects of piping systems can also affect segment definition . Changes in pipe diameter or material properties may define a segment boundary. Since piping is typically arranged in networks, it is also necessary to address flow splits. In most PSAs, it is assumed that a significant loss of flow due to diversion would not result from a pipe failure that is less than one third the diameter of the main pipe section (NUREG/CR-2815)1. However, this assumption has not been adopted for the purposes of pipe segment definition in the RI-ISi program. Potential flow diversions were considered for lines as small as one inch in diameter if the section of pipe is included in a system that is covered by the program. The initial number of pipe segments for 18 systems are summarized in Table 3.2-1. Surry Unit 1 as-operated piping and instrumentation diagrams were used to define the segments. Segment names use a system identifier, and segment numbers start at the fluid source and continue through system termination. Segments are numbered such that parallel train A and train B pipe sections have contiguous numbers whenever possible. Thus, the segments for each system were defined in. a consistent manner. Segment definition is an iterative process with the determination of the consequences and the identification of any potential operator recovery 13

• actions. Color coded drawings identifying the segments are provided in Attachment 2.

References

1. NU REG/CR 2815. "Probabilistic Safety Analysis Procedures Guide,"

Revision 0, January 1984.

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• Table 3.2-1 Surry Unit 1 Segment Definition Summary System Description No. of System Description No. of Seg. Seg.

1. AFW - Auxiliary Feedwater 32 10. FW - Feedwater 20

2. BD - Slowdown (S/G) 12 11. MS - Main Steam 38

3. CC - Component Cooling 66 12. RC - Reactor Coolant 96

4. CH - Chemical & Volume 44 13. RH - Residual Heat Removal 11 1

Control 2

5. CN - Condensate 9 14. RS - Recirculation Spray 13

6. CS - Containment Spray 16 15. SI - Safety Injection ACC - Accumulator Discharge 15 ECCS - Emerg Core Cooling 8 HHI - High Head Injection 27 LHI - Low Head Injection 18

7. CW - Circulating Water 16 16. SW - Service Water 54

8. EE - Emergency Diesel Fuel 7 17. VS -Ventilation 2 Oil

9. FC - Fuel Pit Cooling 9 18. AS -Auxiliary Steam 2 Total Number of System Segments 515 Notes:

1. Segment CH-07 was subdivided by the expert panel after the numerical analysis.

2. Segment CN-08 was subdivided by the expert panel after the numerical analysis .

• 15

3.3 Consequence Evaluation The consequences of pressure boundary failures are measured in terms of core damage and large early release. The impact on these measures can be due to both direct and indirect effects. A direct effect may be a failed pipe that can no longer provide fluid flow, thus resulting in the disabling of a system essential to the safe shutdown of the plant. An indirect (spatial) effect may be flooding that disables a critical electrical component. Direct Effects The direct effects include:

• failures that cause an initiating event such as a LOCA or reactor trip,
• failures that disable a single train or system,
• failures that disable multiple trains or systems or
• failures that cause any combination above.
• Examples of segments and their direct effects with and without operator action are given in Table 3.3-1.

Indirect Effects Indirect effects are evaluated to determine if the consequences would differentiate piping segments in the risk evaluation. Indirect effects evaluations include consideration of pipe whip, jet impingement spray, high environmental temperatures and flooding. Indirect Effects Evaluation - Information Collection The internal flooding PSA was used to evaluate the potential for flooding and spray. For pipe whip and jet impingement, Chapter 14, Appendix B, of the Surry UFSAR was used to identify high energy lines which are defined in the UFSAR as piping that has a maximum operating pressure greater than 275 psig and a maximum temperature equal to or greater than 200°F. Generally, the impact of failure in piping operating at these conditions is evaluated by walking down the areas of interest.

• 16
• Indirect Effects Evaluation - Pre-Walkdown Evaluation Initially, the plant is divided into areas corresponding to the fire areas defined within the plants 10 CFR 50, Appendix R report. The following areas were reviewed for indirect effects:
• auxiliary building,
• main steam valve house and safeguards area,
• service building,
• mechanical equipment room no. 4 (charging pump service water pump room),
• containment,
• turbine building,
• mechanical equipment room #5 and
• emergency service water room.

Indirect Effects Evaluation - Walkdown The walkdown included members from the PSA, ISi, structural mechanics and bperations groups at Virginia Power and members of the PSA and piping groups at Westinghouse. An example of the walkdown sheets used at Surry are found in the WCAP-14572, Revision 1, pages A-13 and A-14. The walkdown covered the specific areas identified below:

• main steam valve house,
• charging pump cubicles,
• service building,
• turbine building and
• auxiliary building near elevator and boric acid storage tanks .
• 17
• The other areas reviewed during the pre-walkdown review did not require a walkdown because information was available to evaluate the indirect effects.

Indirect Effects Evaluation - Results An example summary of the indirect effects identified for Surry Unit 1 is given in Table 3.3-2. Conditional Consequences The current Surry PSA model was used to evaluate the consequences of pipe failures during operation in Modes 1 and 2. The PSA model is a standard internal events model that is based on the small event tree large fault tree method of quantification. The fault trees in the model represent the systems important to successful mitigation of severe accidents. There are about 1000 plant components represented in the model at varying levels of detail. The event trees are designated as plant damage state event trees. That is, the event trees provide the state of the plant considering both reactor and containment heat removal systems functionality. This degree of detail is necessary to determine both severe accident figures of merit: *cor~ damage frequency (CDF) and large early release frequency (LERF). The model is solved using a batch process that is based on tabular input. Therefore, all of the fault trees and event trees can be solved simply by initiating the batch process. So, for each segment, with unique consequences, a full solution of the model including cut set generation and quantification was utilized. This approach avoids the issue of cut set truncation associated with manipulation of sensitivity analyses based on a nominal plant model. Average estimates of unavailability developed at the time of the IPE were included in the fault trees. The truncation value for the model was the same in each run. Functions were solved and cut sets retained to a value of 1E-9. Sequences were quantified to a truncation level of 1E-10. The sequences are concatenated into a final CDF equation using a truncation value of 1E-11.

• Given the above model and solution strategy the decision to be made for.

each pipe segment was which component(s) in the model would serve as a surrogate(s) for the pipe segment. Recall that typical PSA models do not include pipe segment failures because the failure probability of these

• passive components is thought to be much lower than that of active components. Therefore, surrogate active components are chosen which 18
• result in the same consequence or consequences as the failure of the pipe segment.

In order to decide which surrogates to use it was necessary to review the segment definition to determine the direct effect of the failure assuming no operator action and the indirect effects on any components in the vicinity of the segment. The indirect effects analysis provides the information needed to indicate which type of effect is possible for a given segment. Based on this review one or more model solutions were required. If the only effect was a loss of the system function then a single run was required. If the direct effect resulted in the loss of a system function and an initiating event, two runs were required. The indirect effects were included by making additional runs for a segment that caused the failure of surrounding equipment due to flooding, spray, jet impingement, pipe whip or environmental effects. Table 3.3-3 includes some examples of the runs made in order to illustrate the process. Auxifiary Feedwater segment AFW-001 was evaluated and found to have both direct and indirect effects. The direct effect is the loss of all three unit 1 AFW pumps based on the loss of the Emergency Condensate Storage Tank. This failure would not cause an

• initiating event. So, the three pumps were failed as the surrogate components for the direct effect for this segment resulting in a conditional core damage frequency (CCDF) of 1.69E-3 and a conditional large early release frequency (CLERF) of 1.02E-4. The only indirect effects assessed for this segment were of the category jet impingement/spray.

This categorization is based on the walkdown of the area. The failure mode associated with this type of limited indirect effect is a through-wall crack. For segment AFW-001 the system failure mode is more limiting although that is not generally the situation. The jet impingement/spray evaluation concluded that the failure of the two motor driven AFW pumps was likely and the model quantification resulted in a CCDF = 3.22E-4 and a CLERF = 2.47E-5. For the system runs, the failure mode was defined as the disabling leak a (leak large enough to prevent the system from performing its function). The double-ended rupture failure mode was assigned to pipe segments which included the indirect effect of pipe whip. Segment AFW-001 was not identified as being susceptible to pipe whip so no consequence calculation was performed for this more catastrophic category. A second example is provided of a segment where failure results only in an initiating event. For the reactor coolant system, a LOCA can result from a leak of any size greater than the capacity of the charging pumps . But the failure probability decreases as the break size increases. 19

• Therefore, for the reactor coolant system, the spectrum of possibilities was represented by three traditional sizes: small, medium and large. The consequence for each of these segments was calculated by setting the initiating event frequency of the appropriate initiating event to one. The conditional core damage probability (CCDP) and conditional large early release probability (CLERP) for these events are listed in Table 3.3-3.

The contribution to pipe segment risk is calculated as the sum of the products of the CCDP(CLERP) and the failure probability as discussed in Section 3.5. A final example illustrates the situation where a high energy line fails. In this situation, pipe whip is a possibility. Segment BD-0088 was evaluated for the effects of jet impingement or spray, loss of system function and pipe whip. The results of the analysis are shown in Table 3.3-3. The consequences from the loss of system function and jet impingement or spray were conservatively assumed to be the same since the equipment layout in this area of the plant makes it extremely difficult to precisely determine the individual targets. However, it was possible to identify that certain additional components could fail ~s a result of a blowdown section of pipe whipping into a smaller diameter pipe. An additional run was made to incorporate the additional failures resulting from the pipe whip . These results are shown below the other results for this segment in Table 3.3-3. The results are identical for the pipe whip run because the failure of the CC system has the biggest impact on the RHR system which is already failed by the failure of the CC trip valves 109A\B. All of the segments were evaluated using the techniques discussed above. The consequence results were provided to the quantification team to determine the individual and total pipe segment contribution to risk. The above consequences are combined with the failure probabilities for the respective failure mode and summed to determine the contribution to pipe segment CDF or LERF. The calculations are performed according to the definition given in Section 3.6.1 of WCAP-14572, Rev. 1. It should be noted that the conditional consequences are determined by subtracting the CDF (LERF) determined with the pipe segment failed from the base case CDF (LERF) in order to determine the change in CDF (LERF) due to pipe segment failure. As a result these numbers represent a change in risk as a result of the pipe segment being failed. The total risk is not calculated. Once the initial quantification process was complete, each segment was evaluated again to determine the consequences of the pipe section failing

• if perfect operator action were to occur. The consequences do not change for many of the segments. However, for some systems numerous 20

flow paths are available and it is possible to have different consequences . For example, Segment AFW-001 can be isolated without losing the supply of all AFW. There are three Condensate storage tanks in the Surry design. A failure in Segment AFW-001 would fail two of the three tanks. Drawing 1-AFW-01A (See Attachment 2) shows that a supply of AFW from 1-CN-TK-3 through the AFW booster pumps is still available as is the fire protection system and the supply of AFW from the opposite Unit. The impact of operator action is determined by repeating the process using the appropriate surrogate components as shown in Table 3.3-4. The indirect effects are assumed to occur instantaneously and are therefore not subject to the recovery actions performed by the operator. These results are used to determine a new set of risk rankings. The impact of the operator action is to make some other segments more important. The segments are ranked both ways and provided to the expert panel for consideration. This process is discussed in more detail in Section 3.5 .

• 21

Table 3.3-1 Surry Unit 1 Examples of Direct Effects for Segments With and Without Operator Action Segment ID Segment Description Drawing Failure Effect Failure Effect References Without Operator Action with Operator Action ACC-001 1-SI-TK-1A to 1-Sl-109, Loop 1 cold leg. 11448-CBM-0898-3 Loss of one accumulator: No change. SH. 1, Rev. 5, Accumulator injection (Function 11448-WMKS- D2). 0122L1 ACC-002 2"-Sl-63-602 from 12"-Sl-45-1502 to 1-SI- 11448-CBM-089B-3 Loss of one accumulator: No change. 103, 1-SI-HCV-1852A and 1-Sl-104. SH. 1, Rev. 5, Accumulator injection (Function 11448-WMKS- D2). Accumulator drains to 0122L1 sump. ACC-003 2" level taps from 1-SI-TK-1A to reducer 11448-CBM-089B-3 Loss of one accumulator: No change. in the lines to 1-SI-LT-1920 and 1-SI-LT- SH. 1, Rev. 5 Accumulator injection (Function 1922 D2). Accumulator drains to the level of the pipe break and into sump, ACC-004 1"-Sl-100-602 from 1-SI-TK-1A to 1-SI- 11448-CBM-089B-3 Loss of one accumulator: No change. HCV-1853A and the line from 1-SI-TK-1A SH.1, Rev. 5 Accumulator injection (Function to 1-SI-RV-1858A. D2). Accumulator depressurizes and remains full. ACC-005 1"-Sl-11-602 from 1"-SI-TK-1B to 1-SI- 11448-CBM-0898-3 Loss of one accumulator: No change. HCV-1851A. SH. 1, Rev. 5 Accumulator injection (Function D2). Accumulator drains to sump. ACC-006. 1-SI-TK-1B to 1-Sl-130, Loop 2 cold leg. 11448-CBM-089B-3 Loss of one accumulator: RHR path can be isolated by 1-SH. 2, Rev. 3, Accumulator injection (Function RH-MOV-1720A, assume can 11448-WMKS- D2). When in operation, loss of be identified by accumulator 0122D1 RHR Mode 3 large LOCA with loss of pressure. Result would loss of one accumulator. be loss of one accumulator and one path of RHR, return to RCS. ACC-007 2"-Sl-65-602 from 12"-Sl-23-1502 to 1-SI- 11448-CBM-089B-3 Loss of one accumulator: No change. 125, 1-SI-HCV-1852B and 1-Sl-123. SH. 2, Rev. 3, Accumulator injection (Function 11448-WMKS- D2). Accumulator drains to 0122D1 sump. 22

• Area Table 3.3-2 Surry Unit 1 Summary of Indirect Effects Indirect Effect(s)

Auxiliary Building . Flooding/Spray The source of the flooding or spray is the low head to high head recirculation lines or the RWST piping supplying the charging pumps. Component Cooling pumps and the Charging pumps would be lost if no action were taken to isolate the ruptured line. High Energy The charging pump recirculation line and the discharge line were identified as the source of the jet impingement. MOVs 1-CH-MOV-1863A/B and 1-CH-MOV-1115B/D were identified as the potential targets in the charging pump cubicles. The loss of the 1A and 1 B CC pumps is assumed to be the result of spray from the failure of either 4"-SLPD-50 or 6"-SA-21. Similarly, it was also

• determined that the four cables containing the power supply for CC pumps 1A, 1B and 1C as well as the power supply for Charging Pump 1C are subject to jet impingement. In one section of the AB basement the walkdown team concluded that the most manageable approach to indirect effects would be to assume that all of the PSA-credited equipment fails in its current state.

Additionally three sections of blowdown system piping which could be subject to pipe whip resulting in the failure of smaller diameter pipe were identified. MSVH/Safeguards Flooding/Spray The source of the flooding or spray was identified by PSA flooding analysis as a break in the main steam lines or the main feedwater lines. The worst case flooding effect identified in this area is the loss of the steam generator PORVs, the Containment spray pumps and the auxiliary feedwater pumps along with propagation of the flood to the Auxiliary Building which results in a loss of the charging pumps and the component cooling pumps .

• 23
• Area Table 3.3-2 Surry Unit 1 Summary of Indirect Effects Indirect Effect(s)

High Energy A rupture of the bypass line (6"-SHP-45-601) could result in a failure of the decay heat removal path upstream of the isolation valve. The steam supply line to the TDAFW pump (3"-SHP-57-601) was postulated to fail the 3A motor driven AFW pump by severing the power cord. It is assumed that the equipment in this area fails as a result of a main steam or feedwater line break. MER3 The most significant indirect consequence of piping rupture in this area is the partial loss of Control/Relay Room HVAC and Charging Pump SW pumps 1-SW-108 and 2-SW-10B. Turbine Building Flooding/Spray Loss of the ESGR due to flooding from the Turbine Building. High Energy Jet impingement from a high temperature line is postulated to cause the partial loss of offsite power. For any main steam or feedwater line break in the Turbine Building the team determined that the most manageable approach is to assume the MS and FW systems are lost. MERS Flooding/Spray The only significant flood source is the Service Water supply to the ESGR chillers with potential to disable two of five trains of the backup chillers for the Control Room\Relay Room HVAC system. ESW Pumphouse Flooding/Spray The only flood source in this area is the SW system-related piping .

• 24

TABLE3.3-3 CONSEQUENCE CALCULATION EXAMPLES WITHOUT OPERATOR ACTION SEGMENT ID SEGMENT DESCRIPTION DIRECT EFFECT INDIRECT EFFECT Surrogate Component CCDF(P)/ Surrogate Component CCDF(P)/ CLERF(P) CLERF(P) AFW-01 Pipe section from the Emergency Condensate Storage 1-FW-P-2 1.69E-3 Jet Impingement Spray 3.22E-4 Tank to the Turbine Driven Auxiliary Feedwater Pump 1-FW-P-3A 1.04E-4 1-FW-P-3A 2.47E-5 1-FW-P-3B 1-FW-P-3B RC-001 Reactor Vessel to Loop 1 Isolation Valve 1-RC-MOV- None - only IE None 1590. Intersects segments RC-16 and RC-20. LLOCA 9.4E-3/ 3.nE-5 RC-001 Reactor Vessel to Loop 1 Isolation Valve 1-RC-MOV- MLOCA 5.36E-3 None 1590. Intersects segments RC-16 and RC-20. 5.53E-6 RC-001 Reactor Vessel to Loop 1 Isolation Valve 1-RC-MOV- SLOCA 6.41 E-3 None 1590. Intersects segments RC-16 and RC-20. 1.65E-6 BD-008B Containment penetration 40 between 1-BD-TV-100E 1-BD-MOV-1 OOA/B 2.81E-2/ 1-BD-MOV-1 OOA/B 2.81E2/ and 1-BD-TV-100F. 1.63E-2 1-CH-MV-728 1.63E-2 1-MS-TV-101A/B/C 1-CC-TV-109A/B 1-S1-M0V-1842/67C/67D/69A BD-008B Containment penetration 40 between 1-BD-TV-100E See above row 1-BD-MOV-1 OOA/B 2.81E-2/ and 1-BD-TV-100F. 1-CH-MV-728 1.63E-2 1-MS-TV-101 A/B/C 1-CC-TV-109A/B 1-S1-MOV-1842/67C/67D/69A 1-CC-E-1A\1B 25

TABLE 3.3-4 CONSEQUENCE CALCULATION EXAMPLES WITH OPERATOR ACTION SEGMENT ID SEGMENT DESCRIPTION DIRECT EFFECT INDIRECT EFFECT Surrogate Component CCDP/ Surrogate Component CCDP CLERP AFW-01 Pipe section from the Emergency Condensate Storage 1-CN-TK-1 3.63E-4/ Jet Impingement Spray Included with Tank to the Turbine Driven Auxiliary Feedwater Pump 1-CN-151 2.59E-5 1FW-P-3A direct 1-FW-P-3A 1FW-P-3B 1-FW-P-3B 26

• 3.4 Failure Probability Assessment Failure probability estimates must be generated in order to determine piping segment core damage frequency (CDF) and large early release frequency (LERF). A subpanel was formed to estimate these failure probabilities. The subpanel used a Westinghouse developed simplified structural reliability and risk assessment (SRRA) software program to aid in the process. Refer to WCAP-14572, Revision 1, Supplement 1 for a description of the SRRA software.

The SRRA software in conjunction with industry failure history, plant specific failure history and relevant information including expert opinion determined the final failure estimates. The specific piping failure events considered are small leaks (through-wall crack), large leaks (based upon the segment disabling leak rate) and full breaks (only used for pipe whip consideration in indirect effects). Piping is defined as straight pipe, elbows, tees, other similar piping components, and their connecting welds. The subpanel members familiarized themselves with the piping materials, system thermal operating modes (pressure, temperature, number of cycles, etc.), thermal transients, extended lay-up or intermittent system operation, system water chemistry, and previous ISi experience. Operating experience or problems such as cracks, leaks, repairs, corrosion, valve leakage, vibration (operation and testing), pipe support problems, high steam/condensate flows, and inadvertent or unexpected transients were considered. Information from industry failure records and the appropriate system engineers was also evaluated. The methodology analyzes one or more points on a defined piping segment at the location deemed by the subpanel most susceptible to a postulated failure mechanism. Examples of the failure mechanisms considered by the subpanel are given in Table 3.4-1. After determining the postulated failure mechanism at the selected location, the subpanel determined the appropriate inputs for the SRRA software. The SRRA worksheets contain the actual inputs and assumptions used. The order corresponds with the actual SRRA code entry requirement. The subpanel identified on the appropriate form the locations evaluated and postulated failure. mode(s). Snubbers are evaluated based upon their failure to stay unlocked in thermal

• conditions and their failure to lock-up in a seismic event. The failure to stay unlocked in a thermal event is accounted for in a separate run where all data 27
• entries are maintained except for fatigue stress range. This value is increased to a higher value by expert judgment. The failure to lock-up in seismic conditions is accounted for in a separate run where all data entries are maintained except for design limiting stress. This value is increased to a higher value by expert judgment.

The small leak, large leak, and break probability for the snubber malfunctions are divided by 10 to account for the snubber inspection and testing program which maintains a 90% reliability of the snubber performing correctly (in some instances the probability value is divided by 5 instead of 1O if there are a large number of snubbers). The probabilities are compared (normal and snubber malfunctions modified). The highest values are used for the segment (leak and break). As previously indicated, the SRRA code could not be used for all failure mechanisms or piping materials. In these instances values were determined using alternative means. Generally, the SRRA code was used to give an idea of where the possible ranges of failure probability would fall. For example pitting wear is not modeled in the SRRA code. However, the code does model wastage (erosion/corrosion) and fatigue. The probability for pitting wastage was bounded by these type mechanisms so we were able to establish an upper and lower bound failure probability. The final probabili.ty selected was determined by panel members using the bounding information and industry experience. Another consideration was whether a segment belongs to either the SCC or erosion corrosion augmented programs. This information is needed to determine which failure probability is used in the risk-informed ISi process. The failure probabilities used in the risk-informed process are documented and maintained in the plant records. Table 3.4-2 is provided as an example of the failure probabilities estimated. The segments were also evaluated for test interval (time between testing). The interval determined how the failure probability would be used in the risk evaluation described in section 3.5. The test interval analysis assumed that leakage would be found during the testing .

• 28
• Erosion Erosion Table 3.4-1 Examples of Failure Causes Fatigue (high or low cycle)

Mechanical Erosion/Corrosion Thermal Mechanical wear Vibrational Fretting Cavitation Corrosion Bulk corrosion Embrittlement Crevice corrosion Irradiation Pitting corrosion Thermal aging Galvanic corrosion Microbiologically influenced Pitting Corrosion/Cracking lnteroranular Mechanical Damage Transgranular Water hammer Improper or degraded supports Fabrication/Maintenance Improper or degraded restraints Improper heat treatment External loads/impact Improper repairs or alterations Dissimilar metal weld

• 29
• Table 3.4-2 Surry Unit 1 Example Pipe Failure Probabilities Segment ID Postulated Failure Small Leak Small Leak Large Leak Large Leak Mode(s) Probability Probability Probability Probability No ISi With ISi No ISi With ISi No Leak No Leak Detection Detection AFW-001 Corrosion 8.80E-03 8.80E-04 8.80E-03 8.80E-04 CC-025 Vibration fatigue 8.SOE-02 8.19E-02 3.43E-02 3.30E-02 CH-021 Stress corrosion cracking 1.22E-03 7.53E-05 6.00E-04 6.45E-07 CN-001 Wastage/water hammer 3.60E-01 3.60E-02 3.60E-01 3.60E-02 ECC-003 Thermal stratification 8.67E-04 9.35E-05 8.30E-04 2.91E-05 FW-012 Wastage 3.60E-01 3.60E-02 3.60E-01 3.60E-02 HHl-004C Snubber locks up under 3.88E-05 2.76E-06 2.66E-05 9.14E-07 thermal conditions LHl-004 Fatigue 2.01E-05 7.48E-07 1.52E-05 1.17E-07 MS-033 Wastage 2.63E-02 2.63E-03 2.63E-02 2.63E-03 RC-016 Striping/stratification 5.31 E-04 1.70E-05 3.09E-04 5.52E-06 Large LOCA RC-016 Striping/stratification 5.31E-04 1.70E-05 3.34E-04 6.35E-06 Med LOCA RC-016 Striping/stratification 5.31E-04 1.70E-05 3.59E-04 7.00E-06 Small LOCA RC-058 Fatigue 4.15E-05 3.20E-05 4.56E-05 2.81E-05 Med LOCA RC-058 Fatigue 4.15E-05 3.20E-05 4.56E-05 2.81E-05 Small LOCA RH-003A SCC/vibration fatigue 6.78E-02 1.52E-02 4.55E-02 8.19E-03.

SW-004 Fatigue 1.00E-02 1.00E-02 1.00E-02 1.00E-02 VS-002 Vibration fatigue 6.63E-03 2.85E-03 8.69E-03 4.0SE-03

• 30

3.5 Risk Evaluation Each piping segment within the scope of the program was evaluated to determine its core damage frequency with and without operator action, and large early release frequency with and without operator action due to the postulated piping failure. Once this evaluation is completed, the total piping pressure boundary core damage frequency and large early release frequency are calculated by summing across the segments for each system. The calculational methods are described in WCAP-14572, Revision 1, Section 3.6. These four calculations for each segment provide the baseline from which risk importance measures can be determined. The results of these calculations are presented in Table 3.5-1. The core damage frequency due to piping failure without operator action is 6.28E-05/year, and with operator action is 4.0SE-06/year. The large early release frequency due to piping failure without operator action is 5.1 BE-06/year, and with operator action is 4.46E-07/year. These calculations took no credit for inspection-activities other than augmented programs. To assess safety significance, the risk reduction worth (RRW) was calculated for each piping segment. A summary of the segments for each

• system that fall into the various risk categories is given in Table 3.5-2. A list of segments with RRW values greater than 1.005 is given in Table 3.5-3. The segments with RRW values from 1.001 to 1.005 were deemed to be worthy of additional consideration by the plant expert panel.

The risk achievement worth (RAW) was also calculated for each piping segment. However, it was determined that the RAW values did not differentiate importance between segments. For example, most segments had a RAW value greater than 2 which is the RAW limit for designating a segment as important per NUMARC 9301 1 . References

1. NUMARC 93-01, Revision 2, "Industry Guideline For Monitoring Effectiveness of Maintenance at Nuclear Power Plants," April 1996

• 31
• System # of Segments CDF without Table 3.5-1 Surry Unit 1 Number of Segments and Pi :>ing Risk Contribution by System CDF with LERF without LERF with Operator Operator Operator Operator Action Action Action Action ACC 15 4.68E-11 3.06E-11 2.76E-11 3.81 E-11 AFW 32 6.54E-6 2.59E-7 2.66E-7 1.28E-8 AS 2 7.84E-9 7.84E-9 7.85E-9 7.85E-9 BD 12 4.60E-7 4.60E-7 2.68E-7 2.68E-7 cc 66 2.34E-8 1.90E-8 1.97E-8 1.60E-8 CH 44 2.73E-7 2.73E-7 1.54E-9 1.54E-9 CN 9 1.20E-6 4.27E-8 6.74E-8 1.13E-9 cs 16 1.42E-7 9.74E-9 1.21 E-8 2.17E-9 cw 16 1.00E-7 1.00E-7 2.79E-9 2.79E-9 ECC 8 9.78E-11 9.78E-11 8.08E-12 8.08E-12 EE 7 5.56E-10 5.56E-10 7.82E-12 7.82E-12 FC 9 N/A N/A N/A N/A FW 20 4.76E-7 4.75E-7 2.51 E-8 2.51E-8
• HHI LHI MS RC RH 27 18 38 96 11 8.0SE-7 8.79E-8 4.25E-7 1.61 E-6 6.54E-8 1.71 E-7 1.44E-9 4.25E-7 1.60E-6 6.54E-8 7.17E-8 7.43E-9 1.03E-8 4.56E-9 6.55E-8 1.88E-8 5.02E-11 1.03E-8 4.54E-9 6.55E-8 RS 13 3.81E-9 1.58E-9 5.85E-12 0 SW 54 4.37E-5 1.43E-7 4.13E-6 1.02E-8 vs 2 6.84E-6 0 2.24E-7 0 TOTAL 515 6.28E-5 4.05E-6 5.18E-6 4.46E-7
• 32
• Table 3.5-2 Surry Unit 1 Summary of Safety Significant Segments

                              # of Segments                      # of Segments
                                                 # of Segments with RRW>        with RRW from      with RRW<

System # of Segments 1.005 1.001 to 1.005 1.001 ACC 15 0 0 15 AFW 32 8 10 14 AS 2 2 0 0 BO 12 6 0 6 cc 66 3 10 53 CH 44 3 0 41 CN 9 . 1 0 8 cs 16 0 6 10

• cw ECC EE 16 8

7 4 0 0 0 0 0 12 8 7 FC 9 N/A N/A N/A FW 20 6 7 7 HHI 27 5 3 19 LHI 18 0 0 18 MS 38 2 8 28 RC 96 10 21 65 RH 11 2 1 8 RS 13 0 0 13 SW 54 11 18 25 vs 2 1 1 0

• TOTAL 515 64 33 85 357
• Table 3.5-3 Surry Unit 1 Results Segment Summary by System (Segments with RRW > 1.005)

Segment ID RRW Applicable Case {CDF/LERF, W/ or W/0 Operator Action) ACC None AFW AFW-4 1.02 CDF-Op act 1.008 LERF- Op act AFW-5 1.02 CDF- Op act AFW-6 1.02 CDF- Op act AFW-15 1.01 CDF - No Op act 1.006 LERF - No Op act AFW-16 1.01 CDF- No Op act

• AFW-17 AFW-18 1.006 1.02 1.01 1.02 1.01 LERF - No Op act CDF- No Op act LERF - No Op act CDF- No Op act LERF - No Op act AFW-19 1.02 CDF- No Op act 1.01 LERF - No Op act AS AS-1 1.005 LERF - Op act AS-2 1.01 LERF - Op act BD BD-0028 1.02 CDF-Op act 1.009 LERF - No Op act 1.11 LERF - Op act BD-003 1.02 CDF- Op act 1.009 LERF - No Op act 1.11 LERF - Op act BD-0058 1.02 CDF- Op act 1.009 LERF - No Op act 1.11 LERF - Op act 34

Table 3.5-3

• Segment ID Surry Unit 1 Results Segment Summary by System (Segments with RRW > 1.005)

RRW Applicable Case (CDF/LERF, W/ or W/0 Operator Action) BD-006 1.02 CDF- Op act 1.009 LERF - No Op act 1.11 LERF - Op act BD-0088 1.02 CDF- Op act 1.009 LERF - No Op act 1.11 LERF - Op act BD-009 1.02 CDF- Op act 1.009 LERF - No Op act 1.11 LERF - Op act cc CC-25 1.008 LERF - Op act CC-30 1.008 LERF - Op act CC-33 1.008 LERF - Op act

• CH CH-008 CH-009 CH-010 1.02 1.02 1.02 CDF - Op act CDF - Op act CDF - Op act CN CN-008 1.02 CDF - No Op act 1.007 CDF - Op act 1.013 LERF - No Op act cs None cw CW-5 1.006 CDF-Op act CW-6 1.006 CDF-Op act CW-7 1.006 CDF-Op act CW-8 1.006 CDF-Op act ECC None
• 35

Table 3.5-3 Surry Unit 1 Results Segment Summary by System (Segments with RRW > 1.005) Segment ID RRW Applicable Case (CDF/LERF, W/ or W/0 Operator Action) EE None FC NIA FW FW-1 1.007 LERF - Op act FW-2 1.007 LERF - Op act FW-5 1.008 LERF - Op act FW-12 1.008 LERF - Op act 1.04 GDF - Op act FW-13 1.008 LERF - Op act 1.04 GDF - Op act

• HHI FW-14 HHl-10 1.008 1.04 1.008 LERF - Op act GDF - Op act LERF - Op act 1.008 GDF - Op act HHl-12A 1.005 LERF - Op act 1.009 GDF - Op act HHl-13 1.009 LERF - Op act 1.008 GDF - Op act HHl-15 1.009 LERF - Op act 1.008 GDF - Op act HHl-17 1.009 LERF - Op act 1.008 GDF - Op act LHI None MS MS-33 1.009 LERF - Op act 1.041 GDF - Op act
• 36

Table 3.5-3 Surry Unit 1 Results Segment Summary by System (Segments with RRW > 1.005) Segment ID RRW Applicable Case (CDF/LERF, W/ or W/0 Operator Action) MS-34 1.009 LERF - Op act 1.041 CDF - Op act RC RC-16 1.03 CDF- Op act RC-17 1.03 CDF- Op act RC-18 1.05 CDF- Op act RC-19 1.009 CDF- Op act RC-37 1.01 CDF- Op act RC-38 1.01 CDF- Op act RC-39 1.01 CDF- Op act RC-41 1.07 CDF- Op act RC-42 1.06 CDF- Op act RC-43 1.06 CDF- Op act RH RH-003 1.025 LERF - Op act RH-0038 1.01 CDF- Op act 1.01 LERF - No Op act 1.13 LERF - Op act RS None I SW SW-04 1.006 CDF- Op act SW-05 1.006 CDF- Op act SW-06 1.006 CDF- Op act SW-18 1.09 CDF - No Op act 1.11 LERF - No Op act SW-19 1.09 CDF - No Op act 1.11 LERF - No Op act SW-20 1.09 CDF - No Op act 1.11 LERF - No Op act 37

Table 3.5-3 Surry Unit 1 Results Segment Summary by System (Segments with RRW > 1.005) Segment ID RRW Applicable Case (CDF/LERF, W/ or W/0 Operator Action) SW-21 1.09 GDF - No Op act 1.11 LERF - No Op act SW-22 1.09 GDF - No Op act 1.11 LERF - No Op act SW-23 1.09 GDF - No Op act 1.11 LERF - No Op act SW-24 1.09 GDF - No Op act 1.11 LERF - No Op act SW-25 1.09 GDF - No Op act 1.11 LERF - No Op act vs VS-2 1.12 GDF - No Op act 1.044 LERF - No Op act

• 38

3.6 Expert Panel Categorization The final safety determination (high and low safety significance) of each piping segment was made by the expert panel using both probabilistic and deterministic insights. The expert panel was comprised of personnel who have expertise in the following fields; probabilistic safety assessment, inservice examination, nondestructive examination, stress and material considerations, plant operations, plant and industry maintenance, repair, and failure history, and system design and operation. Members did not need to be experts in every field; however, diversity of expertise was considered to prevent heavy reliance on any one member's judgment. Use of members associated with the Maintenance Rule was considered to ensure consistency with the other PSA applications. Alternates were used if their expertise and training were sufficient. The expert panel had the following positions represented by either the permanent or alternate member at all times during an expert panel meeting.

• Probabilistic Safety Assessment (PSA engineer)
• Operations (Senior Reactor Operator or Shift Technical Advisor)
• lnservice Inspection (ISi)
• Plant & Industry Maintenance , Repair, and Failure History (System Engineer)

A minimum of 4 members or alternates filling the above positions constituted a quorum. The expert panel chairperson was appointed by the Nuclear Engineering Manager. The chairperson conducted and ruled on the proceedings of the meeting. The chairperson appointed an alternate chairperson from the panel if he was unable to attend a meeting. Members and alternates received training and indoctrination in the risk-informed inservice inspection selection process. It included indoctrination in the application of risk analysis techniques (risk importance measures, threshold values, failure probability models, failure mode assessments, PSA modeling limitations and the use of expert judgment) for ISi. Training documentation was maintained with the expert panel's records.

• Worksheets were provided to the panel on each system for each piping
• segment, containing information pertinent to the panel's selection process.

Examples of these wor.ksheets can be found in WCAP-14572, Revision 1, pages 39

8-22 through 8-40. This information in conjunction with the panel member's own expertise and other documents as appropriate were used in determining the safety significance of a piping segment. The consensus process was used by the expert panel. Consensus is defined as unanimous during first consideration and 2/3 (rounding conservatively) of members or alternates present in the second or subsequent considerations. The chairperson shall allow appropriate time duration between considerations for deliberation. The chairperson appointed someone to record the minutes of each meeting. The minutes included the names of members and alternates in attendance and whether a quorum was present. The minutes contained relevant discussion summaries and the results of membership voting. These minutes are available as program records. An example of the minutes taken is provided in Attachment 3. The initial expert panel was comprised of the following members.

• Chairman - Jack Martin (Primary) Alternate as designated
• PSA - Ron Thomas (Primary) Dave 8ucheit (Alternate)

Operations - Jim Simpson (Primary) lnservice Inspection - Dave Rogers (Primary) John Paul (Alternate)

• Plant & Industry Maintenance , Repair, and Failure History - Gary Thompson (Primary) Spencer Semmes (Alternate)
• Engineering Mechanics - Nitin Shah
• NOE - Dave Dodson
• Failure Lab/ Materials - Leslie L. Spain
• 40

3.7 Identification of High Safety Significant Segments

• The results of the categorization of the piping segments into high and low safety significant segments as determined by the expert panel are summarized in Table 3.7-1. A summary of the high safety significant segments and the basis for the determination by the expert panel is shown in Table 3.7-2.

A comparison of the results of the expert panel safety significance determination and the risk importance measure determination is shown in Table 3.7-3. This comparison shows a generally good agreement between the piping segments chosen by the expert panel and those identified by risk importance measure calculations. Several piping segments that were identified through the calculations to be high safety significant were determined by the panel to either have a lesser consequence or inappropriate failure mechanism which resulted in the change to the categorization. A numerical analysis reflecting the panel's opinion was performed to support these changes. In other instances, piping segments which were identified through the calculations to be low safety significant were assigned to the high safety significance category because of more severe consequences postulated by the expert panel or the consideration of other deterministic insights .

• 41
• Table 3.7-1 Surry Unit 1 Summary of High and Low Safety Significant Segments as Determined by Plant Expert Panel System Number of Number of High Number of Low Segments Safety Significant Safety Significant Segments Segments ACC 15 0 15 AFW 32 11 21 - i AS 2 2 0 BD 12 6 6 cc 66 6 60 CH 44 8 36 CN 9 0 9 cs 16 0 16 cw 16 4 12 ECG 8 7 1 EE 7 0 7 FC 9 0 9 FW 20 13 7 HHI 27 14 13 LHI 18 7 11 MS 38 3 35 RC 96 11 85 RH 11 4 7 RS 13 2 11 SW 54 8 46 VS 2 2 0 TOTAL 515 108 407
• 42
• Segment IDs AFW-4,5,6 Table 3.7-2 Surry Unit 1 Summary of High Safety-Significant Segments Description of Segments AFW pumps to check valves Basis for Safety Significance Loss of emergency condensate
• storage tank (CST) and all flowpaths to each AFW pump; High leak probability from corrosion AFW-15, 16, 17, 18, 19 Piping between check valves and Loss of emergency CST and all MOVs auxiliary feedwater, including crosstie from Unit 2; flow-assisted corrosion (FAC) program needs to continue AFW-30,31,32 Piping from check valves to manual Loss of turbine-driven AFW pump valves and motor-driven AFW pump oil cooler; possible water spray impact resulting in loss of all AFW pumps AS-1 Piping above the component cooling Indirect effect of spray and jet water pumps impingement on component cooling water (CCW) pumps, Unit 1 CCW system disabled AS-2 Piping above component cooling Indirect effect of spray and jet pumps; piping under power cables to impingement on 3 CCW pumps and the charging pump 1 charging pump BD-28,3,58,6,88,9 Containment penetration to Loss of containment integrity, small containment isolation valve, piping steam line break outside containment beyond outside containment isolation with no reactor trip, loss of blowdown, valves loss of SG isolation on steam generator tube rupture (SGTR);

indirect effects of spray and jet impingement on CCW supply, main steam (MS) trip valve, 3 safety injection (SI) MOVs CC-25, 30, 33 CCW for the RCPs from containment Loss of Unit 1 and 2 CCW systems, penetration loss of cooling to the RCP motors causing reactor trip, previous leaks on line CC-28A, 288 CCW pipe on the discharge of RCPs Loss of Unit 1 and 2 CCW systems inside containment, loss of cooling to

                                                             . the RCP motors causing reactor trip, potential thermal barrier leak CC-29                  CCW pipe on the RCPs thermal           Loss of Unit 1 and 2 CCW systems, barrier discharge paths                loss of cooling to the RCP motors causing reactor trip, potential thermal barrier leak

• 43

Table 3.7-2 Surry Unit 1 Summary of High Safety-Significant Segments Segment IDs Description of Segments Basis for Safety Significance CH-5 Containment penetration for RCP Indirect effects of spray and jet seal injection return to MOV impingement causing loss of CCW to RHR, 3 MS trip valves, 3 SI MOVs, one blowdown MOV CH-7A,8,9,10 Bypass line on seal return from Line failure results in small LOCA; RCPs; piping to RCP seals between 3 vibratory fatigue concerns pump casings and check valves CH-11,12,13 Seal injection path between Loss of charging system support to containment penetration RCPs; vibratory fatigue concerns CW-5,6,7,8 Condenser circulating water (CW) Loss of each CW header to supply header from intake structure to condenser, loss of cooling to recirc intersection of spray heat exchangers (HX); loss of service water supply to bearing cooling HX and emergency switch gear chillers; indirect effects from flooding ECC-0 Piping from refueling water storage 1,.oss of RWST outside containment; tank (RWST) to check valves crosstie to Unit 2 would not automatically activate

• ECC-1,2,3 Piping to cold legs between 1st and 2na isolation (check) valves Loss of RWST inside containment; potential inter-system (IS) LOCA initiating event; degradation of cold leg injection; only one injection path to a cold leg, flow restrictors limit flow; common mode failure mechanism ECC-5,6,7 Piping to hot legs between 1st and 2nd Loss of injection to each hot leg on isolation (check) valves recirculation from high and low pressure trains; Potential ISLOCA initiating event; degradation of hot leg injection path FW-1,2,3,4,5,6,7 From feedwater (FW) headers to Loss of main feedwater 18x24 reducer; supply lines to FW pumps; recirculation header to condenser; FW pump discharge header FW- Feedwater header to steam Loss of main feedwater 12,13,14,15,16,17 generators HHl-1,2,3 Piping from RWST to suction of Loss of RWST and loss of Unit 2 charging pumps RWST cross-connect to charging pumps
• 44

Table 3.7-2 Surry Unit 1 Summary of High Safety-Significant Segments Segment IDs Description of Segments Basis for Safety Significance HHl-4C,5C,6C Discharge piping from charging Loss of RWST, loss of Unit 2 RWST pumps cross-connect to Unit 1 charging pumps and loss of Unit 2 charging pumps cross-connect to unit, loss of volume control tank (VCT) and boric acid tank (BAT) to the charging pumps HHl-8,9 Normal charging/injection to cold and Loss of RWST outside containment, hot legs/seal injection between loss of Unit 2 RWST cross-connect to several valves Unit 1, and loss of Unit 2 charging pumps cross-connect; loss of VCT and BAT HHl-10, 11 Normal injection paths to cold legs Loss of RWST outside containment, between several valves and loss of Unit 2 RWST cross-connect to containment Unit 1, and loss of Unit 2 charging pumps cross-connect; potential interruption of high head flow until operator recognizes, isolates and aligns alternate charging HHl-12A To cold legs between several valves Loss of all cold leg injection HHl-13,15 Alternate/normal injection path to Loss of RWST outside containment, cold/hot legs between MOVs and loss of Unit 2 RWST cross-connect to containment Unit 1, and loss of Unit 2 charging pumps cross-connect, and loss of alternate path of HHSI to cold legs; indirect effects from spray and jet impingement on CCW supply and several MOVs HHl-17 Normal injection path to hot legs Loss of containment sump inventory between MOV and containment if MOV is open; loss of alternate path of HHSI to hot legs (but normal path available) if MOV is closed LHl-3,4 Containment sump to MOV Loss of recirculation from each low pressure injection train LHl-7,8 Train 8/A from check valve to HPI Loss of RWST outside containment. suction MOV, RWST recirc, hot leg Break momentarily disrupts flow. injection MOV and cold leg injection Large break LOCA - LH pumps most important depending on timing, HH pumps could provide core cooling .

• 45

Table 3.7-2 Surry Unit 1 Summary of High Safety-Significant Segments Segment IDs Description of Segments Basis for Safety Significance LHl-9,10 Cold leg injection from SI-MOVs to Loss of RWST outside containment. SI-MOV and CV SI valves Break momentarily disrupts flow. Large break LOCA - LH pumps most important depending on timing, HH pumps could provide core cooling. LHl-18 Piping from 1-SI-MOVs to 1-CH- Loss of RWST outside containment MOVs and loss of Unit 2 cross connection; Loss of low and high pressure recirculation. Break momentarily disrupts flow. Large break LOCA - LH pumps most important depending on timing, HH pumps could provide core cooling. MS-32 Common main steam supply header Main steam line break (MSLB) to turbine driven AFW pump from outside containment. Jet check valves to normally closed impingement from MS line crack valves and steam trap would damage all components in MS valve house (all 3 AFW pumps, both containment spray pumps, 3 MS relief valves. Concern also in blowing down all 3 steam generators . (FAC program currently in place). MS-33,34 Common main steam supply header Loss of main steam to turbine-driven to the turbine driven AFW pump from AFW pump. MSLB outside normally closed valves containment. Jet impingement from MS line crack would damage all components in MS valve house (all 3 AFW pumps, both containment spray pumps, 3 MS relief valves. RC-16,17,18 Safety injection from first isolation Potential large, medium, or small check valve to Reactor coolant LOCA depending on break size with a system loop hot leg potential for striping/stratification and thermal fatigue. RC-37,38,39 Loop fill header from Reactor Coolant Potential small LOCA with high System to cold leg. potential for vibratory fatigue RC-41,42,43 Safety injection from first isolation Potential large, medium, or small check valve to reactor coolant loop LOCA depending on break size with a cold leg. potential for striping/stratification RC-58,59 From PORV block valve to Loss of cold overpressure mitigation pressurizer PORV. capability during shutdown

• 46

Table 3.7-2 Surry Unit 1 Summary of High Safety-Significant Segments Segment IDs Description of Segments Basis for Safety Significance RH-2 Header line between the two Residual Loss of RHR during steam generator Heat Removal suction isolation tube rupture (leads to LERF). Also valves loss of RHR and potential LOCA during shutdown RH-3 From Residual heat removal suction Loss of RHR during steam generator isolation valves through pumps and tube rupture (leads to LERF). Also heat exchangers to discharge motor loss of RHR and potential LOCA operated valves during shutdown RH-38 Line off main RHR header after RHR Loss of RHR during steam generator heat exchangers to RWST return line tube rupture (leads to LERF). Also isolation valve. loss of RHR and pot~ntial LOCA during shutdown RH-11 RWST return line between two Loss of containment boundary if the isolation valves and through path is open. Previous containment containment penetration integrity issue RS-3A,4A From containment sump penetration Loss of ORS pumps. Containment to pump inlet isolation valve penetration. Failure could lead to direct release outside containment (LERF) . SW-4,5,6 From service water pump discharge Loss of one service water pump with through the diesel cooler and shaft wastage potential; previous fiberglass bearing oil cooler to the intake failures at plant structure SW-44,45 Line from header to the charging Loss of cooling to one of the charging pump intermediate seal cooler pumps; potential spray may disable all charging pumps SW-46,47 From charging pump intermediate Loss of cooling to one of the charging seal cooler to discharge header pumps; potential spray may disable all charging pumps SW-54 Charging pump cooler discharge Loss of cooling to one of the charging header to unit 1 and Unit 2 isolation pumps; potential spray may disable valves to main discharge header all charging pumps VS-1 Makeup supply to surge tank Loss of Units 1 and 2 control Rooms and Emergency Switchgear Rooms Water Cooled Chillers VS-2 The main piping of the chilled water Loss of Units 1 and 2 control Rooms system and Emergency Switchgear Rooms Water Cooled Chillers

• 47

• Table 3.7-3 Surry Unit 1 Comparison of Expert Panel and Risk Calculations (Note 1) in Safety Significance Determination System Expert Panel CDF Without CDF With LERF Without LERF With No Credit for Final Decision Operator Operator Action Operator Action Operator Action Augmented Programs Action (Note 2)

ACC None None None None None None AFW AFW-4, 5, 6, 15, AFW-15, 16, AFW-4, 5, 6 AFW-15, 16, 17, AFW-4 AFW-15, 16, 17, 18, 19 16, 17, 18, 19, 30, 17, 18, 19 18, 19 (CDF/LERF - No Op. 31, 32 Act.), 28 (GDF-Op. Act) AS AS-1, 2 None None None AS-1, 2 None BD 8D-28, 3, 58, 6, None 8D-0028, 003, 8D-0028, 003, 8D-0028, 003, 8D-002B, 003, 0058, 88,9 0058, 006, 0088, 0058, 006, 0088, 0058, 006, 0088, 006, 0088,009 009 009 009 (CDF/LERF - No Op. Act./Op. Act.) cc CC-25, 28A, 288, None None None CC-25, 30, 33 None 29,30, 33 CH CH-5, 7A, 8, 9, None CH-008, 009, 010 None None CH-008, 009, 010 10, 11, 12, 13 (GDF-Op. Act.) (Note 3) CN None CN-008 CN-008 CN-008 None CN-008 (CDF/LERF - No Op. Act.) cs None None None None None None cw CW-5, 6, 7, 8 None CW-5, 6, 7, 8 None None None ECG ECC-0, 1, 2, 3, 5, None None None None None 6, 7 EE None None None None None None. FC None N/A N/A N/A N/A N/A 48

• Table 3.7-3 Surry Unit 1 Comparison of Expert Panel and Risk Calculations (Note 1) in Safety Significance Determination System Expert Panel GDF Without GDF With LERF Without LERF With No Credit for Final Decision Operator Operator Action Operator Action Operator Action Augmented Programs Action (Note 2)

FW FW-1, 2, 3, 4, 5, None FW-12, 13, 14 None FW-1, 2, 5, 12, FW-1, 2, 5 (LERF-Op. 6, 7, 12, 13, 14, 13, 14 Act.), 12, 13, 14 (GDF-15, 16, 17 No Op. Act., CDF/LERF-Op. Act.), 15, 16, 17 (GDF-Op. Act.) HHI HHl-1, 2, 3, 4C, None HHl-10, 12A, 13, None HHl-10, 12A, 13, HHl-4A (CDF/LERF-No SC, 6C, 8, 9, 10, 15, 17 15, 17 Op. Act.), 12A 11, 12A, 13, 15, (CDF/LERF-No Op. 17 Act./Op. Act.) LHI LHl-3, 4, 7, 8, 9, None None None None None 10, 18 MS MS-32, 33, 34 None MS-33, 34 None MS-33, 34 MS-32 (GDF-Op. Act.), 33, 34 (GDF-No Op. Act., CDF/LERF-Op. Act.) RC RC-16, 17, 18, 37, None RC-16, 17, 18, 19, None None RC-16, 17, 18, 41, 42, 38, 39, 41, 42, 43, 37, 38, 39, 41, 42, 43 (GDF-Op. Act.) 58, 59 43 (Note 4) RH RH-2, 3, 38, 11 None RH-0038 RH-0038 RH-003, 0038 RH-0038 (LERF-No Op. Act./Op. Act.) RS RS-3A, 4A None None None None None SW SW-4, 5, 6, 44, SW-18, 19, SW-04, 05, 06 SW-18, 19, 20, None SW-18, 19, 20, 21, 22, 45,46,47, 54 20, 21, 22, 21,22,23,24,25 23, 24, 25 (CDF/LERF-(Note 5) 23,24,25 No Op. Act.) 49

• Table 3.7-3 Surry Unit 1 Comparison of Expert Panel and Risk Calculations (Note 1) in Safety Significance Determination System Expert Panel CDF Without CDF With LERF Without LERF With No Credit for Final Decision Operator Operator Action Operator Action Operator Action Augmented Programs Action (Note 2) vs VS-1, 2 VS-2 None VS-2 None VS-2 (CDF/LERF-No Op. Act.)

Notes

1. For risk calculations, the segments identified as high safety significant had calculated values for RRW of greater than 1.005.

2. No segments other than those piping segments already in an augmented program were identified.

3. During the expert panel meeting, segment CH-07 was subdivided into 2 segments, CH-07A and CH-078. The consequences for CH-07A were identified to be commensurate with CH-08 and thus was identified as a high safety significant segment.

4. During the expert panel meeting, the failure mechanism and thus the probability for segment RC-19 was determined to not to be appropriate for the Surry plant. Therefore, the failure probability was reduced and the segment became low safety significant.

5. During the expert panel meeting, the failure mechanism and thus the probability for segments SW-18, 19, 20, 21, 22, 23, 24 and 25 was determined to not occur because of the coating on the inside of the piping. Therefore, the failure probability was reduced and the segments became low safety significant.

50

Structural Element and NOE Selection 3.8 Initial Program The initial program being submitted addresses piping components placed in regions 1 and 2 of Figure 3.7-1 in WCAP-14572, Revision 1. Region 3 piping components are to be considered in an Owner Defined Program and is not considered part of the program requiring approval. Region 1, 2, 3 and 4 piping components will continue to receive Code required pressure testing, if part of the current ASME Section XI program. The expert panel directed a subpanel to determine final examination locations and methods. The number of locations to be inspected on a segment was determined using a Westinghouse statistical (Perdue) model as described in section 3.7 of WCAP-14572, Revision 1. Table 4.1-1 in WCAP-14752, Revision 1, was used as guidance in determining the examination requirements. The examinations proposed are listed in Attachment 4. The attachment does not include VT-2 visual examinations of an entire segment required by the subpanel. These examinations are scheduled in accordance with the station's pressure test program which remains unaffected by the risk-informed inspection program. The examinations currently scheduled by the existing ISi program are given in Attachment 5. The table in Attachment 5 is sorted by segment for comparison to the table in Attachment 4. A discussion of changes is given in Section 5 . Additional Examinations Since the risk-informed inspection program will require examinations on a large number of elements constructed to lesser inspection requirements, the program in all cases will determine through an engineering evaluation the root cause of any unacceptable flaw or relevant condition found during examination. The evaluation will include the applicable service conditions and degradation mechanisms to establish that the element(s) will still perform their intended safety function during subsequent operation. Elements not meeting this requirement will be repaired or replaced. The evaluation will include whether other elements on the segment or segments are subject to the same root cause and degradation mechanism. Additional examinations will be performed on these elements up to a number equivalent to the number of elements required to be inspected on the segment or segments initially. If unacceptable flaws or relevant conditions are again found similar to the initial problem, the remaining elements identified as susceptible will be examined. No additional examinations will be performed if there are no additional 51

elements identified as being susceptible to the same service related root cause conditions or degradation mechanism .

• 52

3.9 Program Relief Requests The current ASME Section XI inservice inspection requirements delineated by 1o CFR 50.55a(g) has provisions for requesting relief for impractical Code requirements. These relief requests are approved pursuant to 10 CFR 50.55a(g)(6)(i). The proposed RI-ISi program addresses piping only. Current relief requests of administrative nature (e.g., weld identification or marking) or dealing with nonpiping components (e.g., vessels) are unaffected as the existing ASME Section XI program requirements are being maintained. Relief requests for piping are no longer required as our program is being submitted as an alternative (10 CFR 50.55a(a)(3)). In the past relief requests were generated when examination coverage of a weld did not meet the 90% coverage criteria (Code Case N-460). The guidance in WCAP-14572, Table 4.1-1 note 3 and in Code Case N-577, Table 1 note 3, indicates that areas with acceptable limited examinations and their bases shall be documented. It is our intention to accept examinations which exceed 90% coverage as they are currently accepted. Examinations which do not meet this coverage (>90%) criteria will be evaluated for acceptability with the basis documented including a statement as to how the risk is still being addressed. The documentation

• of acceptability will be maintained as a record. This handling of partial examinations represents a change to current practice .
• 53

3.1 O Change in Risk, Defense-In-Depth and New Information

• Change in Risk A comparison between the proposed RI-ISi program and the current Section XI ISi program was made to evaluate the change in risk. Two approaches were used to compare the CDF and LERF changes.

The first approach assumed that for any segment a) in the current Section XI program (for the Section XI risk calculation) orb) in the proposed RI-ISi program (for that calculation) or, c) in the augmented program, the risk associated with that segment would be addressed completely (with 100% effectiveness). The results from this approach are shown in Figures 3.10-1 and 3.10-2 by system, for CDF and LERF, respectively. As shown by the figures, the RI-ISi program (with augmented examinations) addresses approximately 86% of the CDF risk while the current Section XI program (with augmented examinations) addresses about 53%. Similarly, the RI-ISi program (with augmented examinations) addresses approximately 94% of the LERF risk while the current Section XI program addresses only 20%. The systems that lead to the improved risk coverage in the RI-ISi program are blowdown, feedwater, main steam and auxiliary feedwater . The second approach evaluated the change in risk with the inclusion of the probability of detection as determined by the SRRA model. For this risk comparison between the current Section XI ISi program calculations and the recommended RI-ISi program calculations, the following conditions were used:

• For piping segments that are part of augmented programs (such as erosion-corrosion and stress corrosion cracking), the SRRA failure probabilities with ISi were used (no change from previous calculations).
• For other piping segments, the failure probability with ISi for those being inspected by NOE were used.
• For the RCS piping segments, the failure probabilities with ISi for those being inspected by NOE and without ISi for those not being inspected were used along with credit for leak detection.
• The risk calculations were performed for all 4 cases (CDF and LERF with and without operator action). The calculations with operator 54

recovery action from the piping failure assumed perfect operators, that

• is, no human error probabilities was included.
• For piping segments that are in both the Section XI program and the augmented program, no additional credit was given to the Section XI program in the calculations.
• For piping segments that are in both the RI-ISi program and the augmented program, no additional credit was given to the RI-ISi program in the calculations.
• For selected piping segments that are in both the RI-ISi program and the augmented program in which additional or more stringent examinations were proposed beyond the augmented program, a factor of three improvement (based on work done by Khaleel and Simonen, 1994 which identified an improvement factor based on failure potential) in the failure probability was credited.

Criteria For Evaluation of Results The criteria for evaluating the results of the study are the following:

• 1. The total change in piping risk should be risk neutral or a risk reduction in moving from the current Section XI program to RI-ISi.

If not, the dominant system and piping segment contributors to the RI-ISi risk should be reexamined in an attempt to identify additional examinations which would make the application at least risk neutral. If additional examinations can be proposed, then the change in risk calculations should be revised to credit these additional examinations until at least a risk neutral position is achieved.

2. Once this risk neutral position is achieved, an evaluation of the dominant system contributors to the total risk for RI-ISi (e.g.,

system contribution to the total is greater than approximately 10%) should be examined to identify where no improvement has been proposed (i.e., where moving from no ISi or Section XI ISi to RI-ISi, the risk has not changed and it is-still a dominant contributor to the total CDF/LERF). If any systems are identified where this is the case, the dominant piping segments in that system should be reevaluated in an attempt to identify additional examinations which* would reduce the overall risk for these systems and thus possibly the overall risk .

• 55

The results should be reviewed to identify any system in which 3. there is a risk increase in moving from the Current Section XI program to the RI-ISi program. The following guidelines are suggested to identify if additional examinations are necessary:

• If the CDF increase for the system is approximately greater than two orders of magnitude below the RI-ISi CDF for that system or greater than 1E-08, (whichever is higher), then at least one dominant segment in that system should be reevaluated to identify additional examinations.
• If the LERF increase for the system is greater than two orders of magnitude below the RI-ISi LERF for that system or greater than 1E-09 (whichever is higher), then at least one dominant segment in that system should be reevaluated to identify additional examinations

4. If any additional examinations are identified, the change in risk calculations should be revised to credit these additional examinations.

These criteria provided added assurance that the risk from moving to the

• RI-ISi program has been addressed. For Surry, this evaluation resulted in the identification of 10 piping segments for which examinations are now required.

The results from the risk comparison for Surry are shown in Table 3.10-1 and Figure 3.10-3. As seen from the table and figure, the RI-ISi program reduces the risk associated with piping CDF/LERF slightly more than the current Section XI program while reducing the number of examinations required. A comparison between the total piping CDF/LERF and the total plant CDF/LERF (total plant CDF of 7.2E-05/year and total plant LERF of 1.1 E-05/year) was not made because both the piping CDF/LERF and the plant CDF/LERF address large, medium, and small LOCAs, steam line breaks and other events (i.e., there is overlap between the two models). A cost-benefit evaluation supporting the use of the RI-ISi program is given in WCAP-14572, Section 4.4.3. Defense-In-Depth As the reactor coolant piping serves as a fission product barrier, a concern developed as to whether sufficient inspection of the main reactor 56

coolant loop piping remained in the proposed program. The issue developed around the requirement to maintain "defense-in-depth." The reactor coolant piping will continue to receive a system pressure test and visual VT-2 examination as currently required by the Code. Surface and volumetric examinations are also being proposed on the smaller reactor coolant piping as part of the initial RI-ISi program. However, the larger diameter reactor coolant piping was not selected in the RI-ISi process. As such, larger reactor coolant loop piping segments were added back into the program for "defense-in-depth" considerations. The locations selected were associated with the reactor vessel dissimilar metal welds. These locations were identified as being the area to inspect in the RI-ISi process, if the segment was chosen. Additionally, these locations were identified as dominant locations on the loop piping during a previous risk based study completed at Surry by Pacific Northwest National Laboratories. This study focused on the reactor coolant system in part. New Information The final calculational review identified one segment (MS-10) as having a higher conditional consequence than previously analyzed due to indirect effects. A preliminary review of the revised numerical results indicate that the LERF results would make the segment High Safety Significant. The

• segment has been added to the program for inspection, however it's inclusion is not reflected in the change in risk analysis, associated charts, nor was it presented to the expert panel. It has only been added to attachment 4. Other new information may be identified in the interim during the approval process. Segment additions associated with this new information will be handled similarly.

A summary of segment additions for change in risk, defense-in-depth, and new information considerations is provided in Table 3.10-2 .

• 57

100.00% 90.00%

                                                           ----  __,_                 T       T 80.00%

70.00%

                                        ~

C m 60.00% / I§ C C( II, 50.00%

                           /            -        --     -    -     -    --     -- -- -- -- -- -- -- -- -- --

8 iit L- -- - _/ it

  ~

40.00% 30.00%

                  ,v 20.00%

b 10.00% I I . 0.00% RC

                        - BD-FW         MS    CH     AFW     HHI CW    SW    RH     CC CS AS  LHI  ECC   RS   ACC  CN EE FC VS SYSTEM
                               -+-% COF RI-ISi + RI-AUG          -"lo CDF S XI+ XI-AUG       _.,_% CDF AUG ONLY Figure 3.10-1         Surry Unit 1 Comparison of CDF Results on a Piping System Level 58

100.00%

                                                          .   -     --      -T   -   -.            .    -- - -.      .. .

90.00%

                            ~

80.00% 70.00% r fil ffl IC Cl 60.00% T I Cl

 ~

SO.CO%

 ..,I f

i: 40.00%

 ".fl.

30.00% 20.00% r-10.00% 0.00% -I. BO RH FW HHI CC AFW MS AS RC CW SW CH CS LHI ECC A ACC CN EE FC RS VS

                            -+-% LEAF RI-ISi + RI-AUG     -%  SYSTEM LEAFS XI + XI-AUG       .......... % LEAF AUG ONLY Figure 3.10-2       Surry Unit 1 Comparison of LERF Results on a Piping System Level 59

1.00E-04 1.00E-05 II. IC 1.00E-06 w ..I u: Q 0 1.00E-07 CJ z a: a: 1.00E-08 CDF No Operator Action CDFOperator Action LEAF No Operator Action LEAF Operator Action IINolSI *section XI l'IAI-ISI Figure .3.10-3 Surry Unit 1 Comparison of CDF/LERF for No ISi, Current Section XI, and RI-ISi Program 60

• Case Table 3.10-1 SURRY UNIT 1 COMPARISON OF CDF/LERF FOR NO ISi, CURRENT SECTION XI AND RISK-INFORMED ISi PROGRAMS Piping CDF/LERF Piping CDF/LERF Piping CDF/LERF Without ISi Current Section XI Risk-Informed CDF No Operator 6.28E-05 6.09E-05 5.34E-05 Action CDF with Operator 4.0SE-06 2.29E-06 1.67E-06 Action LERF No Operator 5.18E-06 5.09E-06 4.63E-06 Action LERF with 4.46E-07 3.63E-07 1.54E-07 Operator Action
• 61
• Table 3.10 -2 Summary of Additional Segments Added For ChanQe in Risk, Defense-In-Depth, and New Information Considerations Change in Risk Consideration Segments: CS-01, CS-02, HHI-OSA, HHl-06A,.

Segment Additions LHl-01, LHl-02, RC-27, RC-28, RC-29, RC-60A Defense-in-Depth Consideration Segments: RC-01, RC-02, RC-03, RC-13, Segment Additions RC-14, RC-15 New Information Addition Segment: MS-10

• 62
• 4. Implementation and Monitoring Program Upon approval of the RI-ISi program, procedures that comply with the guidelines described in WCAP-14572, Revision 1, will be prepared to implement and monitor the program .

~* 63

,. 5. Proposed ISi Program Plan Change A comparison between the RI-ISi program and the current ASME Section XI program requirements for piping is given in Table 5-1. An identification of piping segments that are part of plant augmented programs is also included in Table 5-

1. Additionally the current program and the proposed RI-ISi program are provided in attachments 4 and 5.

Surry will be performing examinations on elements not currently required to be examined by ASME Section XI. Some examples of these additional examinations are provided below.

• Several elements currently classified as Non-Code Class will receive examination. These examinations will be in addition to applicable augmented inspection programs that will be continued. Non-Code Class systems or portions of systems that are identified as having Non-Code Class piping segments requiring examination include auxiliary steam, steam generator blowdown, and feedwater. The ASME Section XI Code does not address Non-Code Class systems.
• Several elements currently classified as Class 3 will receive examination.

Class 3 systems or portions of systems that have Class 3 piping segments requiring examination include auxiliary feedwater and component cooling water. The ASME Section XI Code does not require NOE (volumetric or surface) examinations on Class 3 systems. The ASME Section XI Code does not require volumetric and surface examinations of piping less than 3/8 inch wall thickness on Class 2 piping greater than 4 inch nominal pipe size (NPS). The welds are counted for percentage requirements, but not examined by NOE. The RI-ISi program will require examination of these welds. Examples where the risk informed process required examination and the Code did not are the suction lines to the charging pumps (high head safety injection). The initial program will be started in the inspection period current at the time of program approval. For example the second inspection period of the third inspection interval for Unit 1 ends on October 14, 2000. If the program is approved such that a refueling outage remains in the second period, we will perform 66% of the required remaining examinations by the end of the inspection interval per the risk-informed inspection program .

• • 64

• Table 5-1 SURRY UNIT 1 STRUCTURAL ELEMENT SELECTION RESULTS AND COMPARISON TO ASME SECTION XI 1989 EDITION REQUIREMENTS Number of High RI-ISi Program ASME Section XI ISi Program Total Number of Safety-Significant High Safety-Significant 1989 Edition Examination Segments Segments (No. in Structural Elementsa Category Weld Selections Credited in System Augmented Program) Augmented Programs CLASS 1 CLASS 2 CLASS 3 NON- B-F 8-J C-F-1 C-F-2 CODE ACC 0 9 0 AFVlf 11 (5) 5 3+3e 6 16 AS 2 2 0 BOC 6 (6) 3 3 12 cc 6 13+4e 0 CH 8 12+6b+4e 1+3e 39 3 CNC 0 6 cs 0 2h 9 2 cw 4 0 ECC 7 12 1 4 24 1 EE 0 0 FC 0 0 FVlf 13 (13) 7 6 17 HHIC 14 (1) 15+2h 63 5 LHIC 7 (1) 7+3b+2h 23 1 MSC 3 (3) 2+1 9 18 23 RC 11 20+1 oh*i+3b 18 146 3 65

• Table 5-1 SURRY UNIT 1 STRUCTURAL ELEMENT SELECTION RESULTS AND COMPARISON TO ASME SECTION XI 1989 EDITION REQUIREMENTS Number of High RI-ISi Program ASME Section XI ISi Program Total Number of Safety-Significant High Safety-Significant 1989 Edition Examination Segments Segments (No. in Structural Elementsa Category.Weld Selections Credited in System Augmented Program) Augmented Programs CLASS 1 CLASS 2 CLASS 3 NON- 8-F 8-J C-F-1 C-F-2 CODE RH 4 1 4 4 12 0 RS 2 2 4 0 SW 8 5+3e 0 vs 2 2 0 Total 108 68 53 33 12 18 202 49 116 89 Summary: Current ASME Section XI selects a total of 385 non-destructive exams while the proposed RI-ISi program selects a total of 136 exams (166 - 30 visual exams), which results in a 65% reduction.

Notes for Table 4.4-2

a. System pressure test requirements and VT-2 visual examinations shall continue to be performed in all ASME Code Class 1, 2, and 3 systems.

b. VT-2 area exam at specific location.

c. Augmented programs for erosion-corrosion and/or high energy line break continue.

d. Pipe coatings program will be maintained.

e. VT-2 for entire segment.

f. UT thickness only.

g. Segment MS-34 has no weld; VT-2 for entire segment.

h. Ten examinations added for change in risk considerations.

i. Six examinations added for defense-in-depth at the reactor vessel outlet nozzle to pipe welds.

66

6. 0 References/Documentation These reference or supporting documents are located at either Va. Power or Westinghouse.

WCAP-14572, Revision 1, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping lnservice Inspection Topical report" WCAP-14572, Revision 1, Supplement 1, "Westinghouse Structural Reliability and Risk Assessment (SRRA) Model for Piping Risk-Informed lnservice inspection" Va. Power Cale. # SM-1124, Rev. 0, "Segment Definitions for Surry 1 RI-ISi Program" Cale.# SM-1087, Rev. 1, "Risk-Based lnservice Inspection Pilot Program - Quantification of Risk" Cale. # SM-1088, Rev. 1, "Risk-Based lnservice Inspection - Indirect Effects Analysis" Cale.# SM-1090, Rev. 1, "Risk-Based lnservice Inspection Pilot Program - Quantification of Large Early Release Frequency" ET# MAT-97-0014, Rev. 0, "Estimated Failure Probabilities for Risk-Based ISi Surry Unit 1" Westinghouse Cale. Note# CN-RRA-019/97, Rev. 0, "Surry Risk-based ISi CDF and LERF Calculations" Cale. Note# CN-RRA-024/97, Rev. 0, "MS Access database for the WOG Risk Based In Service Inspection (RB ISi) for Surry Unit 1 piping segments. Some inputs to the database are from preliminary Surry calculations notes. Cale. Note# CN-RRA-025/97, Rev. 0, "Surry Change in Risk Calculations for Risk-based ISi"

• 67
• Cale. Note# CN-RRA-026/97, Rev. 0, "WOG/Surry 1 Risk-Informed ISi Perdue Model Calculations" Cale. Note# CN-STD-97-027-RO, Rev. 0, "Surry ISi @Risk Simulation"
• 68

Attachment 1 Compliance with EPRI PSA Application Guide

• TECHNICAL REPORT NE- 1105 - Rev. 0 CHECKLIST FOR TECHNICAL CONSISTENCY OF THE SURRY PSA MODEL NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING SERVICES VIRGINIA POWER December 1996 Prepared by Reviewed by _0.-.....'-L./}1__..;...;,;....i~~~""'-"'--- Date t//o (9 2 D. M. Bucheit Approved by~~O- L k. L. Basehore Date , f,,. (l:f1 QA Category: Safety Related
  • Key Words: lnservice, Inspection, PSA
• TABLE OF CONTENTS 1.0 INTRODUCfION * . . * . . . * . . . . . * . . . . * . . . . * . . . * . . . . . . . . Page 1 2.0 CHECKLIST FOR TECHNICAL CONSISTENCY OF THE SURRY PSA MODa . . . * . * . . . . . * . . . . . . . . . . . . . . . . * * . . . . . . . . . . . . Page 2

3.0 CONCLUSION

  . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Page 23

4.0 REFERENCES

  . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Page 24

1.0 INTRODUCTION

This report provides a review of the Surry Probabilistic Safety Assessment (PSA) model [1] adequacy for the application in the Surry Risk-Based Inservice Inspection (RBISI) program. The review was performed based on the Westinghouse Topical Report [2] and EPRI PSA Applications Guide [3]. It was determined that the Surry PSA model [l] accurately reflects the current plant configuration and operational practices. Furthermore, a sanity check, based on the Appendix B of the PSA Applications Guide [3], was performed to confirm that the Surry PSA conforms to the industry state-of-the-art with respect to completeness of coverage of potential scenarios. Section 2.0 provides a checklist for technical consistency in the Surry PSA model .

• Page 1

.* 2.0 CHECKLIST FOR TECHNICAL CONSISTENCY OF THE SURRY PSA MODEL Appendix B of the PSA Applications Guide presents a list of issues that the document contends are significant in determining the risk profile [3]. The issues are classified as being concerned with whether parameter values are within nominal ranges, whether assumptions are justifiable, and whether there is documentation to support modeling decisions. The intent is that a utility may use the checklist to confirm that its PSA model conforms to the industry state-of-the-art, with respect to completeness of coverage of potential scenarios. Table 2-1 presents the result of comparing the Surry PSA model against this checklist.

• Page2

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Gunde] Initiating Event 1. Partial Loss or Total Loss of Support Systems (e.g. Service A list of all systems in Surry is presented in Table Water, AC Power). If these systems have not been identified as 3.1.1-10 of (1). Each support system was being risk significant, they should have been screened out based on evaluated using the following criteria: one of the following reasons:

i. Does its failure cause a reactor trip,

i. Not causing a reactor trip AND OR ii. Does its failure result in failure of any train of ii. Not required for Shutdown any front line system.

OR iii. Low frequency of occurrence If the third criteria is used and the freq. of occurrence is less than l.OE-2/yr for a single train system or 1.0E-4/yr for a redundant system, a critical review is required. However, if the event is bounded in frequency and consequence by another initiator, it could be screened out. For each of the systems which met one of the above criteria, a failure mode and effects analysis was perfonned. Failure of the following support systems were considered as contributors to ono of the initiating events ([l), Table 3.1.1-13):

1. DC Bus IA Page 3

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide]

2. DC Bus lB

3. Outside Instrument Air

4. Component Cooling Water System Initiating Event s. Bearing Cooling Water System

6. HV AC for Emergency Switchgear Room

7. Both Trains of SW Cooling to HPI

8. Service Water Canal

9. 120 VAC VB I

10. 120 VAC VB II

11. 120 VAC VB III

12. 120 VAC VB IV Failure of the following systems were not considered as initiators on the basis that they will not cause a direct or indirect plant trip, even though they may result in the loss of a front line system (i.e. meet the second screening criteria of (1)):

1. 480 VAC Bus lH

2. 480 VAC Bus lHl-1

3. 4160 VAC Bus IH

4. 4160 VAC BUS 1J Page4

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] S. 480 VAC Bus Ul Initiating Event 6. 480 VAC Bus Ul-1

7. Containment Instrument Air

                                                                                           , 8. One Train of SW Cooling to HPI

9. One Train of Closed Cooling System to HPI *

10. Both Train of Closed Cooling System to HPI

2. Interfacing System LOCA In the Surry PSA, Interfacing System LOCAs were assumed to lead directly to core melt. All potential These LOCAs might have been considered low risk significant contributors to this initiating event were identified based on the low frequency of occurrence. If so, the bases for [4]. The initiating event frequency of IS LOCA assigning/calculating the low frequency should be identified in the has been calculated as 1.60E-6 [SJ.

PSA documentation.

3. Steam Generator Tube Rupture In the Surry PSA, Steam Generator Tube Rupture is considered as an initiating event [1] with the Steam generator tube rupture events are risk significant and there calculated contribution of 1.04E-S per year to core should be an analysis of their impact. damage frequency. The supporting analyses are documented in (4), [SJ, and [6].

Page 5

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Event S!,guence Transient Induced LOCAs, such as stuck open safety or relief In the Surry PSA, consequential LOCAs (transient-Development valves, are potentially important contributors to core damage induced LOCAs) are considered in detail (1) which frequency. These should be adequately addressed in the PSA event include the following events: sequence development.

a. Stuck open pressurizer PORV or SRV

b. RCP seal failure following loss of seal injection and barrier cooling

c. SGTR following steam leak inside containment

d. Pipe failure following an ATWS over-pressure event. Vessel/Pipe fa~lure following pressurizer thennal shock

e. Stuck open SG PORV or SRV after SG rupture Page 6

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Event Sequence When manual actions are credited, the time available to complete In the Surry PSA, the time dependency of crew Development the actions may be short compared with the time required to actions, which stems from tho constraints imposed complete the actions. The impact of these timing issues should on the operators by tho plant hardware and have been addressed in the PSA model. thennal-hydraulic characteristics, is considered. The approach used was the EPRI-stylo event tree with the P 1, P2, and P3* Tho P2-panuneter represents the time dependent probability of non-res~nse given the operators are on the correct

                                                                                        *cognitive path".

Where data was available from simulator exercises, the human cognitive reliability (HCR)/operator reliability experiments (ORE) calculation approach described in EPRI NP-6560-L was used as a basis for the quantification of the P2-parameter. Tho approach adopted for the estimation of the remaining parameters is described in Appendix D of [I]. Event Sequence The PSA event sequence model should consider the impact of all In the development of each sequence model, all Development relevant EOPs and each EOP in its entirety. relevant EOPs were taken into consideration, each in its entirety. Where appropriate, the HEP associated with specific step in the procedure was incorporated directly in the model. Ono of tho factors considered in the development of some sequence models was information collected on operator responses to simulated accidents at the Surry Training Simulator. The training exercises were part of the normal Licensed Operator Requalification Program but modified somewhat to meet the data needs of the IPE. Page 7

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide) Surry Unit 1 PSA Model [PSA Application Guide] System Analysis Addressing the impact of room cooling on equipment operability. In the Surry PSA, impact of room cooling on the As a minimum, the impact of room cooling on the Control Room operability of PSA-credited equipment was and Switchgear or Relay Rooms should be addressed in the PSA considered in the dependency matrices. For documentation. example, room beat-up calculations show that Switchgear Room cooling was required to maintain the plant in an operable state. Thus, it was concluded that failure of this function would eventually lead to an initiating event. Therefore, this was treated as a separate initiator. System Analysis Addressing equipment operability under harsh environmental There is evidence that the impact of such adverse

• conditions during some sequences such as conditions inside the conditions was considered in the Surry PSA. In the containment after a LOCA. There should be some evidence that a system modeling task plan, stage Sb, it is stated search has been made for equipment that is not qualified. that "Environmental .conditions which occur in determined sequences will also be analyzed, to take their effect into consideration." [7]. For example, steam line breaks inside the Main Steam Valve House (MSVH), where amongst other components, all three AFW pumps are housed, was treated separately. The concern was the adverse environmental condition caused by a rupture of a main steam line component could fail all three AFW pumps. In modeling the operation of the various systems following the initiating event "Main Steam Line break outside Containment" each impacted system model includes a term to take account of the probability that the break occurs in the MSVH leading to the failure of the equipment housed in the room.

Page 8

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide]* *

• Surry Unit 1 PSA Model

[PSA Application Guide] System Analysis Addressing the role played by Batteries for providing a buffer to In Surry, the 125 VDC buses arc powered from tho allow time for recovery or repair of the initial fault to the 480 VAC buses (via inverters) and in tho event of preferred DC power supply (battery chargers). This issue is of loss of the AC power source (i.e. loss of offsito concern for plants that have no "backup" to the preferred DC power and loss of diesel generators) they are supply. powered from DC batteries. The AC power is supplied via two independent inverters (battery chargers), each capable of supplying tho required load (i.e. one inverter can be considered as the "backup" to the other). If both inverters fail, i.e. if the only source of power to a 125 V DC bus is batteries, in the Surry PSA model, the DC bus is, conservatively, modeled to fail. Additionally, no recovery of the inverters is included in the PSA model. Page 9

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] ' Surry Unit 1 PSA Model [PSA Application Guide] System Analysis Modeling of the passive components. In some PSAs, failure of In the Surry PSA model, failure of passive passive components, which can cause failure o( multiple components (such as tanks and strainers) were only train~/channels, are assessed to be important and, therefore, are modeled if failure resulted in loss of multiple trains included in the PSA models. In such cases, there is a concern that and/or systems. A review of the import1mce list modeling failures of passive components may obscure other more for the model indicates that the Risk Reduction important contributions. If failures of passive components (e.g. Worth (RRW) value for most of these components, tanks) are important in the results of the PSA, the reason for their with exception of two components, ranges from inclusion should be identified and reviewed. 1.001 to 1.0. This implies that even if these components were assumed to be highly reliable and had not been included in the model, the plant's risk profile would not have changed (i.e. they do not mask more important contributors). The two exceptions are plugging of the normally open, required to remain open, isolation valves on the line from the RWST to the safety injection systems (1-CS-25 and 1-SI-24) with the RRW values of 1.016 and 1.025, respectively. Failure of these valves would isolate the Unit 1 RWST water supply to the safety injection systems (i.e. they are important). The failure probabilities for these components, 4.499E-S and S.472E-4 respectively, were calculated using generic data, taking their inspection frequency into the consideration. Since these components are important and their failure probability is realistic, it is concluded that by including these components in the model, they do not mask other, more important, contributors. Page 10

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] **

• Surry Unit 1 PSA Model

[PSA Application Guide] Parameter Estimation Parameter values used for the unscheduled maintenance. The In the Surry PSA model, the following mean application guide's recommended ranges for unscheduled unavailability values .due to unscheduled maintenance unavailabilities are: maintenance are used: Turbine Driven Pump Train = 0.01--0.05 Turbine Driven Pump = 0.018S (fable C.S-7 of Motor Driven Pump Train = 0.001--0.01 [l]) Valves (MOVs) = .0001-0.00S Motor Driven Pump = 0.0026S (Table C.S-7 of Diesel generators = O.OOS-0.0S [l]) Buses = 0.0001-0.001 Valves (MOVs) = 0.0002 (Table C.S-2 of [1]) Diesel generators = 0.0111 (Table C.S-7 of [l]) Values outside these ranges should be noted and identified. Buses = 0.00000727 (fable C.S-7 of [l]) All values, other than the unscheduled maintenance unavailability of buses, are within the PSA recommended range. However, in the Surry PSA, the unavailability of buses was calculated based on plant specific data and it is judged to be a realistic reflection of the unavailability because the component boundary is the actual bus bar which is never in maintenance while the Units are at power. Page 11

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Parameter Estimation Consistency between the component boundaries in the fault trees In the Surry PSA, fault trees were developed using and the parameter data base. the guidance provided in the system modeling task plan [7]. In the task plan, component boundaries for all major components (such as pumps) were clearly defined. Data analysts used/supplemented these definition to ensure consistency between tho fa ult trees and parameter data base. It is noteworthy that control faults and breaker faults are included within the component boundaries for pumps, valves (MOVs), and similar active components. This component boundary was considered during plant data reduction. Page 12

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Parameter Estimation Realistic reflection of plant experience in the component failure In the Surry PSA, generic data was used for nearly rates. Plant specific data should be gathered and reviewed for every component fault as either basic event, or the dominant risk contributors whenever possible. Use of Bayesian prior distribution for Bayesian updating. Generic

• methods can enhance data under some conditions. data were applied in a conservative manner. Plant*

specific data reduction was performed for components which were chosen because they are generally key contributors to the PRA results. Plant specific data was obtained to enable estimates to be made of:

i. initiating event frequency for the more common transients, ii. failures to start of Engineering Safeguards standby or alternating pumps, and diesels, iii. unavailabilities due to maintenance for the trains of important standby systems,

                                                                                                                                                 .-* 1..-'

iv. failures to change state for MOVs

v. other faults for components unique to the Surry configuration.

Bayesian ~pdating of generic data was provided considering the following criteria: (1) relative risk importance of the basic event, (2) appropriateness of the subjective generic data prior, (3) availability of plant data, and (4) statistical significance of plant data ([l), Appendix C). Page 13 \

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Dependent Failures CCF analysis coverage. As a minimum, CCF analysis should In Surry PSA, the following common cause failure include: component groups were identified: o redundant standby pumps o standby pumps- fail to start and run o redundant MOVs/AOVs o standby and alternating pumps- fail lo start and o redundant breakers, diesel generators run after LOOP o redundant check valves, and o MOVs- Fail to open/close o any other components that change state o Check valves- fail lo open/close o Diesel generators- fail to start and run o Batteries- fail to supply power and o additional groups in Service Waler System identified through plant data review. Breakers are not included in the CCF groups. Since breaker faults are included within the component boundaries for pumps, valves (MOVs), and similar active components, their contribution is added into the CCF group of the component they are mapped into. An exception to this rule is that the EOG breakers which are not included within the boundaries of the EDGs. However, their failure rate are bounded by the CCF of the EDGs (i.e. the CCF probability of EDGs is much higher than the CCF probability of EOG-related breakers). Page 14

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guidie] Dependent Failures Low CCF probabilities compared with the failure rate of individual Comparing the CCF probabilities and single components. It is difficult to justify estimates of CCF probabilities component failure probabilities provided in that are more than two order of magnitude lower than the single Appendix C, Table C.8-1, in the Surry PSA component failure probability. Therefore, any PSA that has a model, the CCF probabilities are not less than CCF probability which is less than one hundredth of the single 11100th of the single component failure probability component failure probability is somewhat out of line with except for the CCF probability of 3/3 DGs (CCF expected results. The justification for this should be reviewed very probability of 7 .49E-S vs single failure probability carefully to determine if there are, indeed, unique plant specific of 1.0lE-2 (summation of failure to run and failure features that lead to this result. to start)). Based on a review of [8], the approach used in Surry PSA for. the analysis of DGs CCF probability is consistent with the detailed analysis. of NUREG/CR-4780 [9] and the assumptions and analysis were independently reviewed and were found to be sound. Thus, it is concluded that the CCF probability values used in the Surry PSA model are realistic and defendable. Human Reliability If pre-initiating event human errors are screened out, the basis for For the Surry PSA, the HRA task addressed pre-Analysis that decision should be documented. accident (pre-initiating event) human errors (i.e. human errors during testing, calibration, and maintenance). The specific operator actions that were addressed are summarized in Table 3.3.3-i"of [I]. Page 15

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide) Surry Unit 1 PSA Model [PSA Application Guide] Human Reliabilitl'. Validity of the HEP values for post-initiating event actions. Post- In the Surry PSA, several post-initiating event Analxsis initiating event human errors should be plant and scenario specific. operator actions were analyzed (See Table 3.3.3-2 Any HEP value that lies outside the following recommended of [1]).* In deriving HEPs for these actions, data ranges for these more risk significant functional failures should be from simulator exercise were used together with a reviewed carefully: modified ORE/HCR~orrelation in some instances.

                                                                                   ...      In other instances, the NUREG-1150 values were Failure  to initiate primary feed and bleed cooling l.OE-1 to l.OE-3 used [11]. The Surry PSA model HEP values for Failure  to isolate ruptured steam generator 1.0E-1 to 1.0E-3        the PSA Application Guide listed functional failures Failure  to initiate depressurization and cooldown l.OE-3 to l.OE-5  are:

Failure to switchover to the recirculation l.OE-1 to l.OE-3 Failure to initiate primary feed and bleed cooling HEP =2.664E-3 Failure to isolate ruptured steam generator HEP = l.545E-3 Failure to initiate depressurization and cooldown HEP = 5.326E-2 Failure to switchover lo the recirculation HEP = 5.820E-2 The only HEP which does not fall within the application guides range is the HEP value for "failure to initiate depressurization and cooldown. * (Surry's value is slightly higher) Based on a review of the HEP calculation notes, this HEP value is calculated by adequately considering all the applicable factors and correct application of the methodology (Appendix D of [l]). Page 16

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Human Reliabilit::i: Failing to address dependencies between the individual HEPs that In the Surry PSA, two types of dependencies were Anal::i:sis may occur in the same sequence. addressed for the post-accident human interactions (His). The first is related to the effect of the time available for performing an HI. The second is the question of cognitive dependency between sequential, or parallel, His. The process used for addressing this issue included a review of each sequence to identify operator actions credited in the sequence and dependency between the identified operator actions, if any. Upon identification of any, dependency, the HEP value was adjust to reelect the dependency. Note that where the results of simulator experiments were used for the HRA, many of these problems were eliminated because, the time windows calculated and actions evaluated based on the simulator results implicitly include the dependency between dependent operator actions. Page 17

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Use of multiple recovery terms in a single cutset. Use of multiple In the Surry PSA, dependencies between groups of recovery terms in a single cutset is not recommended practice and operator actions or operator actions and specific may unrealistically drive down core damage frequency. component failures have been taken into account [l]. This was done by evaluating each action in terms of how the action would be performed for various combinations of prior system failures, bow long the operator has to perform the action, what cues he has to perform the action, and how it relates to the procedures. Additional checks performed to ensure the believability of the credited operator actions includes the evaluation described in response to the previous issue. . . ..

• Additionally, all sequences that were below lE-7 because of inclusion of operator action were reviewed to ensure that no sequences are artificially eliminated due to low HEPs. All the actions in the sequences which fell into this category were found to be based on procedures and therefore would be performed in the normal course of events ([l],

page 3-126). Thus, even when multiple recovery actions have been used in the same cutset, the cutset's contribution to core damage frequency has not been artificially lowered and the result is considered to be a realistic representation of the event under consideration. Page 18

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Quantification Correct assignment for mission times. System mission times The system analysis for the Surry IPE was should be consistent with the accident scenario. conducted in accordance with Task Plan SM of the IPE project. The task plan provides specific guidance for all facets of the fault tree development. Based on the guidance provided in the task plan, one of the earliest stages of the system model development includes identification of system limitations (7) (e.g. quantity of water . available, expected operability time, etc.) and these limitations are taken into account during modeling (mostly in the definition of mission time and as a part of specifying system success criteria). For example, mission time for Batteries was assigned as 4 hours. Thus, it is concluded that this issue is correctly addressed in the Surry PSA model. Appropriateness of the truncation. limit. This is of particular In the Surry PSA, the fault tree linking approach concern for those fault tree linking approaches that are based on consisted of constructing and solving an event tree ANDing the solutions of fault trees, as opposed to constructing and created by ANDing the contributing system fault solving a large fault tree created by ANDing the contributing trees. In general, a truncation value of l.OE-9 was system fault trees. However, with any approach there has to be used for the fault tree solutions and l.OE-10 was some evidence of coverage towards a stable result. used for the sequence solutions [10]. Since the total CDF is 9.3E-S, the truncation value is about lE-6 below the total CDF. This approach is judged to lead to minimal loss of information. Page 19 ~---------------~-----

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Quantification of Plant In the fault tree linking approach, the use of the deleted term This is issue has been adequately addressed in the Damage States approach to account for the successes in event sequence is Surry PSA. In the Surry model, each core damage necessary to assure that the correct cutsets are generated. sequence was quantified in three stages. In the first stage all combinations of failures and initiating events were combined to give a set of combinations of failures which will lead to core 4Bmage. In the second stage the combinations of failures were compared with the successful functions and all the non-allowed failures removed. In the third stage

• the remaining combinations were compared with disallowed combinations of failures, e.g. Trains A and B in planned maintenance, and these combinations of failures were removed. These stages are completed automatically by the NUPRA software.

Analysis of Results Truncation has an impact on the importance evaluation in that In the Surry PSA, a truncation value of l .OE-9 was events with high risk achievement worth may be deleted. The used for the fault tree solutions and 1.0E-10 was

                       .recommended truncation limit is lE-4 below the baseline PSA core  used for the sequence solutions ([10), and page 3-damage frequency.                                                 113 of [l]). Since the total CDF is 9.3E-S [1], the truncation values are about lE-S and lE-6 below the total base line CD F. This approach is judged to lead to minimal loss of information.

The impact of potentially important assumptions can and should be In the Surry model, the impact of potentially evaluated by sensitivity studies. important assumptions were evaluated by (" performing sensitivity calculations. Sections 3.4.1.6 and 4.8 of [l) provide a summary of these calculations. Page 20

Table 2-1: Surry PSA Model vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] ATWS PWR: Conservative success criteria with respect to pressure based WCAP-11993 which was the most recent analysis on moderator temperature coefficient can make ATWS more that took into account the full range of core loading important than it should be. If RRW of 1.005 or F-V of 0.005, schemes in Westinghouse plants was used for Surry respectively, is used as a measure of risk significance, it could lead PSA. Additionally, the other events which impact to some additional SSCs being identified as risk contributors the success criteria, namely, the power level at which the ATWS occurs, the inclusion of the ATWS Mitigating Systems Actuation Circuitry and the Main Feedwater availability were also considered in drawing up the success criteria ([1], page 3-28). Thus, it is concluded that ATW~ success criteria are realistic (i.e. not over conservative). Loss of Offsite Power and PWR: An issue with major impact on the development of accident In the Surry PSA, RCP seal LOCA is explicitly Station Blackout sequences is the choice of RCP seal LOCA model. The model modeled and evaluated. Seal LOCAs were found assumptions should be clearly stated, an~ if it is not a contributor, to contribute to core damage as initiating events . the reasons why should be determined. and as consequential failures following a station blackout. Page 21

Table 2-1: Surry PSA Mod~ vs PSA Application Guide Checklist Category Issue Description [PSA Application Guide] Surry Unit 1 PSA Model [PSA Application Guide] Loss of Offsite Power and PWR and BWR: The major issues are those associated with the In the Surry PSA, the time to recover AC power is Station Blackout time available for recovering AC power, which is determined by dependent upon a number of factors and plant battery life, room heat-up considerations, RCP seal failure, and conditions: inventory of the CST. These issues should be addressed in the PSA documentation, and the way they are addressed in the model 1. Whether a seal LOCA occurs as the result of should be identified. failures of seal injection and thermal barrier cooling.

2. The length of time the battery will support the Turbine-Driven AFW (TDAFW) pump and 120 V AC for instrumentation, and the possibility of operating the TDAFW with no level indication.

3. Whether room cooling is required to prevent failures of the TDAFW puoip.

4. The loss of water from the intake canal, such that when power is restored, Service Water will not provide cooling to CCW and other systems

5. Whether or not there is a stuck open PORV

6. Depletion of CST Each of these factors was evaluated in detail. A discussion of the timing of the events is given in Appendix B.

Page 22

3.0 CONCLUSION

As noted in Section 1.0, the Surry PSA model (the IPE model and, where applicable, its updates) was reviewed based on References 2 and 3. Table 2-1 was developed in accordance with Appendix B of the PSA Applications Guide [3] and it shows that the Surry PSA conforms to the industry state-of-the-art PSA technology with respect to completeness of coverage of potential scenarios. The model adequately reflects the plant configuration and operational practices. Therefore, it is concluded that the model is technically sound and adequate for the Surry risk-based ISi project. This conclusion is applicable to the Surry IPE model and its updates which are documented in references 10 and 11. It is judged that the above conclusion is also applicable to the North Anna PSA model based on the following:

1. The general methodology used, and the guidelines followed, for the development of the Surry and North Anna models are identical. Thus, the potential for the development of a systematic root cause resulting in a significant divergence between the Surry and North Anna model is minimal.

ii. The Surry and North Anna IPE models were mostly developed by the same analysts. This has minimized the potential for a significant divergence between the models due to the analysts' interpretation of the general methodology. Also, there is a close collaboration between the analysts that perform the updating tasks. iii Familiarity of the author of this report with the development of the Surry and North Anna models .

• Page 23

• • 4.0

[l] REFERENCES Surry Power Station Units 1 and 2 Individual Plant Examination, August 1991. [2] Westinghouse Energy Systems, "Westinghouse Owners Group Application of Risk-Based Methods to Piping Inservice Inspection Topical Report," WCAP-14572, Revision 0, March 1996. [3] Electric Power Research Institute (EPRI), "PSA Applications Guide," EPRI TR-105396, August 1995. [4] Analysis File 322MAF.1, Surry Individual Examination, "Initiating Event/Success Criteria," Virginia Power, NP-1498, June 1989. [5] Analysis File 319MAF.2, Surry Individual Examination, "Plant Specific Data," Virginia Power, NP-1498, NUS Project 081, September 1991. [6] Analysis File 32 lMAF.1, Surry Individual Examination, "Accident Sequence Development," Virginia Power, NP-1498, NUS Project 081, August 1991.

• [7]

[8] Task 320, Surry Individual Examination, "System Modeling Task Plan," Virginia Power, NP-1498, NUS Project 081, August 1989. Analysis File 323MAF.1, Surry Individual Examination, "Common Cause Failure Analysis," Virginia Power, NP-1498, NUS Project 081, August 1991. [9] NUREG/CR-4780, "Procedures for Treating Common Cause Failures in Safety and Reliability Studies," Nuclear Regulatory Commission, January 1989. [10] Analysis File 5T45.SI01, Surry Power Station Individual Examination for External Events, "Surry IPE PRA Model Upgrade," Virginia Power NP-2770, August 1993. [11] Anaysis File SM-1084, Surry Power Station Risk-Based Inservie Inspection Pilot Program, "Surry Plant Damage State Event Trees Update Project," Virginia Power Project 90R90NS009, October 1996.

• Page 24

Attachment 2 Segment Drawings l

TO NITROGEN SLl'PLY STATION Fi I n

                                 'f
                                 ~

,, i (ACC-09) TD REGENERATIVE HEAT EXCHANGER TD PRESSURIZER RELIEF TANK

                 ~~-                                                                 ~RV-NOTES*
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1-Sl-136 ( _..,_ 1-Sl-9'

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RBI LEGEND:

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RBI LEGEND, AFW-01 - - * -- *-- * - AFW-02 - * - * - * - *- * - * - AFW-03 - - - - - - - - - AFW-04 - " - "- " " " - " " " " " _ ,, _,, _,,_ DWG 1-AFW-018 DWG 1-AFW-018 DWG. 1-AFW-018 AFW-05 t 1111111111111111111111111 I AFW-06 _,,_,,_,,_,,_,,_ SEGMENT AFW-07 SEGMENT AFW-08 SEGMENT AFW-09 AFW * * - " - " _ " _ , __ 1 J_. _1-FW-142 1 l -_1-FW-157 DETAIL 'At 1 ~l-FW-172 DWG. 1-AFW-018 : 12 i" .... **, I AFW-23 * - - - - *- - *- ** *- - - *- - AFW AFW-25 AFW-26 AFW-27 111111uu111111111111rn1111u1111uttm11111111m1

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                                                                                                                                                                           **- - ** *{><]- - -

(AFW-23) (AFW-24) G- ..J I OTHER\JISE NOTED.

2. THIS DIAGRAM IS FOR UN IT J, SEAL './ATER UNIT 2 SIMILAR UNLESS TO S/G P-4B OTHER\JISE NOTED SEAL './ATER Ar'w BOOSTER TO SIG VACUUM PUMP VACUUM PUMP (UNIT !) PUMP 3. REFERENCE ll448-FM-068A, SH 3 & 4 (UNIT 2)

AUXILIARY F"EED\JATER SYSTEM D\JG 1-AF"\J-OlA

REACTOR CONTA INMENT I MSVH

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I I I UNIT 2 ,J-DWG. 1- AFW -OlA AUX FEED\JATER DWG. 1- AFW - 0 1A DWG. 1-AFW- 01 A DWG. 1-AFW-01 A SEGMEN T AFW- 12 SEGMENT AFW - 04 SEGMEN T AFW - 05 SEGMENT AFW-06 SYSTEM CONTINU ED RBI LEGEND : NOTES: AFW - 07 1. ALL MARK NOS. PRECEDED AFW-08 AFW-09

                                                                                                                                                                                                             \./ITH 1- F\J- UNLESS AFW- 10                                                                    OTHER\JISE NOTED.

AFW-11 AFW - 12 2. THIS DIAGRAM IS FDR UNIT 1, AFW- 13 UNIT 2 SIMILAR UNLESS AFW-14 AFW-28 OTHER\JISE NOTED

3. REFERENCE 11448-FM-068A, SH 1 & 3 11548- FM - 068A, SH 3 AUXILIARY FEED\JATER SYSTEM D\JG 1-AF\J-OlB

e TORC - E-I C ~

<SG JC) 1-Fl,l-72                                                                                                                                                      NOTES:

(AFl,l-22)

1. ALL MARK NOS . PRECEDED

                                                                                                                                                                                                       \JITH 1- F\J - UNLESS TORC -E - I B ~                                                                                                                                                         DTHER\JISE NOTED.

(SG lB)

                                                        ,                     J-Fl,l- 41                                                                                                          2, THIS DIAGRAM IS FDR UNIT l, (AFl,l-21)                                                                                                                                    UNIT 2 SIMILAR UNLESS DTHER\JISE NOTED TD RC - E-IA      ~i---.(
                                                                           <SG IA)          J -      !             ,_~,,~

J-F\,1- 10

                                                                                                                                  )                                                            3. REFERENCE 11448-FM- 068A , SH 18. 3 RBI LEGEND :

CAVITATING AFW - 15 VENTURI <TYP) AFW - 16 FE-101C FE-101B FE - 101A AFW-17

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(AFl,l-22) (AFl,l-19) (AFl,l-21) (AFl,l-18)

                                       ~ 1- Fl,l - 89                              ct I        (AFl,l - 20)

J-Fl,l- 58 2 I - Fl,l-27 AFW - 20 AFW - 21 AFW - 22 AFW - 28

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                                                                                                 ~           ISOLATION
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l ---f--- I L.. _. -~(80=01 G? __ P!'ii'----~-L I TV-100A (BD-02/y ~ TV- 100B DWG 1 018 SEGMENT 80- 03 I y t

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TV-100F DWG 1-BD-01 B SEGMENT 80-09 NOTES : RBI LEGEND:

1. ALL MARK NO 'S PRECEDED BY 1-BD.

UNLESS OTHERWISE SPECIFIED. BD-01 -- -- -- -- -- -- - BD-02A - - - - - - - - - - - -

2. SYSTEM SHOWN IS FOR UNIT 1, BD-028 - - - - - - - - - -- - - - -

UNIT 2 SYSTEM IS SIMILAR. I BD-04 - - - * - - - *- - * -

3. REFERENCE 11448-FM- 124A, SH 1,2&3 B0-05A BD-058 -**-**-**-**-

BD-07 n.______.n BD-08A 1 1111111 111111111111,11,11111111111,1,1,1 BD-088 - *-

• _ ,, _ *- *- * - - -

CONTAINMENT SUMP STEAM GENERATOR BLOWDOWN COOLING SUBSYSTEM SLOWDOWN DWG. 1-80-01 A

e e r-v,., TO CONDENSATE 1 I CN SYSTEM TO SAMPLE SYSTEM _,,,.-SLOWDOWN

                                                                                                                /        COOLER l'-v,1                           E- 1A 155   I FROM CONDENSATE
                                                                                                                                  ' - i -S~S TEM
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L - - ~ E-2A G) AUXILIARY BUILDIN TURBINE BUILDING TO SAMPLE FROM RECIRCULATION & TRANSFER SUBSYSTEM SYSTEM (TYPICAL FOR 3 CONNECTIONS) FOR CON TINUATION SEE FlG J.1-10 \ DWG. 1-BD - 01A SEGMEN T BD-028

                    ~

TV-lOOB

                                        = O~ -       J_--             0
                                                                   .,.. _ _J r- -

I r t E- 28 DWG. 1- BD- 01 A ,_____Jgo:_o~ - t_ - - - -~ - - J I r,.v,1 1 8D 1 SEGMENT BD-058 I TO CONDENSATE!CN ! TV- 100D L _ S:!_ST~ M__ v_:--i _

                                                                                                                                   -   ~ BALANCE OF SLOWDOWN SYSTEM DWG. 1- BD - 01 A SEGMEN T BD-088      .,_________~~----l TV- lOOF
                                                          ---- +- -,

I TO SAMPLE SYSTEM TO ~~~f~SATE~N 1

                                                                                                                          !so!
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                                                                                                                                  ~ SEE SEGMENT DISCRIPTION I

NOTES: I I E- 1(~-,J '>sicN? I ,_ _ _ __ L_ __, -F;OM CONDENSA TE

1. ALL MARK NO'S PRECEDED BY 1- BD. I UNLESS OTHERWISE SPECIFIED. SYS TEM I

2. SYSTEM SHOWN IS FOR UNIT 1, L------

UNIT 2 SYSTEM IS SIMILAR.

3. REFERENCE 11448-FM-124A, SH 1,2,3 & 4 RBI LEGEND : r- (:,

BD-03 1BD 1 BD - 06 I BD - 09  : TO CONDENSATE!cN  ! L - -SYSTEM v~--i

                                                                                                           - - - - - - - - - ~ BALANCE OF SLOWDOWN SYSTEM STEAM GENERATOR BLOWDOWN COOLJNG SUBSYSTEM                                                            ~              11448-FM-1 24A, SH 4 SEE SEGMENT DISCRIPTION       SLOWDOWN DWG. - BD- 018

e e RV-12~ Tc cc - 10)

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SYSTEM HCV-100 I I I

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                                                                    'c~OLMPLO-N-EN~T-CO-O ~L-IN-G                 r*----~.                         i :   I SURGE TANK                             I                         ~

TK-1 (CC-1A) * -C><J-

• J b b

                                                          ~~

3:t:c1 (cc-le) . RV-137 " ~ FROM CONDENSATEs--cxi- - SYSTEM (cc - 1c) 1-CN-800 ( CC-1 C )i - f (cc-1c)

                                               .L , - , - ~
                                            !-CC- 893 (CC- JA) l -CC-54 7 I

I (CC-1A) j..._ , _ ~ I  !-CC-S 4B TO CHILLED CC PUMPS I I I I ~ ( c c - 3 g - - s ) Dl,/G 1- CC-OlB I TO CHEMICAL I- - - - - -f'o.J- _ ) SEGMENT CC-07 I ADDITION TANK I 1-cc-554 FROM UNIT 2 SAMPLE COOLERS ~ P-lA

                                        ,,       r                                   I
                                                                                                                                               ~

I\ 11 1 (cc -1 A) 1 I ,~ - 'c ~c-z~) { ( CC-4~) Dl,/G 1-CC-018 I - - - - ...,-o..j-- * ) SEGMENT CC-07 L- -{><}- - -- 1 r --- r - - - _ ,_ -- ----- - (CC-19) I

                                                                                                                                        ~

1-CC-560 P-lB (CC-1 A) I I L- -{X}--' I ~ T COMPONENT COOUNG PUMPS RBI LEGEND: r _ .. _ .. _ *,- *- ' - * (CC-1A) I

                                                                        '-{><)--J I       -*- - -n-- - -                             -I     ~             ( c c - s ) ~ Dl,/G 1-CC-OLB
                                                                                                                                             - - - - ...,-o.J- -   -   - )        SEGMENT    CC-08 CC-1A CC- 18 CC-1C CC-2 I                                                               1-CC-566 CC-3 I                                                                                                            CC-4 P-ID                        CC-5
       ;- ----,                                              ~                               -     -     -    - * -     -     -~ C-~ 7) - ,    ~

L ____ -f'o...J (cc- 6 ) e - - s Ill,/G 1-CC-OlB

                                                                                                                                                                         )

CC-6 CC-19

~ I SEGMENT CC-08 CC-23 I I I I 1-CC-575 CC-56 I

I 4><J-i I I P-IC CC-57 I I ( CC - 2) I NOTES,

     ,-./'

I J-- 6 I. ALL MARK NOS. PRECEDED 1,/lTH 1- CC- UNLESS OTHER \IISE NOTED. DWG. 1-CC-028 I DWG 1-CC-028 I DWG 1{ c -03A 2, THIS DRAl,/[NG SHOl,/S EQUIPMENT SEGMENT CC - 23 I SEGMENT CC-19 I SEGMENT CC-57 CONTINUED J-.. CONTINU ED

• CONTINUED 6 COMMON TD BOTH UN!TS, UNLESS OTHER\IISE NOTED.

OWG 1-CC- 02A I 3. REFERENCE 11448-FM- 072D, SH 1 SEGMENT CC-56 CONTINUED l.. . -r- * - *- *- "- - ** . .,-o.. J,-c~c_:s_ 1~ 11448-FM-072C, SH 2 11548-FM-072A, SH 1 2-CC-100 2-CC-TV-2096 L

                                                                - - - -' -s (CC- 57 )                          TO UNIT 2 SUPPLY RETURN                                                                  COMPONENT CODLING SYSTEM               D\./G. 1-CC - OlA

e e I TO CHEMICAL ADDITION TANK

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lO S/ti !l..!NlltNN 1 ~ ~ = ~ DVG 1-CC-GlA SEmOT 1-CC-3

                              ~ ~ - * -fa.J- -                                         r----         E-l A   Ill  11   H1    1 ~   11111 I 1:1 I! I
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                                                                                                                                                               -- ~ ----~

_/.(]'\_ - - - - . ::.!. DIIG l-CC-02B 1 SEGMENT CC - 16A CONTINUED 1 FlDI

                                                                                                                                                            =                                                     DIIG l-CC-02B

__i.fl\_ __ - - ~ SEGMENT CC-20A P-IA SDMC( I

r VATER I =  ;", ~ , - - - - ~ CONTINUED L--,-

1

                                                                               ~

I I TD S/Ci 11..0VDDVN

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X ,-a:-601

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I I - ~ l lMi J-ct-olA ~~ - _J ~ .....1 ,--cc-:112: I

                                                                                       ~---- @:ID E- lB   1111      t-11    ~
                                                                                                                                                                           )I' 1-CC-322 SEr;JCNT 1-<:t:-

• T~ @:ID!

1--CC-589 --+---

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DIIG l-CC- D3A SEGMENT CC-ISA P- lB ,- " ~ - i CONTINUED

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_J --1 I I I- CC-591.1 ...... I DIIG l-CC-02A ( ~ ~

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                                                        ...._,-cc-573
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I P-lD _[ I __ r r T I __( 10 I.NIT 2 DIIG I-CC-OJA ( ~*

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                                                                                                                                                                                                 --1 COMPONENT COOLING PUMPS COMPONENT COOLING HEAT EXCHANGERS m  lJITT 2 SlPPLY RBI LEGEND                                                           NOTES, l ALL MARK NOS, PRECEDED \/ITH CC-07                                         CC-20A                                                     . I - CC- UNLESS OTHER\llSE NOTED.

CC-08 CC-56 2, THIS DRA\llN G SHO\IS EQUIPMEN T CC-09 CC-57 COMMON TO BOTH UNITS, CC-10 UNLESS OTHERIIISE NOTED. 3 REFERENCE 11448-FM-072D, SH 1 & 2 CC - 11 ' 11448-FM-072C, SH I CC-12 111111 11111 II II II ll 11548- FM - 072A, SH l CC-13 CC CC-15A CC-16A COMPONENT COOLING SYSTEM Dv/G. 1- CC_- 01~ -* *-

e e r - GAS STRIPPER TRIM COOLER

                                             - -l-- - -

I - BR-TCV-128 1-BR-E-12

                    -,-, - -             ~

STRIPPER CIRCULATING PUMPS

                                                        -       1  Hll-P-7A   ~  -   - -   ,- - - -  - l SEAL SUPPLY V
                          '-           ~

rr- ~ PRIMARY DRAIN

                                                        -       1  Hll-P-4A   ~  -         ,- - - - - .,

I T>>IK PUMPS SEAi.. SUPPLY

                          '-           ~                -   -    ~                 ---J                   ~ - - - - -  - - - - - 1 I                                                                                    A r-----:3 DWG 1-CC-01 8 (_
                ~

SEGMENT 56 J CONTINUED

                '    L,-          -     ~

OVERHEAD GAS COMPRESSORS

                                                        -        4 1-BR--C-IA ~  -   - -   ,- - -  - -  j                         - -1~ ~ - ~~...;f;f" i        TO UNIT 2A CONTINUED
                           '-     -     ~               -                                                                                RETURN HEADER r

STRIPPER OVERHEAD CONDENSER 1-BR-E-B

                                                               -   i 1-BR-HCV-101 D
                                                                               -   - - - - - - - - - *- - - - - - - - - - I t                                                  i                     1* - - - - - - - - - - - - - - - - ~

PDT VENT ly_ -- CHILL£R/ CONDENSER

                                               -- --           1-BR-HCV- 10\G
                                                                               -                                                                  RBI LEGEND:

lI 1-BR-E-9

                                                                                         - I                                                      CC         -   -   -   -   -
                                                                                   *~-*t 1~-~

t NOTES:

                                                                                                                                                  \. ALL MARK NOS. PRECEDED WI TH 1-CC- UNLESS OTHERWISE NOTED.

2. THIS DIAGRAM IS FOR UNIT 1, UNIT 2 SIMILAR UNLESS OTHERWISE NOTffi.

3. REFERENCE \ 1+-IB- FM-0720, SH 3 COMPONENT COOUNG SYSTEM DWG . 1-CC-02A

e TO 12 INNER ~TNNMOO I 1 PIPE PEMElltlllON COOUNG <Dl.S (ce--,oc) I (cc- 20*),..,. I* (cc-,oe~ - - _ __ _ _

                                                                                                                            ~- *~ - *~                                                              "l
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I I I owo 1-cc-010

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1

                                                                                                                                                                      ~MEN T~:~ ~~ )-

CONTINUED

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L :."~ I r : -~ 1--CC-182 1

                                                                                                                                                                                                                                        - J I

HEAT ~ E R 1- El+-[- 18 . f I - , -.i CONTINUED I ,, I I I I (cc-2oe) I l

                                                                                                                                                                                             ~     -~ r-;*f,- -
                                                                                                                                                                                               @=1ill          (CC- 1'B)       ( CC-17)
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I f

                                                                 '--,                                                               OWG 1-CC-OJB SEGMENT CC-J5                 x,-cc-\.45                                       I 1-CC-178 1-RH-E-1 A                            I                 ..i. ( CC- 17)

I .... CONTINUED _J l {cc-,,) it- - _ _[ ( CC-J7) ( CC-J7) (CC-1'B) CC-191 OWG 1-CC-048 DWG I-CC-04-A I I N-REGENERATI~ I ' C><J-

• T~~~:; T(CC- 18A)

SEGMENT CC-24 CONTINUED SEGMENT CC-24 CONllNlJED I I I

                                                                                 ~   ,

r I HEAT EXOt>>ml 1-CH-£-2 _;t_ "'l- -i' lCV-lOJ :sr£a:: E- 3A THRU E-

                                                                                                                                                                                                                        'r-..J (CC- 1SA)f (cc- J7)
                                                                                                                                                                                                                                                                                - - - - - _J I

I (cc-22A)

                                                                                                                                                                                                                                                                                                          ~: -;:')

Y(cc- 1110) L HEA~~:lifu --...I I C><l 1 ,... 1 1 1 1-+ 1 1 ( CC-J7) 11 11 Q PEH fl I 1-Qi- f-1

                                                           ..r                                                                                I OWG 1-CC-05 SEGMENT CC-40 I

SAMPUNC SYSTDI I  !, D-0 'r-..J f(CC- 22B) f CONTINUED t I J PRIMNn' SHIEl.D WH.1. COOLERS 1-NS-E-2A THRU 2l I I DWG 1- CC- 04C SEGMENT CC- 32 PRES9JRIZ[R UQUD SP,tC(SMfPI.£~ -, I I~

                                                                                                                                            *1r---,
                                                                                                                                                ~

CONTINUED 1-SS-E-10 l EXCESS L.E1DOWN I HEAT ocaw<<.ER I ,~-[-t HCV-108

                                                                                                                                                                                                                                                                                         ~

r -- -- - D'WC I-CC-01A l

                                                                                                                                                ~ :         I PRIWAAY ORAIN COCllR 1-0C-E- 1 l

HCV-114 I 1 ~ 1111111111 SEGMENT CC-1 II CONTINUED I :I '1 ~ ~-- I I I ~~Pl/MP1A ~ L C><J- SEil CDO.lR -C><J L..-~ -)' CC-122 1-RH-E- 2A CC-118

                                                                                                                                                                                                                                                                                                                     .._ - -', ~ CONTINUED MJifcg;_~

FROM 12 OUTER I CONTNNliENT

                                                                                                                                                                           ~ ,--RH-R_PU_ll'_lB--, ~                                             I                                    PIPE PEMElltlllON COClJNG COLS C><J-        SEil CDO.lR             -c><l
                                                                                                                                                                ~OC-IIO                l-RH-£-2S               CC-112~

I

                                                                                                                                                                                                                                        ~       I r                                                                                               L _ -'i ~~Mriir~;:

RBI LEGEND: CC-158 CC-16A CC-16B CC-17 CC-18A 1 1-CC-399 i '

                                                                                                                                       \ - CC- 396 J
                                                                                                                                                                                                                               - -          -t J_

I I I CONTINUED CC-18B

• DWG 1-CC-01A CC-19 --- - -- - * -- SEGMENT CC-23 CC-20A - - *- - * - - -

CC-20B - - -- - -- - - CONTINUED CC-20C - - - - - - - CC-21 - - - - - - - - - CC-22A - CC-22B CC-23 CC-2+ CC-27 L---------------------------------~ NOTES:

1. ALL MARX NOS. PRO:ECE) ~TH CC-32 - - - - - - - - - I-CC- UHl.£S'S OTMER'MS£ NOlm.

CC-35 - - - - - - - - - 2. THIS DIAGRAM IS R>R UNT 1. CC-36 -- - - -- - - -- UNIT 2 SMILAA UHI.ESS CC-37 OTHERWISE NOlED.

l. REJ'ERENCE 11448-fW--<mA, 9i 11:5 CC-38 - - - - - - - 114-48-FM-<mB, SH 1 CC-39 CC-40 I I I I t ! t I I I I I 1I I I I I I t I ! 114-4&-FM-a72C, !it 1,2.3&4 CC-53 114-48-FM-0720, SH 2.J CC-56 COMPONEN T COOLING SYSTEM DWG. 1-CC-02B

e LIQUID WASTE EVAPORATOR SAMPL£ COOLER 1-SS-E-7 _1 -, I I WO EVAP CIRC PUMP I r-- SEAL SUPPLY 1-LW-P-B

                                                                                                                           -1__

BR EV /JP DIST PUMPS SEAL SUPPLY I 1-BR-P-3A&B I I I BR EVAP CIRC PUMPS t- SEAL SUPPLY --i i 1-8R-P-6A&B I I

                          ,JI-                                                                                            _....J BR EVAP WASTE BOT PUMP I-I SEAL SUPPLY 1-BR-P-10
                                                                   -- -- -- -- -- -- -- -- -- -~I I

rNIG 1- CC-018 S[GMENT c__ cc-,s~ ,----- -i I L BR EVAPORATOR BOTIOMS COOLER LOOP 1-BR- E-3A _-J:_ -- ----' 1-BR-TCV-129 CONTINUED (CC-1 SN I I I n-- WO EVAP DIST COND 1-LWk (CC-15A) 1 FROM AUX STEAM 1-LW-E-2 To DA II (CC- 158) r-- - --f'-J- - - _r.

                                                                                                                                                                                                           - J OWG    1-CC-028 SEGMENT CC- 15B L

1-CC-J69 CCNTINUED I I SYS WO f,/ AP BOTIOMS COO I-- - - - - ~ YS- - - LOOP -- -- - ~1:8) ~ --------,* I 330 1-LW- E-+ (CC-1 5N TCV-105 I I I DWG 1-CC-01 A I I -s S[GijENT CC-57 L- -r -- -- -- -- -- -- -- HRSS SAMPLE COOLER RACK -------r- - - - - _J CCNTINUED I

                                                                                                                           -- -- J I                                        2-CC-TV-209A      t L -- -- -- -- -- -- -                                  WO EV/JP DIST COOLER 1-LW-E-3                                                                                               I
                                                                                                                                                                               !I                    -...h

1-:_-:_-_ BR EV AP DIST COOLER 1-8R-E-2A BR EV /JP DIST COOLER 1-BR-E-28

                                                                             --     -- -- -- -- -- -            (CC-1 5 ~

(CC-1~-15B)

                                                                                                                               ---1::aa- TCV- 111 A
                                                                                                                               ~

1-8R-TCV-1 11 B

                                                                                                                                    ----------------I TO UNIT 2 I

l,----- BR EVAP OVERHEAD CON 1- 8R- E-7A

                                                                           - - - - - - - - 5EC_:15_9~1:B2_ _ _ _ _ _ _ _ - - - - - - - - - - - '
                                                                                                '-' "T d-8R-PCV-109A                                                       _J L-- -- -              BR EVAf' OVERHEAD CON 1-BR-E-78                     _§C~~              ~ -------------------

1-BR-PCV- 1098 RBI LEGEND: NOTES: AUX BUILDING EAST HEADER 1. ALL MARK NOS. PRECEDED CC-15A - - - - - WITH 1-CC- UNLESS OTHERWISE NOTED. CC-158 - - - - - - - 2. THIS DI AGRAM SHCWS EQUIPMENT CC-57 - - - - - - *- COMMON TO BOTH UNITS

3. REFERENCE 11 H8-FM- 072C, SH 1&2 COMPONENT COOLING SYSTEM DWG. 1 - CC-03A

r--------- 1 owe 1-cc-020 SEGMENT CC-35 CONTINUED s-- -- -- - ,,J-- l - CC-403

                                             -- --   --  ' I r-       I

_JL_F_U__;_L E....:.P 1-FC- HA I

                                                                                      ..:..IT_:C:..._O_;_;_OLE_R_JL  -

I I

                                                                                                                       -+I _ _ _ - - - - - -  - {

I owe 1-cc-020 SEGMENT CC-35 CONTINUED I I I I I I I I I I I 1 1 I I I I I I- _ I _JL_F_u_EL_P.:....IT....:.c_oo_LE_R_.L 1-FC-E- 18 I _ ~. I I I I I L....- GASEOUS WASTE COMP _J 1 1-GW- C-1A I I I I I L.... GASEOUS WASTE COMP _ _J 1-GW- C-18 RBI LEGEND: FUEL BUILDING HEADER CC - - - - - - F~O~E:~R 2 ' - . - - - - - - --.1 I f- - - - - - - - _J SUPPLY 2- CC- 403 NOTES:

1. ALL MARK NOS. PRECEDED WITH 1-CC- UNLESS OTHERWISE NOTED.

2. THIS DI AGRAM SHOWS EQUIPMENT COMMON TO BOTH UNITS

3. REFERENCE 11448-FM-072C, SH 4 COMPONENT COOLING SYSTEM DWG. 1 -CC- 03B

e e e DWG 1-CC-048 DWG 1- CC- 04C SEGMENT CC- 27 SEGMENT CC-27 CONTINUED CONTINUED 1 CRDM SHROUD COOLING COIL 1-VS-E-6A p-- L ___ _ CCC-24 ) Ccc- 25 ) 1 -------'__;_:----=--...:.;,,,c_---' DWG 1-CC-028 I SEGMENT CC - 24 )"" CON TINUED

                   - ~
                     -----v_x:;--
                                  -  -cJ- - ~

PEN #18 1- CC-1

                                                    -~

I

                                                          - --j           UPPER LUBE OIL f- _    -- _-l _-                   ~ cc~ : 5 ~   ~           - -     - -    ~ CC - : 6 ~ C:_- ~ )_

h_

                                                      ~

I p---- -wi COOLER PEN #25 TV-105A STATOR COOLERS t,. . - ,

                                                                                              ~

I LOWER l-----j LUBE OIL L iI COOLER I I 1~~~~E~ CC C - 2 ~(CC-2BA) (CC-28A~(CC-28B) (CC - 2BB) ( CC-29) ( CC-29)  ?( CC - 27) I f- - - "1 TV-120A- --W-- I

                                                                                                                                - ~

I TV-140A

                                                                                                                                                 ------ ~R, '10                      '             .~

TV-140B

                                                                                                                                                                                                           - ,, ~ J FE- 140 I

REACTOR COOLANT PUMP DWG 1- CC-048 c_ J I I I

                                                                                                                                                                                                                                ...r 1-RC-P- lA                                                                                                                                        DWG 1-CC- 028 SEG~~~N~~D28A     J       I                                                                                      SEGMENT CC-27 I                                                                                         CONTINUED I

DWG 1- CC- 04C (_ J SEGMENT CC- 28A I CONTINUED RCP HEADER RBI LEGEND: NOTES:

1. ALL MARK NOS. PRECEDED CC-24 - - - - - WITH 1-CC- UNLESS CC-25 -- -- -- -- - OTHERWISE NOTED.

CC-26 ------- 2. THIS DIAGRAM FOR UNIT 1, CC-27 - - - - - - - - UNIT 2 SIMILAR UNLESS OTHERWISE NOTED CC-28A - - - - - - - - - - - 3. REFERENCE 11448-FM-072A, SH 1 & 2 CC-28B ---------- 11448- FM - 072B, SH 1 CC - 29 I 1111111 t 'II II II I I COMPONENT COOLING SYSTEM 1- CC- 04A

II 1 CRDM SHROUD COOLING COIL

                                                    'L-_....:.1_
                                                               - VS=---=-E-__:6:..=8_ _...,.

p-( CC-24) ( CC-30) 1 I DWG 1-CC- 028 SEGMENT CC -2 4 CONTINUED s- - -@ - P ~7 -,~sa-} _~ UPPER I- _ --@v- - -{_ __ ~ cc_=- ~o ~ ~ - 3 1 )___ - ~ cc - : 1 ~ c : - : 7 ~ - -s DWG 1-CC- D4A SEGMEN T CC-27 CONTINUED

                                        '~              L~~6L~~L                    ~                 I                 PEN #27                       TV-1 058 STATOR COOLERS I                LOWER
                                         '-----1        LUBE OIL                                6 COOLER
                                                  ~~~E~

l f- - ( CC-30) REACTOR COOLANT PUMP

                                                                           ~~
                                                                                  ~"?

TV-1208 (CC-28A) 1 - - -s DWG 1-CC-04A SEGMENT CC-2BA CONTINUED 1-RC-P- 18 RBI LEGEND: NOTES:

1. ALL MARK NOS. PRECEDED CC-24 - - - - - WITH 1-CC- UNLESS CC-27 - - - - - - OTHERWISE NOTED.

CC -28A - - - - - - - - - - - 2. THIS DIAGRAM FOR UNIT 1, CC - - - - - - - - UNIT 2 SIMILAR UNLESS OTHERWISE NOTED CC - - - - - - 3. REFERENCE 11448-FM -072A, SH 1,2&3 11448-FM- 0728. SH 1 COMPONENT COOLING SYSTEM 1-CC-04B

1 L __ CROM SHROUD COOLING COIL __'. 1_-~VS:....-..::E_-6::_:C:...___ _,. p-DWG 1-CC-02B ( CC-32 ) ( CC - 33 ) l I

                                             ~       ~

SEGMENT CC - 32 )"" - __m;;.:_ -

                     ~

r _-- _-,._ _- ~ p---- -i CONTINUED PEN #16 1-CC-59 I - -j UPPER ~ CC: :.3 ~ :- 34 )_ - * - ~ CC-3.4 ~ C:_- :.7

                                                                                                                                                                                        -  _I.

OWG 1-CC-04A SEGMENT CC-27 LUBE OIL J CONTINUED

                                                     !-q              COOLER STATOR COOLERS PEN #26                      TV-105C
                                                                                                       ~

I LOWER 1-----j LUBE OIL l COOLER 1~~~Eil ( CC-33)

                                                                                                    ~ 'T'             -- -s (CC - 2BA)

OWG 1- CC - 04A f- - - -j ~ - - TV-120C 1 - - SEGMENT CC-2BA CONTINUED REACTOR COOLANT PUMP 1- RC- P- 1C RBI LEGEND: NOTES:

1. ALL MARK NOS. PRECEDED CC-27 - - - - - - WITH 1-CC- UNLESS CC-28A ----------- OTHERWISE NOTED.

CC-32 - - *- - - - - 2. THIS DIAGRAM FOR UNIT 1, CC-33 -- -- -- -- - UNIT 2 SIMILAR UNLESS OTHERWISE NOTED CC - 34 ------- 3. REFERENCE 11448-FM-072A, SH 1,2&4 11448-FM- 072B. SH 1 COMPONENT COOLING SYSTEM 1- CC-04C

~---------------- ~-----~~ r - - CONTNNMENT INSTRUMENl AIR COMPRESSOR

                                                          &AL COOLER
                                                                       - :::::4A:::::::~ ~
                                               ~=1:::::-:::IA:::::--C:::::

II *-

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RECIR~~~~i~z'iOOLER PEit ' " TV-1 IOA HCV- 1028

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• MAK~UP ~ I I FCV-112A 1- NS-E-lA NS ~ - - - - -<><J- J. -I STEAM GENERATUR RECIRCULATION COOLER 1-RT-E-lA SYS 1-NS-FCV-101 934 L-- ~ ~

                                                                                                                                                                                              ...~-    -C-::1-
                                                                                                                                                                                                             ~        - - '- -

I-C:C-9J6 1-C:C-9J6 STEAM GENERATUR RECIRCULATION CO OUR 1-RT-E-1 8 STEAM GENERATUR RECIRCULATION COOUR 1-RT-E-l C RBI LEGEND: CC-40 - - -- CC-48 - - - - - - - CC-41 - - - - --- CC-49 - - - - - - - NOTES: CC-42 CC-50 - - - - - - - - - 1. AU. MARK NOS. PRECEDED CC- 43 - - - - - - - - - CC - 51 ------- 'MTH 1-CC- UNLESS CC- 44 - - - - - - CC-52 - - - - - - - OTHER'MSE NOTED. CC- 45 - - - - - - - - - CC-53 - - - - - - - - - 2. THIS DIAGRAM FOR UNIT 1. CC- 46 -- - - - - - -- UNIT 2 SIMILAR UNLESS CC-54 - * - ** - * - OTHERWISE NOTED CC - 47 - - -- -- - CC-55 II II 1, J. REFERENCE 1U-48-FM-0728, SH 2.tJ COMPONENT COOLING SYSTEM DWG. 1- CC-05

D\/G. J-CH-05 SEGMENT CH-15 TV-1204B {H-30~ MOV-1370 DVG. I-CH-02 NO SEGMENT DVG. J-CH-04 ~ (CH-18) A (HHl-08) ~ SEGMENT CH-33 > - - -<.:>< >- ___ - --- -- -t><l 1111111u11111111R111111u1w1~ MOV-1289B MOV-1289A = _

                                                                                                                                                              ~lllllllllllllllllllillLll\lllllllllllllllllllllHIIIIUlllllllllLlllll~llllll;.

TO/FROM I CC SYSTE M (CH-JZ) j __( TCV-1143 DVG 1-CH-04

                ) SEGMENT CH-36 I
                                                                                                                                                                                                                                   ~~

DVG 1-CH-OIB MOV-18698 X)J

        ***~---****                                                                                                                                  SEGMENT t-t-lJ-08                                                          ,l CONTINI.CD                                                 DVG 1-SJ-OJB NOTES                            RBI LEGEND SEGMENT HHl-15 I ALL MARK NOS PRECEDED          CH-lB V!TH J-CH- UNLESS             CH-19 TO AUX.                      OTHERVISE NOTED               CH-20 CH-21 BLDG.                    2 THIS DIAGRAM IS FOR UNIT I.

CH-22 SAMPLE UNIT 2 SIMILAR UNLESS CH-23 SJNK OTHERVISE NOTED CH-24 3 REFE~~CE 11448-FM-OBBA, SH 4 CH-25 11448-FM-OBBC SH I CH-26 0\/G J-CH-02 CH-27 SEGMENT CH-OJ RV-1209 CH-28A CH-28B CH-29 CH-JOA CH-30B CH-31 CH-32 CH-41 HHJ-08 IHlllltlllllltllllllllUUJUlllll CHEMICAL AND VOLUME CONTROL WG. !-CH-OJA

I

                                                                                                                                                                                                                                                                                     ~ [GM[NT RC-38
                                                                                                                                                                                                                                                                                                             '   DVG 1-RC-OIB DVG. I-CH-D5 SEGM[Nl CH-14                                                                +, 1111 , 11
                                                                                                                                                                                                                                                                            @:TI),*
                                                                                                                                                                                                                                                                     ., CJ- .. , ,      ~

I , DVG 1-RC-OIA 5l=@:iD PEN***  : HC V-1556A EGMENT RC-37

                                                                                                                                                                                                                                                  ~~                               L.. I                      . DVG ]-RC-DIC I l-CH- 278           DIIG. I-CH-DIA                          t;' f ~I-09)                      HCv~SEGMENT RC-39 I (HHl-09)

SEGMENT HHl-08 CO<f CD $ ' 10/rRDM UNI l 2)

• 4 *
• L

I

                                                                        @1-00 r--   M~-

A {Hi;Hs)

                                                                           -

• _ .. _ , - " ~

A(ffi8v (fjHJ-06() MDV-1287C i----~ij~ - ,------ ~ oo

                                                                                                                                               ~

2:

• QHHt-=c)

I I I l i-HOV-J286A i (HHHJ<e) I I r-I CHARGING PUMPS_( I _

                                                                                                                                               >= *
                                                                                                                                                             "'                1 I                                  I         ;f_ ~  (HHJ-09)
                                                                       ~                                                                             !*                                                                                                         ~
                                                                                                                                                                                                                                                                ~lZ)J uN!l 2 UN!l 1                                                                                           (fjHH1-;c")A I                                            I         0*1-o,©A(tt<1-0*) 1
                                                           =
                                                           =-=, \

OjHJ-05()"

...t:><}-J r * * -~~V-l B?B 2

H-i]- 09 i ---

                                                                                                                                                                                                                       ~
                                                                                                                                                                                                                                    =-t><::}-

HOV-1287* - '

                                                                                                                                                                                                                                                   ..J                          D\JG 1-Sl-018 SEGMENT HHJ-13 r

J-CH-276 ~ (HHJ-06A) J-CH-267 ~ HHl-llSA) J-CH-258 t (HHJ-04A) D\JG. 1-SI-OIB SEGMENT HHl-17 r - - - - - - - - I

                                                                    -i- - - r - - - - - - - -                                                   - j -,        (HHJ-07)A<fiH!-04B) (HHl-04A)

JIr--;-:r.;.256 -L - -- - --ce::i-r

                   - ( HH!-07) AtHHI-06B) t:     ~          -

(fjHH)6A)

                                        ~ ~ '-      '~        '-  ' .J
                                                                                  i::i' L (HHJ-07)Fl(HHl-05B)        Ir - ~ ' .,j 0,H!-OSA)               :

L - -t><j. - HOV-1275* 1 L___, ...Q_ - 10 AUX BLDG l1JV*l27SC l-CH-274 ~ SAIIPLC

                                                                                                -   -t><j UMlllttUWt1 1 M0V-1275B                          I-CH-26 @~ :t[

5

                                                                                                                                                                                                            ~

I (1+11-o~A) SAMPLE SINK CHARGING W CHARGING""' W CHARGING PUMP

• PUMP PUMP I P-IC I P-IB P-lA iI (LHJ-18)

                                                                                                                             . _. _. _. ,.                           = ~ =                                      I                                                         NOTES
                                                                    .         @,-, ..,A@GD                                                                           ~                     ~                     I                                                       I ALL MARK NOS PRECEDED L *- *- *- *::..t><:1                                                                                                                  --f 1:1rn1111111111111111111uuuumuuu               * -- -                                                                        VllH I- CH- UNLESS j               MDV-127DB                                                    ~                          MOV-1267B                            I                                                          OlHERIIISE NOTED 2 THIS DIAGRAM IS fDR UNIT I, UNIT 2 SIMILAR UNLESS OlHERVISE NOTED MDV-1267A h           Hl-O<A)                                               REFERENCE 11448-,M-OBSB, SH I 11111 ~ D V G I-SJ-OJA
                                                                                              @JD MOV-JB6JA               [GM[NT LHl-08                                                                                                                                                           11448-,M-OBSC, SH 2 (HHI-OJ)p j      (HHI-D1)     A        'DVG HI-OJA                RBI LEGEND, I I       , - L~              S[GMENl HHl-02            CH-04
                                                                                                                                                                                                                 - I                                                     CH-05 s~~iE~~c~~~~D3 CH-16       I lltlllltlllllll11111111111111 CONTINUED r - .L_*- - *- - *- - *- -*- - *- -*-- *- -*J _*- - *- - *-,- *- - *- - *- _.LiI                                                                               =~

CH-17 HHJ-03 HHl-04A i.._~ DVG 1-SI-OIA HHI-04B (CH-04) A (.CH-05) (CH-05) LCV-IIISB SEGMENT HHl-02 HHI-04C

                ---------------, -(><],----0 -<><,,,------t><J- - , -

SEAL \JATER  : MOV-1381 -

                                                                                                              --c:::J--=--S PEN     lt   19 DVG   I-CH-05 SEG~NT CH-06 I

I HH1-05A HHl -05B HHl-DSC lltlllllllllllllllltNUIIUIIUIIIUIIUUIIIIIIMIIIIUIII

                                      !            ITTR !                                                                                                                                                                ~I~

HH1-06A J--

                                      "-----<><,, ------..                                                                                                                       ~ ,--,- -,--,- -,- ~                                           OVG HI-OJA MOV-ISo 3B SEGMENT LHl-07 HH1-06B HHJ-06C HHJ-07 HHJ-08 HH!-09 LHJ-18      tlllttlllllJIIH11Ull11111!1ttrllltllUIIIIUl\tJlrlllltul DVG I-CH-02 S[GM[Nl CH-04 CONTINUED                                                                                                                                                                                                CHEMICAL AND VOLUME CONTROL                                                   D\.IG 1-CH-O!B

TO UNIT 2 @=1ID CH SYSTEM SEGMENT CH-40 INCLUDES BALANCE OF 1 CHEMICAL AND VOLUME CONTROL SYSTEM RV- f (SEE SEGMENT DISCRIPTION AND DRAWING M

                                                                                                                                     ,                                                    11448-FM-0888, SHEET 1.)
                                                               .                                                                     I FROMBOTTLEsJ°"

HYDROGEN L .. . ,I -l..-'l ~ '

                                                                                                                                     '                                                             @3ID
                                                                                                                                                                                                                     ~

FROM L .. _j1--.. PCV-102 1, PCV-101 ~ - .l -!><J- ..PCV-1118 DWG. 1-CH-04 , I RV-1257 TR UCK FIL L J I SEGMENT CH-36

• DWG. 1-CH-OlA i: "'~ C~INUED~ NO SEGMENT (1/2" LINE SIZE)

                                                                                                      !~

lr ;*'N rN

                                                                                                                                          ~                    PCV-1119

_ _J_. ~m,c SOV-1258 PCV-1117 SYSTEM

                                                                                                                                 ~1111111111+                                     ~
                                                                                                                             ~ =~

i - ~\-, I-. r1 tiA~~EL TK-2 r 1

                                                                                                                                                                                                                                                                                            ~            r;~~TEs:
                                                                                                                             ~H                    ©Ew I-*                                                                                                                                I RV-1209

l::

                                                                                                                             ~ ~@EID                                              @EW                                       -*- --*--*-- *--*,- *--*--*--;--*-- *--*-J *--*--*--*0 1
                                                ~(lt!IIIIIIHllllllllllll!lltll!l\1....-C !!lllllll!tlllllll!IIIIII~                                                                                                                ~ r @=.Q])t '                          :                              DWG 1-CH-OlA
                                                                                                                                                                                                  @t[j)           1       l-CH-203/20 4                  :                1*  """"'H-                   SEGMENT CH-32
           ~lllllll11111111111llllllltlll1lllllll~ll!l1 ...... llllltl!lll111tlllllllllltllllllll!t1111!                         -                                                                                                                                            ~

l l)l!!N 1 1 _ - - ,,., I I i._ FROM BR

           =                                    =                                                            'v                                                                             ~                     I                                      I                                                SYSTEM
           =                                -1=              1-CH-215 I
  @                                                                                                                                                                                         -y
                                                                                                            £:,                                                                                                                                                                1-CH-173
                                                                                                                                 ~ ~

I ,--- * - - *- - *- - * - - ' - - * --' 1J~1 C><J 11111 FCV-1114A = 111 l l *C><J 1C><J t11111~

                                                                                                              =                  =            T@=.Q])                                                             I I
                                                                                                             ~            -      ~11111111 C>k:):: , ,             ~                                  ,~ ~

I

     =©l=ID
                                                                                                  ~l~~ -I~~::;~~3Bt!                                                                                     ~~

I NOTES: j <<E=

                                                                                                                                                                     @cQj)                                           @E                                                                          ALL MARK NOS. PRECEDED 11-CH-223                                                                        1-CH-219                                                                                                            > ~         ©E@

u WITH 1-CH- UNLESS CHEMICAL MIXING (EBE@ i LOCAL ~ i OTHERWISE NOTED.

2. THIS DIAGRAM IS FOR UNIT I, FROM PG TANK l I

SAMPLE '!2 - v-n ©E@ I UNIT 2 SIMILAR UNLESS

                                                                                                                                                                                                         ~ ~~

TK-3 I WATER SUPPLY  ! r--- -t><J- ----, I I I DWG. 1-CH-018 OTHERWISE NOTED

3. REFERENCE 11448-FM-OBBB, SH-1

                                                                                                              !                                                                                          ~        ~- -----                                 -L-l.- r    SEGMENT CH-04 CONTINUED 11448-FM-OBBB, SH-2

I i TO I @BE)

                                                                                                  ~i 1-CH-221 i RWST                                                                             ?'1-CH-230
                                                                                                                                                                                                                  ;                                                   TO/FROM CC SYSTEM 111                               '--1><'.l---     -       ---'1' - - *- !         ....... ....... .. _ ,_ --*- . ..... .. ... .. ,. ... ... .. ,._ ,_ ,_ ....... .....   -*1 @IT)                                                                            RBI LEGEND
                                                 =                                          1- H-229 :                                                                                                            ,

SEAL WATER

                                                 +"! ltl 1111111111!111 C><J It ...... I I II II      _ ,.. ,.;;;.,,., ,,._ '"' " '" - * ** - '" '"'"' ' ",. __ ,,, ,.,,..,., .,. ,. ,,, ,,,_,,. ,,._._,,. ,,. .,{                                                                              CH - *- - *- - *- - * -

HEAT EXCHANGER

~~ i CH * - * - * - * -

2-- .' ~ .. ~ *;o**-***..N E-1 DWG. 1-CH-03 SEGMENT CH-38 CONTINUED

                                                                                                      * ***-*** -*** ** * ...... ................. ..                                     ******-***i                                                                                           CH-3 * *- *- * - - * - *- - -

CH-4 * - - - - - - - - - -

• CH-36 1 1 1 1 1
• 1 1 1 1 1

                                                              @]ID            ~                                                                                                                                                                                                                 CH * * - * * - * * -

DWG. 1-CH-OIB CH-39 1111111111111111111111111111111111 SEGMENT HHl-03 CH * * - * * - * * - CONllNU(O HHl-3 ....... ....... ...... .. - . ...... CHEMICAL AND VOLUME CONTROL DWG. 1-CH-02

                                                                                                                                                                                                                                    *e
                                                                                                    @=ID SEGMENT CH-3 9 INCLUDES THE BALANCE OF THE CHEMICAL AND VOLUME CONTROL SYSTEM CONNECTING TD BORIC ACID TRANSFER.
                                                                          <SEE SEGMENT DISCRIPTION AND DRA\.IING 11448-FM- 088A , SHEET D FROM EVAPORATOR BOTTOMS TANK CIRCULATING PUMP BORIC                                                             BORIC                                                                         BORIC FROM                 TO                AC ID                                                             ACID                                                                          ACID AUXILIARY                                                                                                             @=ID                                                 CH-39        TANK CONDENSATE           TANK                                                              TANK CT8=ID STEAM SUPPLY LOCAL SAMPLE HEADER             TK-IA
                                                  --- _;t_,

HCV-1110 TK-IB

                                                                                                                            --X-,

ecv-nos [ r-c

                                                                                                                                                               ~;~

l 4r TK-IC

                                  ~

I I I I I I I --~------ : I I

---~

I 1 ----~~~~ TO HIGH LEVEL l.'ASTE Lcx:l--:--::=-  :----c,<J-:-=LOCAL --~ LOCAL DRAIN TANKS 1 LOC AL ~ SAMPLE SAMPLE ~ SAMPLE 'f I ,;:,

                         . -- __________ ,______ ___ r~ J----                - -{><J- - --r-----**-----------r--1><}- ----- -l ~ 1-___ -                                                   1------------~

i i i'-- -t><}- ------i'*---,  ::

I (CH-39) I I I  : I

              @=ID :

I l

                       !-t><l-
                                                         ~

9'- - ,. - ._,-*

• l-CH- 84 I-CH-95 (CH- 38) (CH-39)t

                                                                                           .,J 1

I

                                                                                              \. * * * * -      **
                                                                                                                    - -{><}- - . --i
                                                                                                                                      ~

I I f I I

                                                                                                                                                              .}:,

I I {XJ- ..,- - -{><}--: *-- --- *{><}-'- --( I BORIC

TO UNIT 2

cHARGJNG I PUMPS I

I 1

ACID J-, 1  : I FILTER s~~~~11~sfi5s 1 ~ -" Ic$]_'" tJ I~-~g Ic$]_'g " *~:~r.i:* 1

                                                                                                                                                                                                ~":,-*

1. ALL MARK NOS. PRECEDED l.'ITH l - CH- UNLESS l-CH-88 ~ ' OTHERl.'ISE NOTED.

L - -!><J, * * - '"* * {><), J * - * - -I><}- * * *'- * * -{><)- - * * . . . . . . - - * * * * * * * * - ' 1

2. THIS DIAGRAM IS FOR UNIT I,

                                                                    ~               @=ID                                                                                                           UNIT 2 SIMILAR UNLESS OTHERl.'ISE NOTED

3. REFERENCE ll 448-FM-088A, SH I RBI LEGEND*

CH-3 8 - - - - - - CH-39 --------------- CHEMICAL AND VOLUME CONTROL Dw'G . 1-CH-03

~-- - -:*- - ------------ I I t-CH- 46 z t-CH-14

c MIXED BED MIXED BED CATION BED u

  .!.                                                                                              DEMINERALJZER                       DEMINERALJZER                                      DEM!NERALIZER HA                                   1-!B                                               l- 2 DEBORA TING                       DEBDRATING TD   DEMINERALIZER                     DEMINERALJZER R',/       1-JB                             1-JA SYSTEM t--~~---;
                                                                                                                                                    ~
                                                                                                              ~

I f - ~-~

                                                                                                                                                    ~Ill ~

1- CH-62 ,

                                                                                                                                                                                                        ~

t-CH- 49

CQEID

                                                 ~

(Qj=fil

------ J I11r1

~ ~

1 1-CH-24 C><l--- - - ...I 8

                                                                                                                                                                                                                   - -,       I J.                                                            ~

TD R',/ SYSTEM TD R\J SYSTEM l TD R',/ SYSTEM 7i- cH-478

                                                                         ~ @EID TD R',/

SYSTEM 1::::: TD R\I SYSTEM 11-CH-26 TD R\J SYSTEM TD R\J SYSTEM 9

                                                                                                                . ,_t FROM PG                               FROM PG                                              FROM SYSTEM                                SYSTEM                                                PG

.- .. -l><l- . . @EID, *~ - - ..... - - -,

SYSTEM I TCV-11 43 r - - - - - -{><}- - - - , 1 f D\IG. t-CH-02 @D§)~~ y t SEGMENT CH-36( -{><)- - - -i><r - ..& ... I* ~H~ C~E CV-tllSA REACTOR l HCV- 124~

                                                                                                                                                                                        ,       NOTES*

L. ALL MARK NOS. PRECEDED SEGMENT CH- 32 1I CQEID I' f COOLANT \JITH I - CH - UNLESS FILTER DTHERIJISE NOTED.

                   ' ______ _____ j ~                                                                            TD REACTOR FL-2                         I            ,       2. THIS DIAGRAM JS FDR UNIT I, UNIT 2 SIMILAR UNLESS
                                                                                                                                                                                       .~
                                                                       -- ~ ~ =~                 C~ 36_2    __     ~ V~ Y-   -  _    -  -    _ _ _ ..._          __      J                      OTHERWISE NOTED I

CQEID

                 }       - CH-42 1-CH-27 I

3. REFERENCE 11448- FM- OBBA, SH 3 ll448-FM- 088A , SH 4 L _______________________________ _ *-* *-* * -*. -** - * * - * * - . - - * * - * * - * . - * . __J RBI LEGEND ,

CH-33 --------- CH-34 * - - - - - - -

• CH-35A - - - - - - -----

CH-35B 1 , 1 II * , 1 , , , 1 1 CH-36 - - - - - - - CH-37 -* * -* * -**- CHEMICAL AND VOLUME CONTROL D\./G. 1-CH- 04

I RV-1382A r----r TO PRT (tH-06) I Dw'G 1-CH-OlB L . - , _ _ - , - _ SEGMENT CH-05 ~ PEN # 19 I

                                                                         -- -- L_ -- -- -- --                     - -- -- --                       --1--                                  - --,

1 I I I I I L_ ~ - - r ,------ I I

                                                                                                                                                                                                  . ,I I                                        I
                                     ¢:H-OG) HCV-1307 ¢:[: I                                                                                               I                                        I I                                                                                              I I

TO/FROM E-4 CC SYSTEM

                     ~,~i-oa HCV-1201                       HCV-1137 Dw'G. 1-CH-OlA l                   EXCESS LETDOw'N HEAT EXCHANGER
                                                                                                          ¢:H-06)

HCV-1389

• I I I l

                                                            ~                                                                                                         ~
                                                                                                                   - 1                                      I
                          ~ , (CH-15)

I I

                                                                                                                                ~

• I

($ I

                          ~§ ~

I

• I I

urI .~~~L-1 L...r-.., l--1 '--1)8::]-l '""'" , ,_., r  !

                                                           ..L D',/G. 1-CH-018           ~~-14) t
                                                                                                                      '           i                         I        ..L
                                                                                                                                                                                                    ~      H-06)

L ~*! ~ l-CH-27Ef I Ce:J

                                                                                                                   ~

c:e:J------l

                                                                                                                          ¢:H-07)

I--------C8:l-- I I--------C8:l-- u

c I I

                                                                                                                                                                                                         ¢:[:

I L---- - - - - - BCP ~ -flCP ...J I t (CH-13) I r- ~ I CH- 350 I I (CH-10) 111111" P-lC (CH-12) I r*- ¢:H- 08) P- lA NOTES,

l. ALL MARK NOS. PRECEDED

                                                                                                                                                                                                     \,/ITH 1-CH- UNLESS OTHERw'[SE NOTED,

2. THIS DIAGRAM JS FDR UNIT 1.

UNIT 2 SJM!LAR UNLESS OTHERIJ[SE NOTED

3. REFERENCE 11448-FM- 088C, SH 2 (CH- II)~

                             '                                           fl PEN # 35                                       fl PEN # 37                            PEN # 36 I

I . . (CH-14) (CH-14)1 (CH- 14) RBI LEGEND, L__ j---_J 1 SEAL ',/ATER ~

                                                                                                                           ~
                                                                                                                                                               ~

I CH-06 CH-07 CH-OB CH-09 CH-10

                                                                                                                                                                                                                          , ti I t
                                                                                                                                                    --~

CH-11 --*-**- L_ _-l~tE~;~~N --- --- --- ~ - --- --- --- --- --' --- --- --- CH-12 CH- 13 CH-14 CH-15 llflll'llllll'111l!!lll!!t111111111111111UUII CHEMICAL AND VOLUME CONTROL D\./G. 1- CH- 05

e TD WT

                                                                                                                                                                               ,Cl D

SYSTEM 3:: 3::

J>

1-'w'T -1356 -----------1 z V) r,

J>

r 3:

V) TO -< V) FROM SAMPLING -< r, I 3::

                              ~------< *:::::-                                .;: *      ~~i'"

DIIG. 1-CN- 02 ND SEGMENT 3: V) I P-2B (CN-09) ...'. 0 TRANSFER PUMPS CONDENSATE ,---J TRUCK ST ATION s~~~~~s1l~K @:@ ' (CN-09) ? (CN-07) TK- 2 -i-i - - - - - - - - - ~ 28 FROM

  \/ATER TREATMEN::.-----1><1----"r--..J-,---.-l><J-L--{><J---J SYSTE M 1-'w'T-341 TD                                          FROM r----=-m(CN-09)       (CN- 07)

CHILLED VATER..,....__---11.><J--.---~ HEATING STEAM ' r - -L><~t-----, SYSTEM L_ _C ~ ( CN- 07) 1-HS-102 SYSTEM 436 LCV-!02A TD CHILLED VATER"""4._--l~lf---' SYSTEM <UNIT 2 2-CN-292 D\IG. 1-AF\I-OI A ( ... '4 (CN-09) '"".,,. t=J I SEGMENT CN-08 J l-CN--l50 CX) CX) ONLY)

                                           .,.,        FROM         (

(CN -09) I

                                                     \IT SYSTEM)
                                                                         ......       - - - .-1                                                 OOK TD
                                           ,Cl D                             300                       '                                             HD                                           RBI LEGEND:

3: SYSITK EXTRACTID STEAM :J> C HOT VELL E!lUALIZING LINES CN-'-07 SYSTEM X TO l-CN-SC-1B 143 V)

                                                                                               '                                                                          D\IG. 1-CN-OlB      CN-09 r,

J>

3: 1-AS -156 fL I ----) D\IG. 1- CN - 018

                                                                                                       - ___( SEGMENT CN- 09 CONTINUED ND SEGMENT V)          1-AS - 93                                                                                                                              NOTES, V)                                rROK f£ATJM; r,

sr= DRAINS 1. ALL MARK NOS. PRECEDED

                                                       ! - AS - 91                                                                                                                                \/ITH 1-CN- UNLESS I

3:

                                                                                       ~1 OTHERWISE NOTED.
                                                                                               '                                                                                              2. THIS DIAGRAM IS FDR UNIT !,

UNIT 2 SIMILAR UNLESS OTHERWISE NOTED

3. CONDENSATE SUBSYSTEM

4. REFERENCE 11448-FM-067A, SH 2 TD AB 11448-FM-077B, SH 2 SYSTEM VIA UNIT 2 CONDENSATE SYSTEM Dl;/G. 1-CN- OlA

e TD/FROM CONDENSATE PQ!SHING SYSTEM

                                                                                       , l: :=r I

I I TO s~~~EN~~~~a25s-CONTINUED

                                                                                 -   -   ;_ I-         (C~-o5xt~ ~

1- CP- MOV-100 0 J_----,--, I I D\IG l-CN-02 SEGMENT CN-05 FROM P-3C 1 - - - ~ (CN-06) 9 (CN- 04)

                                                                                                                                        ~t :I      I CONTINUED
                                                                                                                                                                        '1 INLET TRAY SAMPLE C><J   D      c::kJ- - -cH><I- - -          I - -C}- - - _,

I OUTLET TRAY SAMPL 78 TCV-109A 76 I I HOl\lELL SAMPLE TO EXHAUST HOOD SPRAY (CN-06) 9 (CN - 04) I  : C><J D c::kJ- - -(J-C,<)- - - .J I 75 TCV-109B 73 I _J I I r-- --<J- ------,-----------r-J I I I L I I I l-CN- 39 l-CN-51 1-CN-63

                                                                                                        ~

1

: ~ : : : ~N-38  :::~:: 1-CN-~  :::~:: ' :1-CN-62

                                                                                                                                                ~            E~T~s. .--,____               J 1-CN-P- lA              ~           1-CN- P- IB             r.,       1- CN-P - IC                     I   I (CN-01)
                                                                                                       ~                                                                         I i                                    ,

TO/FROM BC SYS (CN-03) J I

                                                                                                       -,&'                            ~                                          (CN-02)1 J

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3. REFERENCE 11448-FM-084A, SH 2 CONTAINMENT SPRAY DVG. 1-CS-OlB

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3. REFERENCE 11448-FM-071A, SH I CIRCULATING \./ ATER SYSTEM D\./G. 1-C\./-01

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1-FC-50 1-FC-49

                                                                                                                                                                                                                                                                                                  .,1 1-FC-E-IB                                                  .

SPENT FUEL PIT FUEL PIT I PURIFICATION PUMP COOLER (FC-06) (FC-06) r-:-.... -------,--~ I -FC-73 2-FC-73 I

                                                                                                                                                                                                                   ~----

( (FC-06)

                                                                                                                                                                                                                              -- -<*l- - : ]

1-FC-44

                                                                                                                                                                                                                                                    @t                 - 0 ~ --- ~
                                                                                                                                            ~ .. ~                                                                                                   1-FC-P-JA              1-FC-45 1-FC-46 I-   ,:,c:.3s   -           ~

1-FC-E-IA

                                                                                                                                                                                         -       1- Fc-

• 2
• I SPENT FUEL PIT
• FUEL PIT  : PURJFICATJON PUMP I COOLER I

(FC-05) (FC-04)  !

                                                                                                           ~

11 \_~ *~

(FC-09)

                                                                                                                                                                                                                   ..... .. _,, _..    ~

(FC-04)

                                                                                                                                                                                                                                                  ,, ~

1-PG-55 1-PG-54 r ' - '- '- '- ' - ' - '-U- ' - ' - ' - ' - ' - ' - '.._ ' - ' - ' - ' - - ' - ' - '...: ' - ' - ' - ' - . ~ _

                                                                                                                                       ' .J.: * - * - ' -,*    .....;:;,l(J,. ' I --c> ' ~
                                                                                                                                                            . 1-FC-70                 .         1-FC-71

( 1-FC-FE

                         \:iv                                                                            :::                               I                I                         I    =
                                                                                                                                                                                      .L...c:,.
                                                                                                                                                                                           ~

I I I .~ 2-FC-71 (FC-05) : (FC-04)

                                                                                                                                                            '-(FC-09)
                                                                                                                                                                  *- *1*                                                            RBI LEGEND:
                                                                                                         ~ 1-FC-9                           ~ 1-FC-11                                                                               FC-01      - - *-- * -- *-

1 _ (FC-09) (FC-06) I (FC-03) (Fc-01) L. -c>'<l- ' -, FC-02 - - - - - - - '--0'0- ' -o-{[}--c>- 1-FC-23 1-FC-26 1-FC-29 1

                                                            .. - FC-72
                                                                     -D'<>- - - - - - - -                                                                                          1-FC-69                                          FC-03 FC-04 1-FC-FL-2            (                         1                                                                                                                                                                         FC-05      I I 1 I t I I I I I I I I I 1I 1 I I I I I I I I I
                                                         /J FUEL PIT FILTER             I               1-FC-16 ' f      (FC-06) j_

1-FC-P-IB @ HC-P-IA Q FC-06 FC-07 FC-08 I I

                                                     ~      - - - - - ~- ~ ~~ 17 1-FC-HB SPENT FUEL
                                                                                              ~T
                                                                                                      ?I               SPENT FUEL
                                                                                                                          ~T y
                                                                                                                                                                                                                                    ~-M        - *-         *- *-          *-      *-      *-
                               ~  ;

PUMP PUMP FUEL PJT NOTES p JON EXCHANGER

                                                                                                      ~*                              t                                                             .

1 ALL MARK NOS. PRECEDED i VITH J-FC- UNLESS L I 1-FC-4 1-FC-5 DTHERVISE NOTED.

                    =

(,_t;;~ 76 _ , _ , _ , J (FC-09)-~ J

                                  *r

• 1-FC-1 j

(FC-08>.! 1 (FC-07) 1-FC-3 I I L----------

                                                                                                                                                -                                                                                                                                                 1-rc-36 1-FC-34
                                                                                                                                                              ~
                                                                                                                                                                      ~

(rc-o 2) SPENT FUEL PIT r

                                                                                                                                                                                                               ...J                2. THIS DIAGRAM IS FDR UNIT 1, UNIT 2 SIMILAR UNLESS DTHERVISE NOTED 3 REFERENCE ll448-FM-079C, SH I (FC-03)1-FC-35 II448-FM-081A, SH I 1-FC-2 1 FUEL PJT SYSTEM                              D'w'G.              l-F'C-01

e e

                                                                                                                                  <O r---

HCV-

                                                                       !SSA
                                                                                                                                 "'(;J*"

( ~~~ ( ~',/~09~ - - ~ - 6

                                                                            * - ( ~W-~9: ~        \J~    :~\J~~~'. ~ ~~15)                              (FW-1 8)

FCV- 1- F\J- 12 1-F\J-10 DWG. 1-FW-02 CF\J-08)

                <,- ---   I MDV-154A 6                 7 1478 1-RC-E-lA CONTINUED            I                                           PI I

I 47 6 I c:o r--- HCV-155B

                                                                                                                                 "'(;J*"

TD ~ SAMPLE SYSTEM 94 * :r_v~ MDV-

                                          ~ )-   :_~        itG ~_   ~~-~)L __<_r"_-_14"J-<1-_.'_F~~F~~~~"~1 FCV-l F" 43
                                                                                                                                                   ~ :o~_

1-F"-41

                                                                                                                                                                      <~~-20}

154B *_r 1488 - w- w 6 87 M 1-RC-E- IB

                                                                                                                                                               ~
                                                            ~                                                                                                  ~

F\J REGULA TING VALVE

                         .I I

BYPASS VALVES r--- r--- I HCV-155C """za...w (FW-16) DWG. 1-FW-02 <,- * *--, (F\J-10) 'T" ( F\J-13) (F\J-13) (F\J- 16) ( F\J-19) (FW-19 ) ( F\J- 08)  : F.\J~ C~\J~O)- - CONTINUED MDV-154C F\J LINE

                                                                                - - ~ - "111 C><J 11 11 111111 ; ~ 4 -

q7 FEED\JATER

                                                                                                                               -c::J-         ~71"'""1""'~~ '1""'"     1-RC-E- lC ISOLATING                                REGULA TING                                                                    n VALVES                                   VALVES FROM AFW SYSTEM RBI LEGEND :

NOTES, FW- 08 - ** - ** - * * - FW- 09 - - - - - - - - - L ALL MARK NOS. PRECEDED FW-10 - *- - - - *- - - \JI TH 1-F\J- UNLESS FW-11 ----------- OTHERWISE NOTED. FW-1 2 - , * - , - * - , * - *, - , , - 2. THIS DIAGRAM IS FDR UNIT l, FW-1 .3 11111111111111111111111111111111 UNIT 2 SIMILAR UNLESS FW- 14 - ** - * * - * * - OTHERWISE NOTED FW-1 5 - - ,- - - - - - - 3. THE FEED PUMP OIL COOLERS, FW-1 6 - - - - - - - - SEALS, ~ STUFFING BOXES ARE FW- 17 --- -- -- ---- SUPPLIED \,/!TH CODLING \JATER FW-18 - * - * - ** - * - ** - ** - FROM THE BEARING CODLING FW-19 11111111111111111111111111111111 \JATER SYSTEM. FW- 20 -**-**-**- 4. REFERENCE 11448-FM-068A, SH l ~ 2 FEED\./ ATER SYSTEM D\./G. 1-F\./-01

I I FEED'w'ATER HEATER !A D'w'G l-F'w'-01 (F'w'-08) D'w'G l-F'w'-03 CONTINUED (F'w'-04) CONTINUED TD SAMPLE~ I SYSTEM 94 I CONDENSER 1- CN-SC-lA (F'w'-05)

                      - - - - - - - ~ D'w'G 1-F'w'-03             FEED'w'ATER ri I RECIRCULATION<~

(F'w'-05) VALVES Gi CONTINUED .., C) FEED'w'ATER I HEATER lB

                                            ,.- - - - - - - -t><}- - * ~

1(F'w'-03)

                                                                           ~

(F'w'-07) (F'w'-07) A ([y-08) J E-lB

                                           ..1.-- ~          ,,,   ,,,, , I , , t><),- . 1- ~                 --- -

D'w'G 1-F'w'-03 )" - - l-F'w'-112 MDV-150B ~ D'w'G 1- F'w'-01 (F'w'-03) B F'w' PUMP CONTINUED (F'w' - 08) DISCHARGE VALVES L. - --{><}- - _ _J CONTINUED BC FEED'w'ATER PUMPS NOTES, RBI LEGEND:

1. ALL MARK NOS. PRECEDED

                                                                                              'w'ITH 1-F'w'- UNLESS                                FW-03    -- - - - - - - - - -

OTHER'w'ISE NOTED. FW-04 - - - - - - - - - 2, THIS DIAGRAM IS FDR UNIT 1, FW-05 ------------ UNIT 2 SIMILAR UNLESS FW-06 _,, _ - *- - - .. - ... - DTHER'w'ISE NO TED FW-07

3. THE FEED PUMP OIL COOLERS, SEALS,~ STUFFING BOXES ARE FW- 08 ----**-**-

SUPPLIED 'w'ITH CODLING 'w'ATER FROM THE BEARING CODLING

                                                                                               'w'ATER SYSTEM.

4. REFERENCE 11448-FM-068A, SH I ~ 2 FEED\./ATER SYSTEM D\./G. 1-F\./-02

FROM 1-SD-P- 1A () 1- SD- 15

                                                                      ~p 1-SD-6 FROM 1-SD-P-18 1-SD LCV-106 FE- 103 I

FEEDWATER HEATERS ' I

                                                                             ~                                                  ~                    :                    0 Cl  ,Q "           " D "' C><l 1-CN-132 CEHD
                                                                                                          - """ r *- -

I

                                                                                                                                                - r;~

I

                                                                                                                                                       ~ ~

_I_ -o-,------ 1 I

                                                                                                                                                             ~
                                                                                                                                                                              -c><!-

1-CN-139

                                                                                                                                                                                        -*-~1---r :) --s ~              P-1B DWG 1- FW-02 CONTINUED b~                            I OWG , -CN-02 SEGMENT CN-05 J:l B      ~

I ( TI C] I I 11 I I 38 I I I I D 1 I I CJ I 1 n-28

                                                                                ! I l I I I D I I I C><J 1-CN- 130 I~

CEHD = I 1 I I I I

                                                                                                                              ~

(FW-01) I I

                                                                                                                                                           ~

1- CN- 466

                                                                                                                                                                        -,fr- +l+-+ll-. -{><]-.*- **-s 1- CN-465 BC DWG 1-FW-02
                                                                                                                                                                                                                              ~

CON TINUED

                                                                                                                             'J
                                                                                                         ,c,-,1                 OHO L - - - - - - -           01-CN- 135
                                                                                                                                                                                        -I/~ ~               --w                -s   DWG 1- FW-02
                                                                                                                                                                                                                                        ~

CONTINUED FROM DRAIN COOLERS ~--****~~A BC FEEDWATER PUMPS RBI LEGEND: NOTES:

1. ALL MARK NOS. PRECEDED FW-01 1111111111111111111 1,111111 WITH 1-FW- UNLESS FW-02 * - - - *- *- - - OTHERWISE NOTED.

FW-03 - - - - - - - - - - 2. THIS DIAGRAM IS FOR UNIT 1, FW-04 - - - - - - UNIT 2 SIMILAR UNLESS FW-05 ---*-**-- OTHERWISE NOTED J, THE FEED PUMP OIL COOLERS, SEALS, & STUFFING BOXES ARE SUPPLIED WITH COOLING WATER FROM THE BEARING COOLING WATER SYSTEM.

4. REFERENCE 11 4-48-678, SH 1 & 2

5. REFERENCE 11 <<B-6BA, SH 2

6. REFERENCE 114-48-69A, SH 2 FEEDWATER SYSTEM DWG. 1-FW-03

e e TO ATMOS (TYP)

                        ~        I

(:- '- . - I I

                                                         . . -I.. r_ J____             I
                                                                                        ,...:i RV-101A h=~

tuF""m ATOMOSPHERIC DUMP

                                                                     '                     :J (MS- 19)

L VALVE

                *C><l l l ' ( t l l l l t l               ~I I
                                                                                                                                                                  -          ( OWG. 1-MS- 05
                                                                                                                                                                                  @=1ID CONTINUED
                                                                     ~ !s- s)
                                                          ~

• 2

 ~o~o:iCETRICTION                           " " ' ,_ " ' ' " " , " ,
- ~

(MS-01)

                   - ~
                                       ~                 @EiID
                                                                     ,    I
                                                                             ~

r. J-I PEN #73 I - - - - I (MS-22)

I I I

                              -~~t  I RBI LEGEND:

MS-01 L: MS-04 MS-07 MS-10 ----- ------- STEAM TO CN y----1c:a:Jf------ GENERATOR MS-13 --------- NOTE 1 1-MS-11 8 MS-16 - _ .. _ - _ MS-19 _ . - '~!-' *_tit 1111111 I II I I I I I- ,_ ~S-28) I r;_ r

                                                                                                                                                  - ~ DWG 1-MS-02
                                                                                                                                                                                 ~t~~

MS-28

                                                                                                                                                                                              -- -- *.:.:-:.~=

I 1-MS-NRV-1 028 SEGMENT MS-26 J-- I I HEADER 18 MS-29 - - - - - _ 1-MS-04 I MS - 35 ,,, 11111111111111111111111111

                                                                                                                                                                                                                 * - - : 1
                                         ~                                   I                                                          I      (MS-28) f ,_ - -

r;_ r

                                                                                                                                                     ~ DWG 1-MS-03 CONTINUED                             I                                                          I        1-MS-NRV-102C SEGMENT MS-27 I                   Q.jS- 25)
                                                                                                                             - - - _ ..J                          HEADER I C     NOTES:
                                                                                     -- -- -- - ~                   (MS- 28)
                                                                            '---                                                                                                 1* All  MARKUNLESS.

1- MS- NO PRECEDED WITH 1- MS-NRV-10; A - 2. THIS DIAGRAM S OTHERWISE NOTED SIMILAR UNLES~5cf1: UNIT 1,UNIT. 2

3. REFERENCE 11 ERWISE NOTED 448- FM-064A, SH 1 & 2 MAIN STEAM SYSTEM DWG. 1-MS-01

e e TO AlMOS (TYP) sv- SV- SV- sv- sv-1018 1048 1038 1028 1058 (MS-30) I I I I I TYP. OF 5 c-.. . - . -*- .. ~ r - J. - * -*-:i (MS-20) , (MS-20) RV-1018 h ATOMOSPHERIC DUMP 1' i@Bl}

                 ~{MS-36)          VALVE                                                                                                                             DWG. 1-MS-05

( @Bl} {MS- 36)

• I ~ TO GN (MS-08) I ~~~B CONTINUED C><J " tttl llllt ~ '111 I. Ill i (MS-26) r1--- . ~ ( M S~ 4) _ _ _ _ _ _@s:_14)~

FLOW RESTRICTION r- - -, IN NOZZLE I I , 1-MS-116 I (MS-02) (MS - 05) . - (M-S- 2-0) 1' I

          - -c:=J--- - --cJ- ... - -                                            - , ~MS:.11~ . -   -   -   (MS:i5~     ~::oa) - - - - - - - - -    ~

PEN #7 4 I (MS-23) r-, TV-1018 I I SG18 1-RC-

-18)                          ~~

I

                                      ~t I RBI LEGEND:

L....! MS-02 MS-05 I I MS-08 - - - - - -- - - - - - STEAM TO CN \---ce::J-----__J MS-11 ~--~--~--~ GENERATOR MS-14 - - - * - - - * - MS-17 , I I , lllllltlfl!llltl l !lltlllltt MS-20 -* * -**-**- MS-23 - - - - *- - * - - MS - 26 - - -- -- -- - MS-30 - - - - - - -

                                      ,.,r,,                                                                                                                           MS-36        1111111111  1 1 11111111,1111111111111 1-MS-04 (MS-23)

CON TINUED NOTES: (MS- 26) 1. All MARK NOS. PRECEDED WITH HAS- UNLESS OTHERWISE NOTED.

                                                                          ..__ -- -- -- _                     ;;l .     '  DWG 1-MS-01
                                                                                                          ~               SEGMENT MS- 28                               2. THIS DIAGRAM IS FOR UNIT 1,UNIT 2 SIM ILAR UNLESS OTHERWISE NOTED 1-MS-NRV-1028

3. REFERENCE 11448-FM-064A, SH 2 MAIN STEAM SYSTEM DWG. 1-MS-02

II TO ATMOS (TYP} sv- sv- sv- sv- SV-101C 104C 103C 102C 105C (MS- 31) I I I I TYP. OF 5 [ - '- - - - - *- - * ..J.. ,- - J- - - -*-:] (MS-21) , (MS-21) RV-/ ' ATOMOSPHERIC , 101C~ DUMP 1

                                                                                                                                                  %@BID

(MS- 37) VALVE

( DWG. 1-MS-05 I ~ ~~ic ~ TO GN (MS- 09) I C><l (MS- 37) '

                                                                , Cf,jS-27)

CONTINUED FLOW RESTRICTION 1- - -,I r1- -~ S -~5) _ _ _ _ _ _ :_-15~

                                                                                               ,          1-MS-155                                 I IN NOZZLE                                                '

s_:: o~s; 6)_ . _ ~s-~1)_ j _ I - _ <M,:.-1_:} L_ - - - =-- 0 ~ ~:=09) _ - - - - - - - _ J PEN #75 I (MS-24) I I TV-101C SG\C 1-RC-

-lC)                             ~~

I

                                        ~t .

I RBI LEGEND : LJ MS-03 MS- 06 I I MS-09 - - - - - - - - - - - - STEAM TO CN \---C8:J----------' GENERATOR MS-12 ------------ MS- 15 - - - - - - - MS-18 r 11 11111 1111 1 1 11 11111111 MS-2 1 ----------- MS -2 4 - - -- -- -- MS-27 - - -- -- -- - MS-31 - - - - - - J"" MS-37 111 II 1111111111 1111 11111 1111 1-MS-04 (MS-24) CONTINUED QJS-27) NOTES:

                                                                          ,                                   ,;'l *     '  DWG 1-MS-01

1. .AU MARK NOS. PRECEDED WITH

                                                                         ..__ - - - - - - - ~                              SEGMENT MS- 28 1-MS-NRV-102C                                                 1- MS- UNLESS OTHERWISE NOTED.

2. THIS DIAGRAM IS FOR UNIT 1,UNIT 2 SIMILAR UNLESS OTHERWISE NOTED

3. REFERENCE 11 448-FM-064A, SH 1 & 2 MAIN STEAM SYSTEM DWG. 1- MS- 03

e e e DVG 1-MS-01 (MS-22) CONTINUED (MS+-~:~ !(MS-::)__ _ DVG 1-MS- 02 (MS - 23) CONTINUED 2- - 1 I e 1 - (MS-23) 7j ,*~ " (MS- 32) - 1- MS- 178 I

                                                             ~    I

• I-MS-196 1-MS- FE c,,:i , , '

                                                                                       - ~ 1- MS

= PCV- 102B (Ms-,2)

                                                                                                    ,.  '= I J! 1-1-MS
                                                                                                         = PCV- 102A ,

I (Ms-33:i

..L... _ -

(MS-33) (TYP OF 4)

                                                                                                                                         , - ** ;=f,tMs- 3:)
                                                                                                                                                  --          I-MS TV-120 1-1-f:~---------

GOV- 005 (MS-~ 4 ) t -ce:::J R0-1 04 100 1- MS ~ TD- 9 ~

                                                                                    +,,
                                                                                           +
                                                                                                         =
                                                                                                         ~+  l-MS-10
                                                                                                                                                    '      L__

TDJkBfR TD!ll'llir 1- FV-T-2 flll AUXR.IARY STEAM GEIERAT!R FEED PIH' (HII- P- 2l 2--@J~ 11~11 C><J ~ r DVG 1-MS-03 t° -,  !- MS  :  : l- MS- 7 l- MS-348 VS- 18 ':;;;z  : L __ ~

                    -r~;ff1 (MS-24)                                                           l-MS- 270~       ~

l- MS- 331 j CONTINUED ~ 0 S-3~) ~

                 ~ ~;~                                                                                                                                     ...

1- MS- 8 (

                                                                                                                                                      )            (MS- 33) 1..1.J        R0 - 103 I- MS            (MS- 33)

J I-MS- 347 I

                                               ~-

TD- I

                                                             - -,s)- - -
                                                             !-MS/ I
                                                                                  -{><J-r- - --

l-MS - 341

                                                                                                                --{><}-- - -

I- MS- 316 RB I LEG END: VS-19 :

                                                                      ~

MS-22 MS-23 tn~~ (MS-33)  : MS-24

                                                                                                                ~ - - -:;;;i- - - -{><}- - - _J                                                      MS-32
                                                    ~    - ---Q-MS--3~~ ___             _J                                                I- MS. I VS- 20   ,

I- MS- 346 MS-33 I-MS- 342 I MS-34 K NOTES:

1. ALL MARK NOS. PRECEDED VITH 1-MS- UNLESS OTHERVISE NOTED.

2. THIS DIAGRAM IS FDR UNIT !,UNIT 2 SIMILAR UNLESS OTHERVISE NOTED

3. REFERENCE 11448-FM-064A, SH 4 MAIN STEAM SYS TEM D\.JG. 1- MS-04

                              ?
                                ~------------------,

I ~ (MS-38) .-------------....

                =-.7\           ~:J ___ ..J6. --,                                                 r- -D-- - ~               -- ~           --

HCJSTLRE SEPARATOR & REHEAT[R M0~~1ioc rc~-~ij,c DIIG J-MS-Ol (MS-16) c- -*--*-,I '~ --, i _= I-MS-TV-\ 1-HS-lV-3 I .- J:f;:

                                                                 ~

1 I I I 1-MS-E-IC CONTINUED

                                                      ~~           ,1                             :                   ~              Q (MS-38)
                                                      'f ~         I                              L ___ -       - -cL-      - - -{>I<}- - -

I .c I I I-HS I-HS MO!ST\Rl: SEPARATOR & REHEAT[R L, I I HOV-1000 fCV-1040 1-MS-E-10

                                           ~

ci I d HP TURBINE I

                                           ~                               l-TM-1-l               I I

L--..!-, I r .J I L------.J LP TURBINE ND 2 1-lt+-T-LP-2 I- 1 I '\' I DIIG J-MS-03 (MS-18) 2" - *- ,- *- ,.J I _,& ~ I

                                                                                                                      ~                    (MS-38)

(MS-18) I I ~~ I ~ r------- ~1-Hs -- ~I-MS -- CONTINUED ~ ""j "1 I f _.!, ~ MO!STLRE SEPARATOR & REHEAT[R

                                                                 ~~

MOV-JOOA rcv-100 \-MS-[-lA I I i.J6_ __ .J I I I-MS-TV-2 I -'- I L ___ _Jlo. __ .J I l_ --~ 1-MS-TV-4 I r- - _ c~ -~ 8) (MS-17) ,, .JI (MS-38) DIIG 1-MS-02 t"'- - "- 1 I I-HS HOV-IOOB I-HS fCV-104B MOISTURE SEPARATOR & REHEAT[R 1-MS-E-IB (MS-17)  : I CONTINUED I I

                                ~-~-

1 I r---------------- ---------.J I I LP. TURBINE NO 2 1-TM-T-LP-2 6 , I L-------------------------,

                             };                                                                                                                1§
                                       ~-- -Dr - - ~ - - ,::}- - - ,                                        r-- -q- - - ~               -- -f'.J- -- ~

7 i I I 1c0-~ija, L-;;S.--J I (MS-38) 0 0 (MS-38) I rc0-~ijaB

                                                                                                                          ~-- ~ -JI-MS TCV-107B I      7 I

I I I I RBI LEGEND MS-16 MS-17 MS-18 MS-38 ------------ I r- -, I I 5 -- ~ I-MS TCV-106A

                                                                   --.J I

I (MS-38) (MS-38) L-- ~ --0 : I I I-MS TCV-1068 I

                                       ~-    - - -t                       1- -   TYP  or 3)           <TYP OF 3J --t                          ~---J I

NOTES* 6 ~--~ --J L__ ~ __ 9 6 I. ALL MARK NOS. PRECEDED 111TH J-MS- UNLESS OTHERIIISE NOTED. 2 THIS DIAGRAM IS ,OR UNIT !,UNIT 2 I-HS I I I-MS TCV-IOSA L. - - ..J 1CV-J05B SIMILAR UNLESS DTHERVISE NOTED J REFERENCE ll 448-FM-064A, SH 5~6 1-CN-SC-JA 1-CN-SC-JB CONDENSER CONDENSER MAIN STEAM SYSTEM D'w'G, l-MS-05

e (NO SEGMENT) e Ji-RC-107 (RC-30) (NO SEGMENT)~ HCV-1201 - I

                                                               ~

(RC - 30) (RC-30)

                                                                                                        --= - -

1- RC-11 (8B2)

                                                                                                                                    --,                                                        D\iG. 1-Rc-01c SEGMENT RC - 29 )

c...._ 1_-..Rc. -. 82 (RC-30) - I D\iG. I - Sl -OIB DWG 1- CH - 018 ui SEGMENT ECCS-05 U1 (NO SEGMENT)

                                ~1 ;_~                                                                                                                                                      {-,1-91                                                             D\iG. 1-RC-O!C SEGMENT RC-33 J~                                       ;u         F                                                                     MDV-              , ::,:

I (RC-10) ~(RC-37)

                                                                      '  ~ :~ 6                    I  ~                     (RC - 27) :    H         ~1590                                     I
                                                        ~                                                                                                                                      I
     ~    -&*--*---
      *I ~ C- 07)                   I                                 '
                                                      ** ,. .J ****** -..J..)1
                                                                                                        \          (RC-04)
                                                                                                                   .. I***

CRC-04)

                                                                                                                                     .J. 1.

• l.,!I  ;

                                                                                                                                                                            ' CRC-20)

I** ,** *-1(RC-16)

                                                                                                                                                                                                         -~
                                                                              ~ (RC- 07) STEAM                                                'CRc-21)       ~ ( RC - Ell)                 DWG I-ACC-OI        I REACTOR COOLANT                                     I              ~--                       GENERATOR                               I
                                                                                                                                                        =
                                                                                                                                                     ~'" ""~
                                                                                                                                                                              '"                 It SEGMENT ACC-01        I
                                                                                                                !"~-~ -~~;!~t£f=I;;;~::. *-*-* ~
     = PUMP P-IA                               (TJC- 3<)

E- lA I

                                                                                                                                                     '                             1-s,~,                      I
                                                                                                      ~
     ~       (RC-~
     - --- --0 L!J         LOOP A
                                                                                                                                  ~

T '. t~ I '""\! 0 .. -=,:::;- . 0

                                                                                                                                                                      'M' I

I LOOP C HOT LEG DliG. 1- RC-OIC SEGMENT RC- OJ Ht I 11111 II! 111111111111 11111 Ill ltl, 11 I Ill 1111111111111111111111111111 111111111'11111111 I I M 111111 (RC ~2D: $ ~lf(RC-41) 1'1111111 1::k:l .... . . r:*'~ ~ 0 LOOP C COLD LEG D\iG. 1- RC- O!C SEGMENT RC - IS

                                                                                                                                                  ~-1~~1            13
                                                                                                                                                                        )     . (RC-40) :         ~

D\JG, 1-CH-O!A (

!:(RC- 40)

                                                                                                                        ~            *  ---c><J-- *

• _J I I

REACTOR VESSEL VENT DIIG 1- RC- OIC SEGMENT RC-SO SEGMENT CH-24 J LCV-1460A I RBI LEGEND: I

                           -           CRc- 3 o) 1- RC - 50

( DIIG. 1- RC- 018

                                                    * - --->.,)SEGMENT RC - 28 (RC-44) :
                                                                                                                                                                                       "'O n

I RC-01 RC-04 RC-07 RC-10 I 11111111 Ill

                                                                                                                                                                                                                                                                          ** r** i-1*

1111 1111 111111 RC-13 -**-**-**-

                                                                                                                                                                                       < I RC - 16     - - - - - - - - -

RC-20 ---------

U1 RC - 21 - - - - - - - - - NOTES: U1 RC-24 - - - - - - - - - - -

1>

RC - 27 - - - - - - -

1. ALL MARK NOS, OF MAJOR COMPONENTS D\iG. 1- RC- 018 RC - 30 LOOP B HOT / COLD LEGS PRECEDED 'v/ITH I-RC- UNLESS SEGMENTS RC - 02/ RC- 14 RC-31 - - - - - - - - - -

DIJG. 1-RC -01 B DTHER'v/ISE NOTED. RC - 34 - - - - - - - SEGMEN T RC- 32 RC-37 - - - - - - - - -

2. THIS DIAGRAM IS FDR UNIT I, DIIG. 1- RC- 01D RC-40 -*-*-*-*-

UNIT 2 SIMILAR UNLESS SEGMENT RC- ~! RC-41

• 1- - - - - - -
• DTHER'v/ISE NOTED <NOTE* SEGMENT RC - 78 IS ON D\JG 1- RC - O!Dl RC-44 RC-46 3, REFERENCE 11448-FM-086A, SH I RC-66 - - - - - - - - -

11448-FM-083B, SH 3 RC-72 RC-75 , """" "" ""' "" ""'" RC-90 - - - - - - - - - - - RC-93 - - - - - - - - - - REACTOR COOLANT SYSTEM D'v/G 1- RC - OlA

e e LOOP A HOT LEG DWG. 1- RC-01 A SEGMENT RC-01 LOOP C HOT LEG DWG. 1-RC-01 C SEGMENT RC-03 L LOOP A COLD LEG LOOP C COLD LEG DWG. 1- RC-01 A DWG . 1- RC-01C DWG . 1-RC-01A SEGMENT RC-13 REACTOR SEGMENT RC-50

                         ""t DWG. , - cH - 0 1B      SEGMENT RC - 30                                                                                                       VESSEL R-1                            ,-~~-,,,REACTOR VESSEL VENT (NO SEGMENT)                                                                      (RC- 28) tll I
                                                ~I
                                                        ~~gME~TR~c~1~ 2                ..... *1 l-RC- 50                                                            DIIG I-SJ-OLA SEGMENT ECCS- 06        I DWG . 1-RC- 0 1C SEGMENT RC - 50 Lfl I
                         ~u                     Bi=                                                         ,, - * ~

II~ (RC- 38) ~ ~

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I I I NOTES, a ~-@-, ~ l I I I  ! 2--1 mt- X ca, I I I L AL L MARK NOS. OF MAJOR COMPONENTS PRECEDED \./ITH 1-RC- UNLESS ( RC- II)~

    , G, t (RMB)      (RC-32) I   I            ~     ~Rc- ~7)       (RC- 05) (RC- 28)   I      (RC-tc **z,** ,** ,**                     (RC- 17)
                                                                                                                                                                             ,.J I  I                 OTHER\./ISE NOTED.

2. THIS DIAGRAM I S FOR UNIT 1,

                  ,. ,. ,.1 ,* * ,. ,. ,

(RC- 08)

                                             ,. ,. ,.,1. ,. ,. ,. 1. ,L. ,.J-
                                              , RC- J L -t:a::J- _ J   (RC- 08) STEAM
                                                                                             ...... ~ . - ~
                                                                                                    , (RC- 64)        __ ;               (RC- 02)

I I UNIT 2 SIMILAR UNLESS OTHER\./ISE NOTED I REAC TOR COOLANT

PUMP P-18 I~

                                                        ~                   GENERATOR E- 18    (RC-64)~

0 (Rc-22

                                                                                                                            )   -'Jl(RC- 76)

L DIIG 1-Acc- 01 SEGHEN1T ACC- 06 I I

3. REFERENCE 11448-FM- 086A, SH 2 I (RC-94) I :t r- - ~ - - - - -,

                                                                                                                                      ~                i                                              RBI LEGEND :

1

' , Ci) L!J (--1 (RMI ) (RC- ?J) (RC-76) (RC- 76)  :

RC-02

l-RC- 48 (RC- 76) _..l...

_ l- SI- 130 I RC-05 LOOP B 0 -r- 0 RC-08

• r* 1* a 1* 1* 1* 1* 1*

I i'*****------------------------------------** ": M <!rn)~" Oc-<e) i~~, i i I (RC- 47) I (ot-<>J J: RC-11 RC-14 RC-17 RC-22 RC-25 (RC- II) MOV-1593 ( RC- 14)- - - ~ - - '- *1 (RC- 49) RC-28 RC-32 RC-35

                                                                                                                           ~ ,<Rc- 42>,                                                               RC-38 01/G I-SI-OJA SEGMENT ECCS-02 ~ --~

l- SJ-82 t RC-42 RC-47 RC-49 RC-62 111111111111111111 llltlll\1111111111 !\ !I RC-64 RC-67 RC-73 01/G 1-CH-OIA RC-76 SEGMENT CH- 41 RC - 91 RC-94 REACTOR COOLAN T SYSTEM Dw'G. 1- RC - 018

e D\./G, 1-RC- OlD D\./G. 1-RC-OlA J:i: SEGMENT RC-19 J CONTINUED SEGMENT RC-30 1-RC-82 D\./G, 1-CH-OlB ll*I ( DVG, 1-RC-OIA n (NO SEGMENT) r-- - ., ]SEGMENT RC-30 < QlC-29)

                                                                                                                                                                                                                                                                             ~                              ~

I QlC- 33) I DWG 1-SI-OIA

                                                                                                                       ~ 1!                                                                                        ~ --- - --, :                                                                           ~

SEGMENT ECCS-07 I -SI-94 ~ ~(RC-68)

                                                                                                                                                                                                                        ;: -@ - ~

1 I g~ --D-S QlC-39) n

(RC- 18)

(RC-18)

(RC- 19) I 1 1 (RB:J) :

                                                                                            ?l           (RC-03)

MDV-1594 (RC-06)

                                                                                                                                                                                                                    *~
                                                                                                                                                                                                              , k~)~ ~                    ~     436 IQlC-33)
                                                                                                                                                                                                                                                                                                         ~

(RC- 39) 1 (Ri::o:9)@ ~C-l ) 2

                                            ~-               - - 1_ ---

Dl.'G 1-Acc-01 SEGMENT ACC- II Dl.'G 1-sI-OIA

                                                           ~                    SEGHENT ECCS- 03
                                                                                                              ~ et-' ~ * * =
                                                                                                     - - ' ---icx::i-
                                                                                                                      ~

I

                                                                                                                                                                              =

• 1 (RC-09)

STEAM GENERATOR E-1C

                                                                                                                                                                                                               .. - ~- f.

• 1* 1* - - l* l~ 1* 1* 1*
• 1'*

L .-c::a::J- J

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                                                                                                                                                                                                                                                                              ..L I

I QlC- 36) a

• 1 I~

REACTOR COOLANT I PUMP P-IC I I I I QlC-48)

                                                           "'~l- Sl-147I                                         ;"

~

                                                                                                                                                   ,, .        "' :                t
                                                                                                                                                                                   * (RC-74)                 QlC-92) *~-(                                              LDD p C r-r\._
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                                                                                                                                                                                                                                                                                                                      ~ **-I LOOP A HOT LEG                                I                                                 :                                   ~                             *            .... *                 -I ----)                                                                                                   I    ~)

D\./G. 1- RC-OlA SEGMENT RC-01 I I l-S[-85 ~ ~ I L - - - ....-H I l-RC-103 0 - 0 7 * '-1 I QlC-43) _ I ... ~ i _L I I ~ ~');(' * .... . . , (RC-26) : +Jru-i I LOOP A COLD LEG (RC-03) 1 ('JlC- 48) I ('JlC-43)

                                                                                                                ~

(!lC- 23) IV --i!iJ I I D\./G, 1-RC-OIA SEGMENT RC-13 ,I QlC- ll *S) !~- 4 11*

                                                                                                - -(RC-15)  !I - -                   -----------------------------------------~

(RC-12) I MOV-1595 RBI LEGEND* I (RC-87) I L -- - ** - - -c-::1- *- *- *- *- *~ RC-03 VESSEL (RC-50) I (RC - 70) L- RC-104 L- RC- 173 (RC- 50) [fil (RC- 88) RC - 06 RC - 09

• 1 - 1* 1- 1* 1*

R-1

                                       '.     ;~llllll!lllillllllllll!Hlllllllllllll!l I 1111lltl/!ll11111111!1!11111111Htll!llllllll\!l!lltlill111tll!lllll!+llllllll1!1t!ll!l1!1!H!ll111!1111Ulll1!!11(:::8::] 1111111111111!ltlllllllllll!;illlllllllfllll ~         -      -    -                                     RC-12   - * - * * * * * * -
                                         \                                             I                                                                                                                                                           SOV - !OOBI                          SOY-I OB2                         RC - 15  -       -     - ,* 1

• 1 -

                                           ,( ~ )

I =

                                                                                                                                                                                                                                        ~ (Rf}o)
                                                                                                                                                                                                                                                              ;t_           (RC- 89)

RC - 18 RC - 19 RC - 23 RC - 26

                                             \                                                                                                                                                                                          ""'""s'ov-100A1-                       -      - sov -1 aaA2                       RC -29   -       -     -       -     -     -

RC-33 - - - - - - - - - -

                                                                                                                                                                                 ~

08

                                                                                       ~~.:~.~~*~ce::J ~R7~~              !'                                 '~ L-RC-157                                                                                                                                                  RC-36    - - - - *- - - -

I L-RC-105

                                                                                                                                                                                                                                          REACTOR VESSEL VENT                                                           RC-39   -------

RC -43 - - *- - - - ,- - RC - 45 - - - - - - - - -

                                                     **                                I                                                                                                                                                                                                                  REFUELING       RC -48   - - - - - - - -

CAVITY RC-50

                                                       \                               L_ -- --                                                               --                                                                                                                                                          RC- GOA ************************************* ***

NOTES* RC- 608 LOOP B HOT /COLD LEGS ', I RC - - - - - - -- D\./G, 1-RC- OlB l. ALL MARK NOS. OF MAJOR COMPONENTS RC- 65 - - - - - - - - - SEGMENTS RC -0 2/RC-14 PRECEDED VITH 1-RC- UNLESS RC - 68 - - - - - - - - i~ OTHERVISE NOTED. RC - 69 - - - - - - - - - - 2, THIS DIAGRAM IS FDR UNIT l, RC - 70 - - - - - - RC -74 UNIT 2 SIMILAR UNLESS

                                                                      ~1 RC-77 OTHERVISE NOTED                                               RC - - - -                 - - --

3. REFERENCE 11448-FM- 086A, SH 3 RC - - - - - - -

RC - - - - - - - RC- 88 - - - - - - - - - 1-RC- 603 D\./G, 1-RC- OlD RC - - - - - - - SEGMENT RC - 51 RC - - - - ~ SEGMENT RC - 79 ON DVG 1- RC - O!Dl RC -------- REACTOR COOLANT SYSTEM DVG 1- RC-OLC

e e r - - - - - - 1

                                                                                                                    -.£"'

I Dw'G 1-RC-OIA Dw'G 1-RC-OlC SEGMEN T RC-44 SEGMENT RC - 45 RV-1721 RV-1859 PCV-1473 RV-l203 I I (FC-56) I PRESSURIZER RELIEF TK. (RC-61) I

                         ----- -   --      I TK-2 TD PRIMARY DRAIN L - ~ ~ - - - - ~ ~ ~ ~ ~ ~~ ~--\TRANSFER I

n HCV-l523 TANK

                        <l-              p          @c -5 7)       I             MOV-1536                     PCV-1455C                        RC-54 I

(Rc-71) , r --c><J- R I RC-55

                                                                                  ~7~ I           t!'~~)----l><J-A ~

E RC-56 r I s RC-57 I (RC - 71) s RC - 58 u 9 ~ ~

                                                                                        ?I-'~ !'           r*-1. __T__ -~~

R RC-59 I RC-61

                               '--                                   z                                                                                                     RC-71 E                                                                                                     RC-78 R                                       SOV -IOIBI @C - 84)     SOV - lOIAI I                         RC - 79
                                                                                    - - ~        @c - ss) t      s                       s       1 @c - 86)                RC-82 RC-83 L.                                  _J                          RC-84 SOV- l01B2              SOV-IO!A2                             RC-85 RC-86 Dw'G 1-RC-OlC SEGMENT RC-19
                            ~ -- -- -- -- -- _ _J                                                                            l__J CONTINUED                                                                                                        REFUELING CAVITY REAC TOR COOLANT SYSTEM            1-RC-OlD

_f}_ CCV) c)CC\./ r 1

                                        ~

ccvC,---~ RHR PUMP P-lA

                                                   -w*-~*~ ;           ccv              i l

TD SS r -c><J-JS

                                                                                                                                                                            -<><Jo 19 DIIG 1-RC-OIA
               ~* """
             , AC!!R-o~

1 CRE::::QJ)

                                                      ,1.'.'l,                          ~ - ~ - - - - - -, -            1
                                                                                                                                         .J I                   RHR HEAT EXCHANGERS I

L, j @Em I , D\.IG 1-CH-OIA SEGMENT RC-20 ~ *- .~ BYPASS FLO\/ /1 _I* ~ -I><)- ; C~SEGMENT CH-28A MOV-1701 I CONTROL VALVE \JI I I . FCV-1605 r - *- H!N IFLOl,I RECIRCUL ATION ,LIN[ * -  ! - - * - - *- - * - - * ~ I

                                   . C))8[)                                           I                     CR!El]) I                                                                       I I                                                    I                                                 !I   CC\./ = £ 1 : CCV E-IB I                                            I I                                  RH FLO\/

I CONTROL VALVE L. -c><J- - ' ' - ' -<><Jo - ' J 20 24

                                                                                                                       ! -l,_                                                               ..J r  HCV-1758 (n\ _L
                                                                                                              \@I -,-

1 I r SEAL RV-1721 CRlEID

• COOLER NOTES*

RH::jj 'l- " - " - ".Jli <REE[]l) PEN # RI/ST RETURN 1 ALL MARK NOS PRECEDED LINE ISOLATION VALVE \IITH I-RH- UNLESS 24 CSE[ NOTE zl OTHER\IJSE NOTED TD PRT i- "-++ ,- ""IL)- , - * .. 4 -) TO RI/ST 2 THIS DlAGRAM JS tOR UNIT I, 1-RH-29 CR!EID l-RH-100 UNIT 2 SIMILAR UNLESS OTHERIIISE NOTED FROM 3. MDV HAS BEEN ELECTRICALLY ACCUMULATOR B DISCONNECTED AS PART OF I DCP 92-049. rn ss ~ ---------- ..J CRE::::QJ) A CR!EM). DIIG 1-ACC-01 4. REFERENCE 11448-FM-087A, SH I 28 CREER) CR!ElE) I ~,-;;o?i1,i'o'~'""""f":" L-S SEGMENT ACC-06 11448-FM-087A, SH 2 11448-FM-0898, SH 2, ~ 3 I ' I ' RBI LEGEND 1~~ RH-02 RH-03 RH-OJA RH-038 RH-08 l!t!l!IUlllllllllllllllllHIIUHJUUIIIIIIIIIIIIIIUI ! CR&]J)

                                                                                                                                       "'*-*~- r I
                                                                                                                                       .         A MOV-1 7208 RH OUTLET MDVS CR1E FROM ACCUMULATOR C DIIG 1-ACC-01 SEGMENT ACC-11 RH-09 RH-10 RH-II RH-12 RH-13 RH-14 RESIDUAL HEAT REMOVAL                          D\JG.                  l-RH-01

REACTOR CONTAINMENT (RS-09) _.. ,::- - - ,:: '!:I\ - - ... _ A ..,.._ C... RS RING HEADERS AND NOZZLES CTYP)

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FROM - S'v/ - SYS (TYP) r ....I ~1!11!1!11111/ttl 1111111,

                                                                                               ....I                                                       +11m111111111111 lB                        lD         RS         lC                                         lA 1-RS-06 PEN. II 70                     CEBD COOLERS I
                                                                                                                                                             ~111111111   11

( RS - 07) - - - - - - l I I ..1 I I P-2B I TD I~@s~o~ro T I r _!s~ o:.A) A L-~~ Mov- ~ Mov-156B Jl - _J I I I t\1 Ill!;! S'v/ SYS (TYP) REMOVABLE .ilillil._ 155B I SPOOL PIECE

• 1-RS-15 --RD-111B 1RD-lllA (TYP)

I (RS- 0 8 ) ~" """ "" """"""~ I I I (RS - 04A)A

                  ;::.\;:><J , , 1' II
                                         @J '" 111""""""""'   "" , , ,Q , ,

(RS- 04B) MDV- n;.,=-=--1~ _ _ _ _ _ _ _ ..J MDV- 156A , ~~~ I 155A P-2A PEN. II 71 CEBD L - ~ OUTSIDE RS PUMPS FROM ~ r@ "" C~s-12) P-lA fl ptl P-lB I INSIDE if I! I I

                                                                                                        =IT)         I RS PUMPS PEN. II 67 (RS-03A)
                  ~      - - - - -               --- - -                                          I I

CONTAINMENT SUMP I  : (RS-05) L - - - - - - - - - - - - - - - - _I _ - - _J NOTES: RBI LEGEND, I. ALL MARK NOS. PRECEDED RS-01 - - -- -- -- - WITH 1-RS- UNLESS RS-02 -*-*-*-*- OTHERWISE NOTED. RS-03A - - - - - - - - - RS-03B - - - - - - - - - - - -

2. THIS DIAGRAM IS FDR UNIT 1, RS-04A - - - - - - -

UNIT 2 IS SIMILAR UNLESS RS-04B OTHERWISE NOTED. RS-05 -**-**--*-

3. FLOW PATH SHOWN FDR RS-07 - - -- -- -- -

ACCIDENT MIT!GATIDN RS-08 -*-*-*-*-

                                                                                    <CONDITION I V ONL Yl                                                              RS-09           - - - - - - - - -

RS-10 - - - - - - - - - - - -

4. REFERENCE 11448-FM-084A, SH 1 RS - 11 - - - - - - -

11448-FM- 084B, SH 2 RS-12 111111wu1 1111111mum11111111111111111111111111t111111111111111 RECIRCULATION SPRAY D\./G. 1- RS - 01

NOlES J ALL MARK NOS PRECEDED

                                                                                                                                                                                                                                      \JllH !-SI- UNLESS DlHER\JISE NOTED 2 lHIS DIAGRAM JS fOR UNJl UNJl 2 SIMILAR UNLESS OlHER\JISE NDlED SYSlEM SHOVN IN RECIRCULAl!ON PHASE 10 CLOD LEGS (HHl-02)~                                                                                                                                                   CONDJl!ON IV [VENlS

_ _ Il',JG 1-CH-OIB r 4 Rff[R[NCE 11448-fM-089A SH I

      ~

(ECCS-00) - I

           ,~s~oo)
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1-s1-410

                                 *        -~

(HHl-01) (HHl-02) 1-51-25

                                                             ,.   -t I
                                                                                    !-CH-MDV-11158 SEGMENT HHl-03 RBI LEGEND:

I L (H~l-02) A r D\JG !-CH-018 I I - - '~ SEGMENT HHl-03 ECCS - - HHl-01 -- * -- * -- 1-CH-MDV- HHl-02 - - - - - - I L lllSD LHl-01 LHl-02 t F:~ LHl-0~ I IIIIIUl!Ut!Ulltlll!llllltllltlflll II I LHl-04 -**-**-**-**- LHl-05 - - *- ** ** ** - LHl-06 I lllllllltllllllllllHll!UIICUllllllll\ LHl-07 - *- - *- ** ** *- ** . . . . HYDRO TEST ~W', D\JG l-CH-018' SEGMENT LHl-18~ A (LHI-OB) LHl-08 LHl-11 LHl-12 LHl-1~ PUMP R V S T ~ o~ MOV-JB63A LHl-14 --- * -- -- P-2 LHl-15 - - * - * - * - * - TV-Sl-1028 , A (LHl-07) LHl-16 LHl-17 O\JG. I-CH-018 ~ S[GM[Nl HHl-03 MOV-18638 rR4~A (LHl-17) (LHl-16) (LHI- 14) (LHl-08) i (LHI-OB)A (LHl-12) (LHl-12) r '- - '- ' *- - *~ -----

                                             - ro  UNil 2
                                                                                                                                                                               -----        -r- -     -!><I ,               c=i          ,       ~(                       D\JG I-SJ-018 ACCUMULATOR MAKE UP LINE

• MOV-18850 MOV-1885A 1-Sl-61 I *  : MDV- PEN ij6Q l-Sl-229 .) SEGMENT ECCS-0 4

                                                                                                                                                                                       ! l I           1B90A TD UNll I
                                                                                                                                                                                       ! : I ACCUHULA TOR MAKE UP Lllf.:

A-(ECC~Hl-02)&

                                                                                                               ' l-Sl-46Ai P-lA
                                                                                                                                     'J (LHl-02)
                                                                                                                                                  ,, -    ,, ~ -~I(LHl-08) l-Sl-58
                                                                                                                                                                                 ~-~-.!.J ____ _

(LHl-08) MDV-D\JG 1-SI-OIB SEGMENT LHl-09 J864A

                                                                                    ,-                                          1-51-56 (LHl-04) A                 =                                              F I

L - - - - - '- - - - - - - - '- - *- '"" S- **- ** :..tx:J 11111<i.( LHI-06) MOV-1860A LHSI

                                                                                                                                                                         ~

945 I I I ([)<TAINM[NT SUHP )"'~~::.~.?(..~ - i-_ (LHl-05) PUMPS

                                                                                                                                               ~

946 t j MOV-18608 (LHl-07) (LHl-07) TD RVST c__ (LHl-17) _J IL i I (ECCS-00) 1 47 Gr - - ~ SI ~

                                                                                                                                                                        .1'i I~* ,.J. _,,. ,+-iii_.'A_   _             ~~2Mt ~i !

1 1 1 SEGMENT LHJ-17 1 '- - '- 'I f ' - '- '- r.:, , V ___,,_s ~~ 1 09 CONTINUED I Mov-1s62B

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1-s1-4ss P-JB l-Sl-50

                                                                                                                                                                                 ~~;c i

f MDV-18648

                                                                             ~                (LHl-17.) A                (LHl-15)    A       (LHl-13)          (LHl-07)                       l (LHl-07)A~                             ~

l.... , - ,_ - * ......... , - ,- , ....._ ** ~ *- ** ** * ,. ,. ,- ,. ,i,,- ,-l><). .. . ... ,, -c:=J- ,, * "* "* "~ D\JG 1-Sl-OIB MOV-IBBSC MOV-1885B 1-Sl-53 MDV- PEN #62  !-Sl-228 SEGMENl ECCS-04

                                                                                                                                                                                                       ]8908 SAFETY INJECTION SYSTEM                                          D\JG. I-SJ-OJA

0 - 'T*-*-*-*, (>+<1-!0) 18&7C l ' O'JG. 1-CH-OIB SEGMENT HHI-OQ T

                                                                       ' - - - - - , -----_.L-        -{)<J-MOV -

J Q PE N II 7 18670 . (HHHl) f

                                                                                                                                            ~    l-S]-225                     .... ELOCll IN (1-til- lZA) '

I- - -c><>- mP

                                                                                                                                                               ~ -<><>--------~

r Tl<<Olll( D POSll lON

i, (~l-l 2

S) (CCCS-Oi} ([tCS-00

                                                                                                                                                                                                                        -*'!**--*--*--*--*--*--*--*--*--*~~ttH[tfCRf~~l I                ~1-Sl-340                                        1-Sl-235 :                                                 I-Sl-79 I                _/[J),_                          (l-*o-12C)          ([ccs-oa                                    ¢:ccs-02) ....G... '         ( D\IG l-RC-OJB r-      ~         ~                   ~                 -~                 '"T *- *- *r _ ,_ ,_,_                       - , -,_:---r::--,S[GM[Nl RE-42 I                              J-Sl-338                          J-SI-236    :              _                               1-SJ-82 L                _/[J),_                          ~ - ~                                     I                     m£D_.!il..          , _ _ _( O\.I& l-RC-OJC I
                                                                                                                                                 - ~~

1-SJ-336 I-SI-237  !

                                                                                                                                                                                   -<><J "'""'""'f's.J- - - - - - - - - T - -
                                                                                                                                                                                                                                          ~                  I
                                                                                                                                                                                                                                                                      - -;,. ~ S [ G M [ N T RC-43 l:SJ-8:5 (l+H-12A)     I                                                                             !                                 I f
                                                                                                                                            ~ ]-Sl-224 II
                                                                                                                                            ~    (HHl-1 4 )                                                                :                                  I D\JG  1-CH-OJB S(GMENl HHl-09 0      P[N  '2l 1-Sl-241 lCillHJ} !~
                                                                                                                                                                                                                          .I; !-Sl-242....,   J-SJ-243~

mEQ)

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P[N #c'J {HHI-16) {HHJ-17) (HHl-18) ~ PEN *113

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                                                                                                                ! l ll 11 IL! 11111 I IF It 1111 t 1111111 ti 11 I 11 t I I LL 111 ti 11 t ti I I JI I I 1111 I I H:;::I f 1111J1114111 t 111! 11 t,t
                                                                                                                                                                                                                                                       =
                                                                                                                                                                                                                                                        =  -

NOTES l ALL MARK NOS PRECEDED VJTH 1-Sl- UNLESS OTHERVlSE NOTED THIS DIAGRAM IS FDR UNIT I, UNIT 2 SIMILAR UNLESS I OTHERVlSE NOTED SYSTEM SHOVN IN t RECIRCULATJON PHASE TO CLOD LEGS l~: '.: :~ COND1110N IV [VENTS

&~ 4 REFERENCE 11448-FM-089A, SH 3 JJ448-FM-089B, SH 4

                                                                          ~            : mE :

I I RBI LEGEND* ECCS-01 -- *-.,-- ,-- --*--*-- *-"'- P(N 11£,0 t-SI-229 ECCS-02 - - * - * - * - , - * - *- DVG. J-SI-OIA ~ L 1 (E~~;:~)- ', , ECCS-03 _ - SEGMENT LHl-12} - L__.1 ECCS-04 _ ,, ECC S-05 1111111rn111111nu1mnm11m111111111111umm11111u ovG i-s1-01A ( A ccH_::-o: = ' ,- ~ <Eccs-o4> (Eccs-os) o""u I-RC-DIA ECCS-06 ------------ S[Gt,<(Nl LH I-09 ~ O _ -, ~ I ' - * - ** - , - ,, - ** - '.! - ,, - ,, - ,, - ,, - ,, -

• Jr-.....j 11111111111111111111111111m1~ L___! SCGMENl RC-16 ECCS-07 - - , - - ,- - , - - , -

M V 1864A I I -- J l  :- (ECCS-04) 1-Sl-239

                                                                                                                                                                            ~

1-'S1~1

                                                                                                                                                                                        ~ L--..( D'wG 1-RC-OJB
                                                                                                                                                                                                                 )

HHJ-10 -*-*-*-*-*-*-*- tI RV-18458 l f 1-- ** -

                                                                                             ** ** -     ** - ..i.* -
                                                                     '- ** - ** -'*- ** - ** - ** - *~- **~
                                                                                                           ~
                                                                                                                        ** - ** - **~

l-Sl-238

                                                                                                                                                              **--** ~
                                                                                                                                  *- - *- - *- - - .l~~-::! ,- ~
                                                                                                                                                                         ~

1

                                                                                                                                                                                                        ~

l-Sl-88 0

                                                                                                                                                                                                                      )SEGME NT RC-17 1

r~tMc ~}CRl~?e HHl-11 HHl-12A I b  ! G:iiB1) ~  :: l-Sl-240 <1TI£@ J-S[-94 HHI -l 2B HHI -J 2C L '.I'. - - i - - -

                                                                                  -   ::0 CJN HOV-I I~                                                                                                                                                           HHl-!2D HHl-13              *_""""'""""'"""""'

O'w'G. l-Sl-DIA t A 9 (bHl-0 ) 1890C HHJ -}4 SEGMENl LHI-07 ~- - PEN

• 61 HHl-15 IIHIUHIIIIIIUllllllLIIIIIIHUl11JUtUHIIIIIUIIU!UL 18&48 HHl-16 -- *-- *-- * -- *-

HHl-17 ---------- HHJ-18 - * - *- *- , - * - * - *- O\JG 1-S I-OJA ~ 2:[~~:.:~~)- ,,J LHJ-09 LHl-10 sEGMENT LH1-11) L......--J ,-Si-22s 11111111111111111111111111111 1 SAFETY !NJECTJDN SYSTEM DI.JG. 1-Sl-OIB

(C',/ SYSTEM) DISCHARGE TUNNEL D\t'G, 1-S',/-OIB D\t'G, 1-Slt'-Ol B D',/G, 1- Slt'- OlB D',/G, 1-Slt'-OIB SEGMENT l-S',/-22 SEGMENT l-S',/- 23 SEGMENT l-S',/-24 SEGMENT l - S',1- 25 l,l t-BC-E-lAi (S\1-14) (S\1- 15) 1 UNIT l (TYP OF 3) : (TYP OF 3) 1 FRON BEARING CONTAINMENT I CODLING SY TE r - -{X}--J I (S',/- 11)  : (S\1-13) , P-6A I-BC-314 I I-BC-E-IB 11 I I i I CTYP OF 4) r - - - - --c><)--l I I I I I 1 CTYP I OF 4l j I

                                                                                                                                                                                                       ' CX} *.               -~*-. ..,- ..                            FROM HEATING SY TE l-HS-104 I              1                     I      I         I
          ;,.,, I I                                                                                           ~                                    Y><r ,           I I

1 I P-6B i FROM PIPE TUNNEL

                                                                                                                                                                                                       ~                                    I I

[... - - - - --c><)--l I I l C><l~-- .... .......,. I I SUMP PUMP l-DA-117 11 t- BC-E-lrn I 1 I I I I FROM CONDENSATE I I I I

                                                                                                             ,-....{>4-l BEARING CODLING \/ATER LC><r .J         I I

I i P-6C

                                                                                                                                                                                                                                                                ~

iI I HEAT EXCHANGERS I

                                                                                                                                                                  }----- --c><)--l I

t C><} ._.., *. 1 I I I I I I I REC!RC SPRAY I P-6D

            ~ ""' '~"'"" L ___ .;,_-* -~

I I I I [... - - - - --c><)--l ,. C><J ** r- - ---  : COMPONENT CODLING ',/ATER 1 HEAT EXCHANGERS

                !                                   @p                                                                                                             I L--------,             I I

FROM CONDENSATE POLISHING

~:;;, 'r~,,_,,,

I C SYSTEM

                  ~r r ~r I
                  ~ ~ (S',/-16)

D\t'G, l-C',/-02 ( A (S',/-ll) SEGMENT S',1-09 '--;------,!><}- - - - - - - - - J MDV-102A  : TO UNIT l Il',/G. l-Clt'-02 D',/G, I-C',1-02 A (S',/-11 ) 1 (Slt'- 12) TURBINE BUILDING ( Il',/G l-S',/-02 D',/G, l-C',/-02 SEGMENT S',1-08 SEGMENT Slt'-07 DE\t'GGM,ENl-TC',/S',/-~210 -..<)-----1><}- -------- .l. - -[><)- - - - - - "") SEGMENT S',/-12 D\IG, I-Clt'-02 S MOV- 102B 12 CONTINUED SEGMENT S\1-08 SEGMENT S',1-07 RBI LEGEND SW-11 SW - 12 SW-13 SW-14 SW-15 NOTES* SW-16 1. ALL HARK NOS, PRECEDED SW-17 ',/[TH 1-S',/- UNLESS SW-18 DTHER',/ISE NOTED. SW-19 2, REFERENCE IH48-FH-071A, SH 2,3&4 SW-20 SW-21 SW-28 SERVICE ',/ATER SYSTEM D\IG, 1- S',/-OlA

                            <Clv' SYSTEM)                                          DISCHARGE TUNNEL I
                                                                                                                                          , (SV -26) r - -*- - - - - - - - -

1111111::11111111111111111 111,i

                                                                                                                        ,_  - ~lv'_- <:_6 ) ~ ~~~~-- -* - ,

1-Slv'-903 I I '

                                                                             !1   111111111 Ill!! 1 111   l!t
                                                                                                               ,,,,,,,,,~ .... c~~~~7,?.~~~~ --- *j __ __ __ _ ___ __ __ __ __ _ _____ --S      D'JG. l-S\J-03B SEGMENT S\J-54
                                                                                                                        !                                    1,
                     !I                          l                          !                                      ~1   I 1-S'J-902 L..J~~-=-5-~ )~

CONTINUED

                                                                                                                  ~                                                    1-S 'J -90 8 TO RADIATION (

MONI TORING -.-)- - ~ (TYP. OF 4) P-SA P-5B ITT i§ ~(SV-27) P- SC P-SD fil *(SV - 23) I I I I I

             ,-~----~-------0=-----D---,

I '"' ~ ce,':'1/./oo ; effi '"' , "'"'  : ""~ I

                                          ~                           @~                                                                                                                   RBI LEGEND 1

SW-22 I Dlv'G. 1-SV-OIA J I SEGMENT 1-Slv'-18 Dlv'G. 1-SV-OIA SEGMENT 1- Slv'- 19 J Dlv'G. 1-Slv' - OIA SEGMENT 1-S lv' - 20 Dlv'G. 1-Slv'-OIA SEGMENT 1-Slv'-21 I J I SW-23 SW-24 SW-25 SW-26 SW-27 SW - 54 NOTES, I UNIT l I I. ALL MARK NOS. PRECEDED IL ___________________________ CONTAINMENT _JI VITH 1-S \,'- UNLESS DTHERVJSE NOTED. 2, REFERENCE 11448-FM-071A, SH J 11448*FM-071B, SH I SERVICE \JA TER SYSTEM D\JG. 1-S'J-OIB

e TD Cl/ DISCHARGE TUNNEL TD Cl/ DISCHARGE TUNNEL e

                                                                                                                                                                                                           ,----D-       IE-S..,.EL-"" <NOTE 2>

FUEL OIL TAN TK-1 I- SII-E-6 i tlllt!lllll1!111111HIIIIIHIIIIIIIIIU!l!Hlll111111'1tll:tr1111111111111un111111111111111!: SHAFT (~~~R~NFG 3~IL COOLER ( S\1-06) 1-SIJ-P-!C STATION VACUUM

                                                                                                                                                         ~*--... ,. -. -....... -*-~*- ---*-.                                                                                                                            Q (SIJ- 06)

PRIMING PUMP SEAL \/ATER COOLERS MECHANICAL CHILLER CONDENSER UNIT 2-CD-REF-1

                                                                                                 <SIMILAR TO
                                                                                              - CD-REF-!Al MECHANICAL CHILLER CONDENSER UNIT MECHANICAL       1-CD-REF-!B                                                                                                                                             P-lB CHILLER           (SIMILAR CONDENSER               TO UNIT          -CD-REF -!Al
                                                                                                                                                                                                          ~-D-I-ES_E_L_"" <NOTE 2)

FUEL OIL TAN TK-1 1-CII-S- 4 TO/FROM UNIT 2 1- SII-E-8 (SIJ-04) CH!LLED \/ATER UNIT TURBINE BUILDING SERVICE \/ATER SYSTEM [------- ~ ----------- I ' J-CII-S- 8 TD RIVER \/ATER FIGURE 3.1-IC i (Sll-01)  : MAKEUP PUMP DIIG 1-S\I-OlA P-lOOB I r---- ~------- ~-

                                                                                                                                                                 , .,~~$ (,~:~)~--

SEGMENT Sll-12 CONTINUED 2-S\1-1324 t ---,, ,

     'f                                                                                                                                                  I (Sll-03) :    f                                                                           P-lA                   : :

(Sll- 04) , ; (S'J- Ol) f I

(Sll-12) I tl INTAKE CANAL INTAKE STRUCTURE

      ~-*-**-*w                  * *J-S\/- 403                                                                          2- S11- P- 4A

P-4A I (Sll-12)

N t~**-**-*W J-S\/-406 J, P--411 2-SII-P- 4B

   ~                                                                                                                  SERVICE                                  RBI LEGEND:

i \/ATER PUMPS SW-01 *- -- -- -- -- -- -- -- --

• NOTES,

1. ALL HARK NOS. PRECEDED SERVICE y \/ATER PUMPS 2-CII-S-4 SW-02 SW-03 SW-04

                                                                                                                                                                                                                                                           \/ITH 1-SII- UNLESS OTHERIIISE NOTEIJ,

2. ONE DIESEL FUEL OIL TANK SW-05 - ... .. . .. . .. . ... ... . .. . ... .. . .. . .. _

JS SHARED BY ALL 3 PUMPS.

      ~

SW-06 llllll!l!lll'll!ltttl11111llll!I ,111111111111111!111 1111111 SW-12 - * * - * * - .. - * * - * * - * * - 3. EMERGENCY SERV!CE \/ATER PUMPS ARE LOCATED IN THE (Sll-12) LOIi LEVEL INTAKE STRUCTURE. 2-C\I-S-8 L.*-**-S "'~ 4. REFERENCE 11448-FM-071A, SH IL2, 11448-FM-077C, SH 1 R!VER \/ATER MAKEUP PUMP 1-SII-P-lOOA SERVICE VATER SYSTEM DVG. 1-SV-02

e e

                                                                                                                                                                   ~              Dl.'G 1-S\J-OJB 111111          ~

SV-U3 SEGMENT S\J- *2 2-Sl.'-S- 2A D\JG 1-Sl.'- 03B (NO SEGMENT)

                                                         ~~
                               ~
                            @:ID I
                                      ~,a39 sv-1!64
                                      @:ID 8-S\J- 3
                                                        - -<><l-- * -

SW- '63 'l' tf :-~ ---, £ **- *-**-**--~ I ,l-Sl.'-S-2B

                                                                                                                                             ~

P- !OB sv-u, CHARGING PUMP S\J PUMPS DIJG 1-SIJ-03B SEGMENT S',/-*J l r II I

                                        - -<><>-=

sv-:m ~

                                            @:ID
                                                      *-*         l I r i I ~ 1-t
                                                                              ~
                                                                                    = @:ID
                                                                                        ~

7 sv 315PCV-101A . -s TO UNIT 1

                                                                                                           ~2 -J:.~r~a~-

I SV-26 r.=a\ I I I - + C><l ' H T'.J-{><1- -

• DISCHARGE Dl.'G 1-Cl,'-02 SE:G>EHT SV-10 ,--

IIM!NU[D

                     - - -' "l><l-i:IDp_Lj_i~,-1t
                                     ~            ~                                                                                         ~

t'I TUNNEL I 1

                                                                                                                  @:ID
                                                        =                                                            1- VS-P-lA CHILLER CONDENSERS
                                                       ~~                                                                                                 .

SV-266 ----r--------- 1

                                                    - - * - * - * - , - - * - * - * - * - * - * - * - * - * . . . . . ! . . J I

RB I LEGEND: SW-10 I! I!~~~ rwj~* SW-29 SW-30 SW- 31

                                                                                                                   ~~* [ .. ~i~o~- ,,,.,                                   23 SW-32 SW-33 1

I -:) -T- 1-VS-E-4B I SW- 34 SW- 35 II 1111 1 1$ II lit f SW-36 l sv-J21 l - VS- P-lB sv-J26 CHILLER CONDENSERS t' SW-37

~ SW-38 SW-39

                                      ~~

SW-40 I I

                                                                                        * ~:~ , -- -

SW-41

                              ~- ~ --*-*1 I
                                                      ~  ~      ~

L  ?~ J

                                                                                              !       ~ l:ID~

sw-;o I SV*XIS

                                                                                                                         ~
                                                                                                                                ?

PCV-lOIC c-- ~'"cv-

                                                                                                                            - -c,I.:;- - - -
                                                                                                                                                 -{Xi- L
                                                                                                                                                                    @:.ID  ~

i

                                                                                                                                                                                            -  -s      TO UNIT 2 DISCHARGE
                                                     - -.....,...,-- .          "-        1-: "
                                                                                                                     'Ev-==

i TUNNEL

                                                                                                          ~

SV*33J SV- 30< I L~ ~lODC SELF CLEANING STRAINERS I " ~ - ~ l-VS-P-lC J ~ SV*J36 CHILLER ~ I CHILLER CONDENSER CONDENSERS sv-:i<< L ~ -:_ -:_ -:_ -:_ -:_ -:_ -:_ -:_ -:_J-:_ - ____ ~ ~ HP! _ ~

                                                                                                           -   CONTROL,        RELAY ROOMA IR- CONDIT!ONm G CHILLER- CONDENSER~

NOTES.

l. ALL HARK NJS. PRECEDED

                                                                                                                                                                                                                     \IITH 1-S\I- UNLESS OTHER\IISE NOTED.

2. REFERENCE 11448-FM- 071B, SH I 11HO-FH-071D, SH I SER VICE \./ATER SYSTEM D\./G. 1-S\./-03A

Dw'G 1-Sw'- 03A (S\1- 42) (S\1- 42) (S\J-44) (S'w'-44) ,-------*-: (SV - 46) FROM 1- P-lOA SEGMENT Sw'-40

                   ~                 ----              -- -t><J- - ~               -     -- ' T I
                                                                                                                                                        , -{><}- -       - ,  -1*-- - - *r - -                     --t><J- ,

1 1- Sw'-E-lA i \ I I '*..... ___..,/ (S\1-42) I Sll-269 (S\1-46) l (S\J-54) ~ I I (S\H8) (S\1-48) [Fti=f::--j (S\1-51)  ? Dw'G 1-Sw'-03A

                                                                                                 ~ -- ~

I LE.:.5.{U

                                                                                                                                           ;. . - - - - --cJ<J. TCV-
                                                                                                                                                                              --       -{X}-- -

1 FROM 2- P-lOA TD UNIT 2 CHARGING PUMP (S\1- 42)), LOSA

                                                                                                ,0,l-S\1-171 (S\1-49)   I I
                                                                                                                                                                  -lr (S\J-51) I I

Dw'G 1-Sw'-03A - - - - ~ - - - S\I SUBSYSTEM I (S\1-49) ,------------, DIIG 1-S\I-OLB

I-CH- '

FROM 2-P-!OB ~ - , --l><J- - I

                                                                                                                       '"'i  C" _c:;n
                                                                                                                          ._1,. ___ ,,_,L
                                                                                                                                           ~    - -  -

(S\1-52) (O~~ -

                                                                                                                                                                            -  -  -    -{><}- - - - -

(S'w'- 52) 1 ) SEGMENT S\1-54 CONTINUED

                                                                                                    ~'w'-4~                                                                                                               I 2-Sll-443                                                  l- S'w'-llS                                                                                                 (S\1-53) I       :

(S'w'- 43) (S\J- 43) ~ -l-  : (S\J-54) f cs\1-47) _t

• I

                                                     *

• cs\1-so) cs\1-so) Fci-:r::--1 cs\1-53)

(S\J- 43) I

                                                                                                         ---t><1- - --1      C" _ c:;r     r- - - -
                                                                                                                          . _1,. ___..,_"--*                        TCV-
                                                                                                                                                                               -      --{X}--          -     -    -     J 1

Dw'G 1- Sw'-03A ( G_ 1 ~ j_ Q.. , (S\J-45) 108C  :**-------~ FROM 1-P-10B r---:'. -~ -- - - --t><l-- - -,---...._,- - - - - - - - - - - - -- -I><}- - - - - - - -t*------*-t- - - - - -{><)- - J SEGMEN T Sw'- 41 s11- 1oe (S\J- 43) CHARGING PUMP (S'w'-45) :**-------: (S\J- 47) l-S'w'-897 LUBE OIL COOLERS 1-Sw'-E-IB  !\ \

                                                                                                                                                                                       , ........,/

RBI LEGEND: SW-42 SW-43 SW-44 SW-45 SW-46 SW-47 NO TES: SW-48 SW-49 1. ALL MARK NOS. PRECEDED SW - 50 WITH 1-SW- UNLESS SW-51 OTHERWISE NOTED . SW-52 2. REFERENCE 11448-FM-0718, SH 1 SW-53 SW-54 I I II 1111 lilt I 1111 SERVICE \./ ATER SYSTEM D\./G. 1-S\./-03B

e 1-VS-234 OFFICE BUILDING AIR COND. LNIT l- VS- AC - 5 I-VS-241 LA![]RATDRY AIR COND. UNIT l- VS- AC- 3 VS-251 VS-247 1-VS-2S6 ASSEMBLY ROOM AIR COND. UNIT 1- VS- AC- 4 <,------ixi---- ~ t- VS - 345 l-VS-344 REFRIGERATION PIPING 1-VS-£-tC SEE l144B-fB- 041A, SH I FOR DETAIL

                                                                                  <:-+-------,0-----------<><l------j CHILLED VA1£R PUJfl' I-VS..P..3B REFRIGERATION PIPING                                                                                                                        D\iG 1-vs-02 1-VS-£-19                                                                                                                              0ZEZ)

SEE l1HB-FB-04IA, SH I FOR DETAIL CONTINUED

                                                                                  < : - + - - - - - ! Z I - - - - - - - - - - - - C > < l - - - --   --l RBI LEGEND <

VS - BC- 283 NOTES!

1. ALL HARK NOS. PRECEDED 111TH 1-VS- UNLESS aTHER\llSE NOTEn

2. THIS DIAGRAM IS FTIR UNIT L REFRIGERATION PIPING UNIT 2 SIMILAR UNLESS 1-VS-£- IA OTHERIIISE NOTED SEE 1144B- FB-041A, SH 1 FOR DETAIL 3. REfERENCE ll44B-f1Hl4IA, SH 1 11448-FH--OJJA CHILLED \./ATER SYSTEM D\./G. 1- VS - 01

r - - Z-VS-AC-'JI RELAY ROOM UNlT 2

                                                                         - ---=-     -i><l-     - ""l                                        r    -    -I><)-   -1):XJ-    - -@

2-VS-of\C-8 R(Ll'll IUD1 UNIT 2

                                                                                                                                                                                                                ---          ~       - -   -,
                     --j

"= 1-vs-01 1-vs-~1 l- VS-247

                                                                                                                    ~ Dw'G
                                                                                                                          ~

1-vs-01 C[)HJNL(D I

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I r - - - - 1-vs-...c-1 R'ELAT RCIJN I r

                                                                                                                                             '        ,                          t*VS-of\C-2 R[Hl RID1 UNll I
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I

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I

                                                                                                                                                                -1):XJ-    -    -@                              -   -    -   -l><I- -  -   -I 2-VS-AC-7                                                                                                           l*VS-Al>b 1                                    RELAY ROOM                                                                                                          Rf:LM R001                                                      I UNIT Z                                                                                                               UNIT J I

I I ~ I r--- - --

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                                                                                                                                                       -I><)-

I

                                                                                                                                                                -1):XJ-    -    -@                              - - - -l><I- - - . . . J J-VS-AC-7                                  I                                                                        2-vS--'C-6 I

1 R(LAY RID1 R£LAY RCD1 UNIT J I I !J.1[12 J. _J - - ,

                                                   --r -======~===='= j =
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I

"ii:-{> - - - - ..,. _ T CllHD =

Q::j Q:: --~:1 Cc:NTROL AND R[Lil\Y RCD4 CONTRCl. AND R(LAT RCIJH COHTRO.. i'IND R[LAY RCXJH AIC CHILLER VAT[R A/C CHILLER \/ATER A/C CHILLER \lfil(R

                                     ]-VS-[-4A                                            1-VS-C-41                                                                 l*VS-[-4C
                                                                                                                                                                                                                                          - I_

coma). AND R[LAY

                                                                                                                          ,VC CHILLER   VAT[R RCDt PlH' CC)flRD.. AND R£L4Y R(D(
                                                                                                                                                                                                  /IJC CHILLER ,..AHR P\.H' r

I

                                                                                                                                                                                                                                                       -{_        -,

J*VS-P-2B 1-VS-P-~ r - - - - - - -I><!- - - - - - - ,_ - - - - - - -(><)-- --J._ _ ______ J I 0 l-VS-TK-IOOA SURGE TANK 1 I I I ..L r - -

                                                               - L-
                                                                            ---<:oc>- -
                                                                         ~ <}- _., ov~-OJ
                                                                                            -    -   -                T L

J -<n>- - - - - - - - - - - ....J RBI L[r£NI) I C(JflHUD vs-01 11111111,111111111 vs-oz - - - -

                         - - - - - - - - J                                                                                                                                                                                                           lr(ll{S; l ...i.L MARK tlJS, ~CCDCD
                                                                                                                                                                                                                                                          \IJTH l*VS* lk[SS IDH:MSl:N!IT[O r!THISDl~lsrt11Lt1Jll, Lt,illlSIJl,JtM!UM.{SS OTICRVIS[ NOTCD 3R£:r[R(NC(ll44B-rit--G4IA,SH2 CHILLED \./ATER SYSTEM                     D\./G. l-VS-02

MER- 3 MER-4 ~ MER- 5 TURBINE BLDG. I D',/G  !-VS- 02 )" - - - - - -co:J- ~ 1 - - - - - - - - - - - - - - - J. -, 0ZEDZ) CONTINUED I

                                                 ~       )

nb} -"1r I Q::::;i CONTROL ROOM CHILLER

                                                                                               --1 CONTROL ROOM CHILLER
                                                                                  ! - VS- E-4E
                                                                                                             -D-
                                                                                                             -D-1
                                                                                                                  ...J
                                                                                                                                           ~

2

                                                                                                                                                                                        ~

2 i 1-VS-AC- 219 l - VS- AC - 222

                    >-VS-HO                                                                                                    MER 5                               MER 5 AIR HANDLING UNIT                 AIR HANDLING UNIT "T"                                          "T"
                                                ~       CHILLED ',/ATER PUMP                CHILLED ',/ATER PUMP
                                                                                                                   ~
                                                                                                                   ~

9 MER- 3 MER-4 ~ MER- 5 9 1- VS-P- 2D  ! - VS - P- 2E 9 ~DI

                                            ~                                                                     ~

TURBINE BLDG. I t .i.. T D',/G 1-VS- 02 )- - - - - - - -co:J.- - - J - - - - - - - - - - - - - - - - -, - - - - J 0ZEDZ) CONTINUED I L ___ __ _ ..J _ _ _ _ _ _ -D- _J RBI LEGENO VS-D2 - - 1111D L ALL P1ARI< l()S. PRECEIED YITii 1-vs- LN.£SS IJTltJMS[ P<ml!.

2. THIS IIIAC;W4 IS rt11 UNIT l.

I.MT 2 SOOl.AR lN.ESS [JTlfJMS[ lflTlJ)

3. REFtRENCE 11'441-flH41A, SH l CHILLED \./ATER SYSTEM D\./G. 1-VS-03

• Attachment 3 Example Expert Panel Minutes

Surry Unit 1 Risk Informed Expert Panel Meeting Minutes 8/20/97 The following expert panel members were in attendance: Jack Martin (Chair), Gary Thompson (System Engineer Primary), Jim Simpson (Ops Primary), Nitin Shah (Engineering Mechanics), David Dodson (NDE), Les Spain (Materials/Failure Lab). Additionally alternates John Paul (ISi) and Dave Bucheit (PSA) were present. The required quorum was met. The following guests were in attendance of the meeting: Alex McNeill (appointed secretuy for the expert panel), Ernie Throckmorton, Westinghouse employees Nancy Closky and Ken Balkey. The pwpose of the meeting was to continue the Risk Informed ISi expert panel evaluation process. The meeting began by reviewing the feedback verbally received from the NRC observers at the last meeting. Generally, the feedback called for improvements in the information presentation to the expert panel. The Chairman, Jack Martin, added that a general write-up of deterministic insights for the entire plant would be useful to aid looking at the insights on a segment by segment basis. This was assigned to Ken Balkey, Nancy Closky, Alex McNeill and Dave Bucheit. Feedback from the expert panel on check valve separation of segments suggested that inspection expansion could be used in lieu of higher classification if there are reliable differences in failure probabilities between the segments. Previously, a numerically low safety significant segment had been made high since it was separated only by one untested check valve from a high safety significant segment. The suggested alternative was to examine the high safety significant segment and expand into the low safety significant segment only if problems were identified in the high safety significant segment. The panel thought this was an acceptable alternative, however they felt previous classifications were appropriate based upon the failure probabilities reported and their uncertainties. The panel reviewed the definitions ofRRW and RAW, these follow: a) RRW (Risk Reduction Worth) indicates the reduction factor in risk if the piping is assumed perfectly reliable for all failure modes. The RRW is calculated by reevaluating the PSA model and substituting a value of zero for the component unavailability for each piping segment of interest. b) RAW (Risk Achievement Worth) indicates the increase factor in risk if the piping is assumed failed for all failure modes. The RAW is calculated by reevaluating the PSA model and substituting a value of unity for the component unavailability for each piping segment of interest. Discussion on the eves system continued. A general system overview of the CVCS was read to the panel. Segment CH-014: This segment was Low Risk Significant numerically. Deterministic insights were reviewed. The panel noted that the segment supplied seal injection to the RCPs and provided containment isolation. The panel noted multiple check valve containment isolation inside the containment, flow restriction outside containment and potential needle valve use, and MOVs and manual valves further upstream of the segment for containment isolation outside containment. The panel unanimously voted the segment as Low Risk Significant.

• Segment CH-015: This segment was Low Risk Significant numerically. Deterministic insights were reviewed. The segment was a continuation of the seal injection header. The discussion for CH-014 was
• applicable. It was noted that seal injection is important in Appendix R considerations in that if a fire results in a loss of component cooling function only seal injection remains to prevent RCP seal failure and the resultant seal LOCA. The panel unanimously voted the segment as Low Risk Significant.

Segments CH-016 & 017: These segment were considered together. The segments were considered Low Risk Significant numerically. Deterministic insights were reviewed. The segments are used for RCS loop filling and could be used for alternate safety injection flow path and emergency borate flow path. The segments are normally isolated. The panel unanimously voted the segment as Low Risk Significant. Segments CH-018, 019, 020, 021, 022, 023 and 041 were tabled pending numerical results which included failure of auxiliary spray. Numerical result update assigned to Dave Bucheit. Segment CH-024: The segment was considered Low Risk Significant numerically. Detenninistic insights were reviewed. The segment is part ofletdown. It was noted that AP-16 requires operator isolation of letdown for RCS leakage greater than 24 gpm. Letdown was noted as important in shutdown with solid pressurizer operations. Discussion centered around repair options if leakage occurs and use of excess letdown. The panel unanimously voted the segment as Low Risk Significant. Segments CH-025, 026, 027: These segments were considered together. The segments were considered Low Risk Significant numerically. Detenninistic insights were reviewed. The discussion for CH-024 was applicable. The panel unanimously voted the segments as Low Risk Significant. Segment CH-028A: The segment was considered Low Risk Significant numerically. Detenninistic insights were reviewed. The failure of this piping on Surry Unit 2 was discussed. The difficulty of shutting down the unit without Letdown was also reiterated. The panel unanimously voted the segment as Low Risk Significant however noted that the company may want to incorporate some sort of inspection here for plant reliability. Segments CH-028B to CH-040: These segments were evaluated together. The numerical results indicated the segments were Low Risk Significant. Deterministic insights were reviewed. It was noted that the basis for the low categorization had been fully discussed on similar segments previously. It was noted that segment CH-040 had hydrogen. Leakage from the segment could result in a fire. Additionally leakage could cause misleading information concerning VCT level. The panel unanimously voted the segments as Low Risk Significant. The next meeting was tentatively established for Wednesday, August 27, 1997 at 2:00pm. at Surry. The meeting was closed.

                                                                   ;;;A~
                                                                                              ,/;

Respectfully submitted,

 ~m~

Alex McNeill Jack Martin Secretary Chairman

Chemical & Volume Control System Summary of Functions The chemical and volume control system (CVCS) is used to:

• adjust the concentration of the chemical neutron absorber for chemical reactivity control,
• maintain the proper water inventory in the reactor coolant system,
• provide the required seal water flow for the reactor coolant pump shaft seals,
• provide high pressure flow to the safety injection system,
• provide for reactor coolant cleanup and degasification,
• maintain the proper concentration of corrosion-inhibiting chemicals in reactor coolant, and
• provide a means for draining the reactor coolant system to the primary drain system by means of the excess letdown flow path.

Maintenance Rule Summary The maintenance rule program identified 25 functions for the CVCS, of these the following functions were considered risk significant: MR Function # Description CH006 The CH system provides auxiliary means to spray the pressurizer. CHOU The CH system provides HI Head SI. CH012 The system suction auto swaps to RWST on low VCT level & SI. CH013 The CH system provides flow to the opposite unit CH system. CH014 The CH system provides RCP seal injection flow & return flow. Of the risk significant functions only function CH012 was not modeled in the PSA. PSA Model Recommended Enhancements Several enhancements to the PSA model have been recommended for this system as a result of maintenance rule review. These are summarized as follows: Short Term

1) Increase charging pump test and maintenance unavailability.

2) Add test and maintenance unavailability for charging cross tie using the opposite units charging pumps.

Medium Term

1) Revise PSA to require 1/2-CC-P-2A/B operation to cool charging pumps.

2) Increase charging pump cross tie reliability performance criteria to 1 fails closed failure/year for each manual valve, and the flow path should have a test and maintenance unavailability of 438

• hours/year and the goal setting limit of 876 hours/year.
• the model.

3) The charging pump dependency on the VS fans and dampers for cooling should be added to

4) The RWST MOVs to the HHSI pumps, l-CH-MOV-l 115B/D, should have a test &

maintenance unavailability performance criteria of 438 hours/year and a goal setting limit of 876 hours/year. Both MOVs will not be removed from service at the same time. Long Term

1) l-CH-MOV-1115B/C/D/E limit switches required for VCT/RWST swapover are not modeled.

2) l-CH-MOV-1275AIB should be included as fail open valves in model. Required for LOCAS where pressure drops below 1275psig.

3) The charging pump suction and discharge MOVs should be represented in the PSA model as a plugging fault.

4) The nonregenerative heat exchanger should be added to the model for normal charging success.

5) 1-CH-MOV-llSA is modeled as fails closed. This is not logical for a three-way valve that fails to the VCT. *

6) Add the charging pump cross connect valves and drain valves to the model.

7) The unit 2 charging pumps should be explicitly included in the PSA model.

8) The pressurizer spray modeling should include l-CH-MOV-1310 failing open and l-CH-MOV-1311 failing closed. Include test and maintenance unavailability.

9) Add the BAST to the model for emergency boration. Additionally add the manual valves in the emergency boration flow path.

Risk Informed ISi Summary Current Program Scope The system currently is included in the ASME Section XI program in part. Large portions of the letdown path in the auxiliary building are currently excluded. For this system, 44 piping segments were identified. Consequence Evaluation The direct consequences postulated for the CH system were primarily:

• loss of charging (no impact on PSA)
• loss of seal injection (no impact on PSA) or
• loss of Unit 1 RWST, Unit 2 RWST crosstie, Unit 2 crosstie to charging pump (CH-14,15, 18,19) OR
• loss ofemergencyboration (CH-20, 21, 38, 39, 41)

Several segments (CH-04, CH-05, CH-14, CH-15, CH-18, CH-19,CH-30A, CH-30B) were identified to have indirect consequences due to piping spray/jet impingement considerations in the Aux Building basement (2' elevation). This was postulated to primarily resultin the loss of the following equipment:

• blowdown containment isolation valves
• CCW to RHR. heat exchanger valves
• MS trip valves (postulated to result in a reactor trip - loss ofMFW (MFW recoverable)
• SI-MOV-1842 (HHSI to cold legs)
• SI-MOV-1867C/D (alternate HHSI to cold legs)
• SI-MOV-1867AIB (HHSito hot legs) (hot leg injection not modeled in PSA)
• Additionally, several segments in the charging pump cubicles were identified to have indirect consequences. However, these consequences were bounded by the direct consequences postulated for this segment.

Failure Probability Evaluation The engineering team estimating the failure probabilities noted the following experiences at Va. Power or the industry:

• The Surry Unit 2 letdown piping leakage down stream of the flow orifices,
• the North Anna seal injection piping leakage at the pump connection; the pump connection leakage was attributed to mechanical pump vibration and the letdown line leakage to flow induced vibration coupled with inadequate support, and
• the replacement of the boric acid transfer system due to leakage. The replacement of the boric acid transfer system was mostly discounted due to improvements in boric acid concentration and temperature lessening concerns for SCC.

In general the system failure probabilities were medium to low in estimates except for the vibration situations and a few SCC situations postulated in isolated portions of the letdown path. The SRRA code was used for all segments. Risk Significance Determination Based on the risk calculations, the results for the charging system are:

• CDF without operator action= 2.73E-7 (total CDF = 6.3E-5)
• CDF with operator action= 2.73E-7 (total CDF = 4.IE-6)
• LERF without operator action= l.54E-9 (total LERF = 5.2E-6)
• LERF with operator action= l.54E-9 (total LERF = 4.5E-7)

The following segments were identified to be HIGH SAFETY SIGNIFICANT based on RRW > 1.005

• CH-08
• CH-09
• CH-10 These segments were expected to result in a small LOCA with a resulting CDF of8.99E-8 and a resulting LERF of2.32E-l0. The RRW for these segments was 1.022 for the CDF with Operator Action case.

NO piping segments were identified to be in the grey area (RRWbetween 1.001 and 1.004). Other Deterministic Considerations

• No external event or shutdown risk importances were identified.
• The charging cross connect is important in Appendix R considerations.
• The system provides emergency boration, auxiliary spray and RCP seal injection for consideration in other types of accidents.
• The system has several segments separated by check valves
• Several segments have containment penetrations .

Attachment 4 RI-ISi Program Examinations

Dra\\ing No.

              *                         !\lark No.               Line Number

• Period Category* Item No. ISi Class Credit l\Iethod 11448-CBB-041.-\-3 1001 1"-VS-23-151 3 R-.-\ RI.I I 38 y PT Relief Request Re,*ision 0 Conunents RBIS! NOTE: Perform PT examination on weld nearest \'ah'e l-VS-PCV-533 on line Segment VS-001 1"-VS-23-151. There is no weld number I 00 I, this is used only to sort the database.

11448-CBB-04 l.-\-3 1002 I 1.,"-CHR-151 3 R-.-\ ALT 38 y PT Relief Request Re,*ision 0 Comments RBIS) NOTE: Perform PT examination on 1st weld on discharge side of pump l-\'S- Segment VS-002 P-28 on line I \'i"-CHR-151. TI1ere is no weld number I 002, this is used only to sort the database. I 1448-CBJ\1-071B-3 1001 I W'-WS-74-2 IX R-.-\ RI.I I 38 y PT Relief Request Re\'ision 0 Comments RBIS! NOTE: Perfom1 PT examination on weld at reducer on line I 1.~"-WS-74-2 IX Segment SW-044 on vah*e I-SW-115 side of reducer. There is no weld number 1001, this is used only to sort the database. 11448-CBJ\1-0718-3 1002 l '/2"-\VS-75-2 IX R-.-\ RI.I I 38 y PT Relief Request Re\'ision 0 Comments RBIS! NOTE: Perfom1 PT examination on weld at reducer on line J 1.i"-WS-74-21X Segment S\V-045 on valYe I-SW-110 side ofreducer. There is no weld number 1002, this is used only to sort the database. 11448-CBl\!-071B-3 1003 I ',~"-\VS-450-21X 3 R-.-\ RI.I I 38 y PT Relief Request Re,*ision 0 Conunents RBIS! NOTE: Perform PT examination on weld at reducer on line I 1,2"-WS-450- Segment S\V-046 2 IX on vah*e 1-SW-896 side of reducer. There is no weld number 1003, this is used only to sort the database. 11448-CBl\!-0718-3 1004 I W'-WS-451-2 IX 3 R-.-\ RI.I I 38 y PT Relief Request Re,*ision 0 Comments RBIS! NOTE: Perform PT examination on weld at reducer on line I \t,"-WS-451- Segment SW-047 2 lX on \'alve I-SW-897 side ofreducer. There is no weld number 1004, this is used only to sort the database. 11448-CBJ\1-0718-3 1005 2"-WS-560-21X 3 R-.-\ RI.I I 38 y PT Relief Request Re\'ision 0 Comments RBIS! NOTE: Perform PT examination on weld at tee on line 2"-WS-560-21X Segment SW-054 (where 2"-WS-560-21X connects to I 'h"-WS-450-21X) on line l "-WS-571-21X side of tee. There is no weld number 1005, this is used only to sort the database. 11448-MKS-1022.-\11-2 JOO! 3"-CC-820-1501 R-A RI.II 38 y UT/1\IT Relief Request Re,*ision 0 Comments RBIS! Note: Perform UT/PT or UT/MT on the weld nearest to penetration # 110 on Segment CC-288 line 3"-CC-820-1501. Note there is no mark/weld number 1001, this is used to sort the ISi database only. 11448-MKS-1022.-\12-3 1001 2'1,"-CC-88-151 R-A RI.I! 38 y UT/1\!T Relief Request Re,*ision 0 Comments RBISI Note: Perform UT/PT or UT/MT on the 1st weld downstream of 4"x2W' Segment CC-28.-\ reducer on line 2'/,"-CC-88-151. Note there is no mark/weld number 1001, this is used to sort the ISi database only. 11448-MKS-1022.-\12-3 1002 l 'h"-CC-803-1501 R-A Rl.11 38 y PT Relief Request Re\'ision 0 Comments RBISI Note: Perform PT examination on weld connecting 4"xl W' reducer on line Segment CC-28.-\ 1W'-CC-803-1501. Note there is no mark/weld number 1002, this is used to sort the ISi database only. RBIS~ Plan Sorted by Dra\\ing and !\lark No., SPSU13 Database Page 1 of 14 Print Date: J(},i2/i97

Draning No.

                 *                     !\lark No.              Line Number

• Pe1iod Category Item No. ISi Class Credit l\lethod 11448-l\IKS-1105812-l 1001 3"-CH-99-152 R-A RI.I I 28 y PT Relief Request Re\'ision 0 Conuuents RBIS! Note: Perfom1 PT examination on weld nearest penetration # 19 on line 3"-CH- Segment Cll-005 99-152. Note there is no mark/weld number I 00 I, this is used to sort the [SI database only.

11448-l\IKS-1122:\4-1 1001 3"-WGC8-1-601 R-A RI.I I 28 y l.1T,'l\lT Relief Request Re,*ision 0 Conuuents RBIS! Note: Perfonn L'T/PT OR L'T/1\IT on the weld nearest to penetration #39 on Segment 8D-002B line 3"-WGC8-l-601. Also see drawing 11448-CBl\I-124A-3. Note there is no mark/weld number I 001, this is used to sort the ISi database only. 11448-l\lKS- l I 22A4-1 1002 3"-WGC8-105-60 I R-A RI.II NC y l.1T/l\lT Relief Request Re,*ision 0 Comments RBISI Note: Perfonn L1T/PT OR UT!l\lT on weld at elbow do\mstream ofrnl\'e 1- Segment 8D-003 BD-150 on line 3"-WGCB-105-601. Also see drawing 11448-C8l\l-124A-3. Note there is no mark/weld number 1002, this is used to sort the !SI database only. 11448-l\IKS-1122A5-I 1001 3"-WGC8-2-601 R-A RI.I I 28 y L1Til\[T Relief Request Re\'ision 0 Comments RBISI Note: Perfonn L1T/PT or UT/1\IT on the elbow to reducer weld upstream of Segment 8D-0058

                                                                             \*alve TV-8D-IOOD on line 3"-WGCB-2-601. Note there is no mark.weld number 1001, this is used to sort the ISi databasey only.

11448-l\lKS-1122:\5-1 1002 3"-WGC8-106-601 R-A RI.I I NC y L1T!l\lT Relief Request Re\'ision 0 Comments RBIS! Note: Perfonn L1T/PT or L1T/l\lT on branch tee weld connecting line 3"- Segment 8D-006 WGCB-2-601 to line 3"-WGC8-106-601. l11e weld to be examined is on line 3"- WGCB-106-601. Note there is no mark/weld number 1002, this is used to sort the !SI database only. 11448-l\IKS-1122:\6-1 1001 3"-WGC8-3-60! R-A RI.I I 28 y UT/1\IT Relief Request Re,*ision 0 Comments RBIS! Note: Perform L1T/PT or L1T/l\lT on weld connecting at 3rd elbow from Segment 8D-008B penetration #40 on line 3"-\\'GC8-3-60 I. Note there is no mark/weld number I 00 I, this is used to sort the ISi database only. 11448-l\lKS-1122:\6-1 1002 3"-WGC8-107-601 R-A RI.I I NC y PT Relief Request Re,*ision 0 Comments RBIS! Note: Perform PT examination on I" weld at 3"xl" Tee that connects to 3"- Segment BD-009 WGCB-107-60 I downstream of vah-e 1-BD-170. Note there is no mark/weld number I 002, this is used to sort the ISi database only. 11448-l\IKS-l I 2L2-2 1001 3"-CC-820-1501 R-A RI.I I 38 y UT/1\IT Relief Request Re,*ision 0 Comments RBIS! Note: Perform L1T/PT or L1T/l\IT on the weld at elbow nearest to penetration Segment CC-29

                                                                             # 110 on line 3 "-CC-820-150 I. Note there is no mark/weld number I 00 I, this is used to sort the ISi database only.

11448-l\IKS-13 IAl-4 1001 3"-SHP-57-60 I R-A RI.I I 28 y L1T/l\lT Relief Request Re\'ision 0 Comments RBIS! NOTE: Perform L1T/l\ff or UT/PT examination on weld at tee connecting line Segment MS-032 3"-SHP-57-601 and 3"-SHP-31-601 on 3"-SHP-57-601 side oftee. Note there is no mark/weld number I 00 I, this is used to sort the ISi database only. RBISl,Plan Sorted by Draning and !\lark No., SPSU13 Database Page 2 of 14 Print Date: JO 21 *9:'

Drm,ing No.

               *                          !\lark No.              Line Number

• Period Category Item No. ISi Class Credit l\lethod 11448-l\IKS-131Al-4 1002 3"-SHP-57-601 R-A Rl.l I 28 y l'Til\lT Relief Request Revision 0 Comments RB1SI NOTE: Perform Ff/l\ff or l'T/PT examination on weld nearest valve 1-PC\"- Segment l\lS-033 l\lS-102B on line 3"-SHP-57-601. The weld to be examined is on the same side ofthe rnlve 1-PCV-l\lS-102B as VSS-9. Note there is no mark/weld number 1002, this is used to sort the ISi database only.

11448-WFPD-13 1001 14"-\VCPD-37-301 2 R-A Rl.11 NC y l'T!I\IT Relief Request Re,*ision 0 Comments RBIS! NOTE: Perfonn l'T/MT examination on weld at reducer 1-CN-PSFR-22 on Segment F\V-001 14" side on line 14"-WCPD-37-301. Note there is no mark/weld number 1001, this is used to sort the ISi database only. 11448-\VFPD-13 1002 l 6"-\VHPD-3-301 2 R-A Rl.11 NC y L1T1I\fT Relief Request Revision 0 Comments RBIS[ NOTE: Perfonn l'T/1\IT examination on weld connecting piece 1-SD-PSFl-59 Segment F\V-002 to piece I-SD-PPS-258 on line 16"-\VHPD-3-301. Note there is no mark/weld number I 002, this is used to sort the ISi database only. 11448-\VFPD-13 1003 l 8"-\\'CPD-33-301 2 R-A Rl.11 NC y LT"f.'l\lT Relief Request Revision 0 Comments RBIS[ NOTE: Perform l'T/l\lT examination on weld nearest pump 1-FW-P-lA on Segment FW-003 line l 8"-\VCPD-33-301. Note there is no mark/weld number 1003, this is used to sort the ISi database only. 11448-\VFPD-13 1004 l 8"-WCPD-32-301 2 R-A Rl.11 NC y l'T/1\IT Relief Request Revision 0 Comments RBIS[ NOTE: Perform UT/MT examination on weld nearest pump l-FW-P-18 on Segment F\V-004 line 18"-WCPD-32-301. Note there is no mark/weld number 1004, this is used to sort the ISi database only. 11448-WFPD-14 1001 14"-WCPD-71-301 2 R-A Rl.11 NC y UT1I\1T Relief Request Re,*ision 0 Comments RBIS! NOTE: Perform UT/l\ff examination on weld nearest and upstream ofR0- Segment F\V-005 109A on line 14"-WCPD-71-301. (This should be a weld on piece l-CN-PPS-127 nearest to R0-109A) Note there is no mark/weld number 1001, this is used to sort the ISi database only. 11448-WFPD-15 1001 18"-WFPD-1-901 2 R-A Rl.11 NC y lIT/1\IT Relief Request Revision 0 Comments RBISI NOTE: Perform UT/l\ff examination on weld nearest and do\\11stream of Segment F\V-006 check valve I-FW-127 on line 18"-WFPD-1-901, on piece l-FW-PSF2-3. (Also see drawing l 1448-FM-068A- valve No. is shown on the FM drawing.) Note there is no mark/weld number 1001, this is used to sort the !SI database only. 11448-WFPD- l 7 1001 18"-WFPD-2-901 2 R-A Rl.11 NC y UT/1\IT Relief Request Re,*ision 0 Comments RBIS! NOTE: Perform lIT/1\IT examination on weld nearest and dO\mstream of Segment F\V-007 check valve l-FW-112 on line 18"-WFPD-2-901, on piece l-FW-PSF2-18. (Also see drawing l 1448-FM-068A-valve No. is sho\\TI on the FM drawing.) Note there is no mark/weld number 1001, this is used to sort the ISi database only. RBI SI, Plan Sorted by Dra'\\ing and Mark No., SPSU13 Database Page 3 of 14 PrintDate: 10*2].9'.'

Draning No.

              *                         !\lark No.               Line Number
                                                                                                  *Period     Category          Item No.         rsr Class        Credit l\[ethod 11448-WMKS-OIOOAIZ                      1-01                    1',"-CH-97-1502                        2       R-A                Rl.12             IA             y                 PT'\T-2 Relief Request       SR-014            Re\'ision    0          Conunents       SOCKET WELD, (WEPSOK). New to plan with Rev. 3 to plan. Designated weld as           Segment    CH-008 terminal end due to licensing concerns (Jolm Lewis). See memo Paul to Lewis of 8-16-94. Replaces weld 1-06 on same line No. & drawing No. New with Re\". 5 to Plan: Weld 1-0 I reported as being inaccessible by Dan Jensen on 9-15-95. Weld 1-06 added back into plan in order to keep the weld selection percentages the same.

Relief Request SR-014 submitted to report that terminal end weld (weld 1-01) ca,mot be examined unless the pump is disassembled. New with Re\". 8 to plan: Weld is scheduled for exam. during the 1997 refueling outage because the pump was disassembled. RBIS! Note: Perform PT/vT-2 examination. 11448-W~[KS-OIOOAIZ 1-03 11 ,"-CH-97-1502 2 R-A Rl.12 IA y PT'\T-2 Relief Request Re,*ision 0 Comments SOCKET WELD, (WEPSOK). RBIS! Note: Perfom1 PT & \T-2 examination. Segment CH-008 11448-W~!KS-OIOOAIZ l-07 l' ,"-CH-97-1502 2 R-A Rl.12 1.-\ y PT,\T-2 Relief Request Re\'ision 0 Comments SOCKET WELD, (WEPSOK). RBIS! Note: Perfonn PT & \T-2 examination. Segment CH-008 11448-W~[KS-OlOOAlZ 1-19 2"-CH-97-1502 R-A Rl.12 I.-\ y PT Relief Request Re\'ision 0 Comments SOCKET WELD , (WEPSOK). RBIS! NOTE: Perfonn PT examination. Segment CH-Oil 11448-W~IKS-O 1OOA4Z l-07 2"-RC-53-1502 R-A RI.I I I.-\ '{ PT Relief Request Re,*ision 0 Conunents SOCKET WELD, (WEPSOK). RBISI NOTE: Perform PT examination. Segment RC-027 l 1448-WMKS-OIOOA6Z 1-02 2"-RC-198-1502 R-A Rl.12 IA y PT/vT-2 Relief Request Re,*ision 0 Conunents SOCKET WELD, (WEPSOK). RBIS! NOTE: Perform PT/\'T-2 examination. Segment RC-037 11448-WMKS-OIOOA6Z 1-03 2"-RC-198-1502 R-A Rl.12 I.-\ y PT Relief Request Re,*ision 0 Comments SOCKET WELD, (WEPSOK). RBISINOTE: Perform PT examination. Segment RC-037 11448-WMKS-OIOOAZ-1 1-0IDM 29"-RC-1-250 IR R-A RI.I I IA y LTT Auto Relief Request SR-001 Re,*ision 0 Comments REACTOR VESSEL- NOZZLE TO SAFE END BLTTT WELD. Per Relief Request Segment RC-001 (SR-00 I) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform UT examination. 11448-WMKS-OIOOAZ-1 1-17DM 27'*,"-RC-3-2501 R 3 R-A RI. I I 1.-\ y UT Auto Relief Request SR-001 Re\'ision 0 Conunents REACTOR VESSEL - NOZZLE TO SAFE END BUTT WELD. Per ReliefRequest Segment RC-013 (SR-00 I) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform LTT examination. 11448-WMKS-OIOIAIZ 1-01 I \~"-CH-95-1502 2 R-A Rl.12 IA y PTl\'T-2 Relief Request SR-014 Re,*ision 0 Comments SOCKET WELD, (WEPSOK). Terminal End designator add with Rev. 3 to plan. Segment CH-009 RBIS! NOTE: Perform PT & vT-2 examination. RBrSI. Plan Sorted by Draning and !\lark No., SPSU13 Database Page 4 of 14 PrintDate: /02/*9-

Drawing No.

              *                        !\lark No.               Line Number

• Period Categm*y Item No. ISi Class Credit l\lethod 11448-WI\IKS-O IO I Al Z 1-01 I \,"-CH-95-1502 3 R-A Rl.12 IA y PT/VT-2 Relief Request SR-014 Rc,*ision 0 Comments Ne\\" \\"ilh Re\". 9 lo plan: TI1is weld ( 1-0 I) is inaccessible unless the RCP main flange Segment CH-009 is disassembled. TI1is \\"eld is scheduled in period 3 to ensure that the weld is examined if the RCP main flange is disassembled. See relief request SR-014. RBIS! NOTE:

Perfonn PT, VT-2 examination. 11448-WI\JKS-OIOIAIZ 1-03 l 12"-CH-95-1502 2 R-A Rl.12 IA y PTl\*T-2 Relief Request Re\"ision 0 Comments SOCKET WELD, (\\'EPSOK). INSPECTION REQUIRES FLANGE Segment CH-009 SEPERATION. RBIS! NOTE: Perform PT & VT-2 examination. 11448-Wl\lKS-OIOIAIZ 1-04 l '*2"-CH-95-1502 2 R-A Rl.12 IA y PTI\T-2 Relief Request SR-014 Re,*ision 0 Comments SOCKET \\'ELD, (WEPSOK). New with Rev. 9 to plan: This weld is added to the Segment CH-009 plan to replace weld 1-0 I on the same drawing and line number. This weld is an additional weld and is scheduled for examination to ensure that 25% of examination category B-J \\"elds are examined in the eYent that weld 1-0 I is not examined. \\' eld 1-0 I is inaccessible unless the RCP main flange is disassembled. See relief request SR-014. RBISI NOTE: Perfom1 PT & VT-2 examination. 11448-Wl\!KS-OIOIAIZ 1-23 2"-CH-95-1502 R-A Rl.12 IA y PT Relief Request Re,*ision 0 Comments SOCKET \\'ELD, (WEPSOK). RBISI NOTE: Perform PT examination. Segment CH-012 11448-WI\IKS-OIOIA2Z 1-0IBC 2"-RC-57-1502 R-A Rl.11 IA y PT Relief Request Re,*ision 0 Comments BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. RBIS! NOTE: Segment RC-028 Perfonn PT examination. I 1448-WMKS-OIOIA3Z 1-02 2"-RC-199-1502 3 R-A Rl.12 IA y PT/\T-2 Relief Request Re,*ision 0 Comments Circumferential Piping Weld, (WEPCB). RBISI NOTE: Perform PT/vT-2 Segment RC-038 examination. I 1448-WMKS-OIOIA3Z 1-05 2"-RC-199-1502 3 R-A Rl.12 IA y PT Relief Request Re\"ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). RBISI NOTE: Perform PT Segment RC-038 examination. 11448-Wl\!KS-OIOIAZ-I 1-0IDI\I 29"-RC-4-250 IR R-A RI.I I IA y l1T Auto Relief Request SR-001 Re,*ision 0 Comments REACTOR VESSEL - NOZZLE TO SAFE END BUTT WELD. Per Relief Request Segment RC-002 (SR-00 I) perform a full volumetric exaniination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface exaniination from the OD. RBIS! NOTE: Perform UT examination. 11448-WMKS-OIOIAZ-1 l-17DM 27W'-RC-6-2501R 3 R-A RI.I I IA y UT Auto Relief Request SR-001 Re\"lsion 0 Comments REACTOR VESSEL - NOZZLE TO SAFE END BUTf WELD. Per Relief Request Segment RC-014 (SR-001) perform a full volumetric examination from the ID (with 5%notch sensitivity on the OD) in lieu of the surface exaniination from the OD. RBIS! NOTE: Perform UT examination. 11448-Wl\IKS-0102AIZ 1-01 1'/,"-CH-93-1502 2 R-A Rl.12 IA y PT/Vf-2 Relief Request SR-014 Re\"ision 0 Comments SOCKET WELD, (WEPSOK). New with Rev. 9 to plan: This weld is added to the Segment CH-010 plan to ensure weld 1-01 is examined if the RCP main flange is disassembled. Weld I-OI is inaccessible unless the RCP main flange is disassembled. See reliefrequest SR-O14. RBIS! NOTE: Perform PT & Vf-2 examination. RBISl,Plan Sorted by Dm\\ing and !\lark No., SPSU13 Database Page 5 of 14 Print Date: J(),*21,*97

Dr:t\\ing No.

              *                          !\lark No.               Line Number

• Period Category Item No. ISi Class Credit l\Iethod 11448-WMKS-0102AIZ 1-01 t 1,2"-CH-93-1502 3 R-A Rl.12 IA y PT'\T-2 Relief Request SR-014 Re,*ision 0 Comn1ents SOCKET WELD, (WEPSOK). Added to plan with Rev. 3 to plan. Designated weld Segment CH-010 as tenninal end due to licensing concerns (John Lewis). See memo Paul to Lewis of8-16-94. Replaces weld 1-35 on 11448-Wl\lKS-0102A2Z. RBISI NOTE: Perfo1m PT

                                                                                & VT-2 examination.

11448-WMKS-0102AIZ 1-03 I h"-CH-93-1502 R-A Rl.12 IA y PT*VT-2 Relief Request Re,*ision 0 Comn1ents SOCKET WELD, (WEPSOK). RBISI NOTE: Perform PT & \T-2 examination. Segment CH-010 11448-Wl\IKS-0!02AIZ 1-04 I h"-CH-93-1502 3 R-A Rl.12 IA y PT-'\*T-2 Relief Request SR-014 Re\"ision 0 Comn1ents SOCKET WELD, (WEPSOK). New with Rev. 9 to plan: This weld is added to the Segment CH-010 plan to replace weld 1-0 I on the same drawing and line number. This weld is an additional weld and is scheduled for examination to ensure that 25% of examination category B-J welds are examined in the e\"ent that weld 1-0 I is not examined. Weld 1-0 I is inaccessible unless the RCP main flange is disassembled. See relief request SR-O14. RBIS! NOTE: Perfom1 PT & VT-2 examination. 11448-WMKS-0!02AIZ 1-07 I ~,"-CH-93-1502 R-A Rl.12 IA y PT/\T-2 Relief Request Re,*ision 0 Conm1ents SOCKET WELD, (WEPSOK). RBIS! NOTE: Perfonn PT & \T-2 examination. Segment CH-010 l 1448-WMKS-0102AIZ 1-14 2"-CH-93-1502 3 R-A Rl.12 IA y PT Relief Request Re,*ision 0 Conunents SOCKET \"VELD, (WEPSOK). RBISI NOTE: Perform PT examination. Segment CH-013 11448-WMKS-O 102A2Z 1-09 2"-RC-58-1502 2 R-A Rl.11 IA y PT Relief Request Re,*ision 0 Comn1ents SOCKET WELD, (WEPSOK), Tenninal End. RBISI NOTE: Perfonn PT Segment RC-029 examination. 11448-WMKS-O I 02A3Z 1-02 2"-RC-200-1502 3 R-A Rl.12 IA y PT/VT-2 Relief Request Re,*ision 0 Conunents SOCKET WELD, (WEPSOK). RBISI NOTE: Perform PT/VT-2 examination. Segment RC-039 11448-WMKS-0102A3Z 1-07 2"-RC-200-1502 3 R-A Rl.12 IA y PT Relief Request Redsion 0 Conunents SOCKET WELD, (WEPSOK). RBIS! NOTE: Perform PT examination. Segment RC-039 l 1448-WMKS-0102AZ-1 1-0IDM 29"-RC-7-2501R R-A Rl.11 IA y UT Auto Relief Request SR-001 Re,*ision 0 Conunents REACTOR VESSEL - NOZZLE TO SAFE END BUTT WELD. Per Relief Request Segment RC-003 (SR-001) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform UT examination. 11448-WMKS-0102AZ-1 l-17DM 27'1,-RC-9-2501R 3 R-A RI.I I IA y Uf Auto Relief Request SR-001 Revision 0 Conunents REACTOR VESSEL- NOZZLE TO SAFE END BlfTT WELD. Per Relief Request Segment RC-015 (SR-00 I) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform UT examination. 11448-WMKS-0103A2-1 1-02 6"-SHP-45-60 I 3 R-A Rl.11 2A y UT/MT Relief Request Revision 0 Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perfonn l 1TtMT Segment MS-010 examination. RBISI.Plan Sorted by Dr:t\\mg and !\lark No., SPSU13 Database Page 6 of 14 PrintDate: 102/*9'.'

Drawing No.

              *                         !\lark No.              Line Number

• Period Catego11* Item No. ISi Class Credit l\lethod 11448-WI\IKS-O 117.-\1-1 1-06 14"-RH-1-1502 2 R-A Rl.16 IA y Fr Relief Request Re,*ision 0 Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perform L'T Segment Rll-002 examination.

11448-WI\IKS-0117.-\2 1-45 10"-RH-7-602 3 R-A Rl.16 2F y L'T Relief Request Re\'lsion 0 Comments CIRCUI\IFERENT!:\L PIPING WELD, (\\'EPCB). RBIS! NOTE: Perfom1 L'T Segment Rll-003 examination. 11448-WI\IKS-0118Al 0-13 6"-WAPD-2-601 2 R-A RI.I I 2A y UT/1\IT Relief Request Re\'ision 0 Comments CIRCUMFERENTIAL PIPING WELD (WEPCB) 3/8 in. & > nominal wall Segment AF\\'-015 thickness. RBIS! NOTE: Perfom1 L'T/PT or L'T/1\IT examination. 11448-WMKS-0118.-\2-1 1-I\IOV-FW-151F 3"-WAPD-10-601 R-A RI.I I 28 y L'TII\IT Relief Request Re,*ision 0 Comments CIRCL11\IFERENTIAL PIPING WELD, (WEPCB). RBIS! Note: Perform L'TiPT or Segment AFW-016 L'T/1\IT on the weld at Yal\'e 1-1\IOV-FW-15 lF. The weld is on the same side ofthe valve as support 1-WAPD-H021A 11448-WI\IKS-0118A2-I 1-I\IOV-FW-151F 3"-WAPD-10-601 R-A RI.I I 28 y L'Til\lT Relief Request Re,*ision 0 Comments CIRCL11\IFERENTIAL PIPING WELD, (WEPCB). RBIS! Note: Perfonu L'T/PT or Segment Af\\'-017 L1T 11\IT on the weld at \'alve I-I\IOV-FW-151F. l11e weld is on the same side ofthe valve as support l-\\'APD-H022. 11448-WI\IKS-0118A2-2 1-FW-58 3"-WAPD-11-601 R-A Rl.11 28 y L'T'PT Relief Request Re\'lsion 0 Comments RBIS! Note: Perform l'T/PT or L'T/l\lT on the weld at \"3l\'e I-FW-58. The weld is Segment AFW-018 on the same side of the valve as support 1-WAPD-H006. 11448-WMKS-0118.-\2-2 1-FW-I\IOV-1518 3"-WAPD-14-601 R-A Rl.11 28 y UT'PT Relief Request Re,*ision 0 Comments RBIS! Note: Perform L'T/PT or L'T/1\IT on the weld at \'alve 1--FW-MOV-1518. Segment AF\\'-019 The weld is on the same side ofthe valve as valve 1-FW-93. 11448-WI\IKS-0! 18Gl-1 1-FW-142 6"-\\'APD-3-60 I R-A RI.13 3E y L'T Thickness Relief Request Re,*ision 0 Comments RBIS! Note: Perform L'T thickness examination at low-point, I" square area on line Segment AFW-004 number 6"-WAPD-3-601 prior to check valve I-FW-142. 11448-WMKS-O! l8Gl-1 1-FW-157 4"-WAPD-5-601 2 R-A RI.13 3E y UT Thickness Relief Request Re,*ision 0 Comments RBIS! Note: Perfonu L'T thickness examination at low-point, I" square area on line Segment .-\FW-005 number 4"-WAPD-5-601 prior to check valve 1-FW-157. 11448-WMKS-0! 18Gl-l 1-FW-172 4"-W APD-7-60 I 3 R-A RI.13 3E y L'T Thickness Relief Request Re,ision 0 Comments RBIS! Note: Perform UT thickness examination at low-point, 1" square area on line Segment AFW-006 number 4"-W APD-7-601 prior to check valve 1-FW-172. 11448-WMKS-0122.-\l 1001 6"-RH-20-152 3 R-A RI.16 2F Relief Request Re\'ision 0 Comments RBIS! NOTE: Perform PT examination on a 1" square area on line 6:-RI 1-20-152 Segment Rll-011 adjacent to integral attachment weld H014-I. 11448-WMKS-0122.-\l 2-09 6"-RH-14-602 R-A Rl.16 2A y UT Relief Request Re,*lsion 0 Comments CIRCL11\IFERENTIAL PIPING WELD (WEPCB). 3/8 in. & > nominal wall Segment RH-003B thickness. RBIS! NOTE: Perform L'T examination. RBISL Plan Sorted by Dra\\ing and !\lark No., SPSU13 Database Page 7of 14 Print Date: 10*21*97

Dra'l\ingNo.

• l\lark No. Line Numher
• Period CategorJ Item No. ISi Class Credit l\lethod 11448-Wl\IKS-0122Al 3-AF 6"-RH-20-152 3 R-A RI.16 2F y l 1T Relief Request Revision 0 Comments CIRCUMFERENTIAL PIPING WELD (\\'EPCB). RBIS! NOTE: Perfonn VT Segment RH-Oil examination.

11448-Wl\!KS-0!22Hl 1-02 6"-RC-16-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCL'l\!FERENTIAL PIPING WELD, (\\'EPCB). RBIS! NOTE: Perfom1 l 'T/PT Segment RC-016 examination. I 1448-\\'MKS-0122H I 1-08 6"-RC-16-1502 R-A RI.I I IA y l'T/PT Relief Request Revision 0 Comments CIRCUMFERENTIAL PIPING WELD, (\\'EPCB). Terminal End. 111is weld added Segment RC-016 to plan with Rev. I and replaces weld 1-05 on line 6"-RC-16-1502, 11448-Wl\!KS-0122H I. RBIS! NOTE: Perform l'T/PT examination. 11448-Wl\!KS-O I 22Hl 1-09 6"-RC-16-1502 2 R-A RI.I I IA y L'T/PT Relief Request Revision 0 Comments CIRCUl\lFERENTUL PIPING WELD, (WEPCB). RBIS! NOTE: Perfonn l'T/PT Segment ECC-005 examination. 11448-Wl\!KS-0!22Hl 1-10 6"-RC-16-1502 2 R-A RI.I I IA y l'T/PT Relief Request Re,*ision 0 Comments CIRCUl\!FERENTUL PIPING WELD, (\\'EPCB). RBIS! NOTE: Perfonn UT/PT Segment ECC-005 examination. 11448-WMKS-O ! 22Jl 1-05 6"-RC-21-1502 3 R-A RI.I I IA y l'T/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). RBIS! NOTE: Segment RC-018 Perform UTtPT examination. 11448-Wl\!KS-0122Jl 1-08 6"-RC-21-1502 2 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). Tem1inal End. l11is weld added Segment RC-018 with Rev. I to plan and replaces weld 2-03 on 6"-RC-18-1502, 11448-\\'l\!KS-0 I 22KI. RBIS! NOTE: Perform UT/PT examination. 11448-WMKS-0!22Jl 1-09 6"-RC-21-1502 2 R-A RI.I I IA y lJr/PT Relief Request Re,*ision 0 Conunents CIRCUMFERENTIAL PIPING WELD, (\VEPCB). RBIS! NOTE: Perform l'T/PT Segment ECC-007 examination. 11448-Wl\IKS-0!22Ji I-IO 6"-RC-21-1502 2 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perform l'T/PT Segment ECC-007 examination. I 1448-WMKS-0122Kl 2-03 6"-RC-18-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB). This weld removed with Rev. Segment RC-017 to plan and replaced with weld 1-08 on line 6"-RC-21-1502, 11448-Wl\!KS-0!22JI. RBIS! NOTE: Perform UT/PT examination. I 1448-Wl\IKS-0122Kl 2-08 6"-RC-18-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Terminal End. This weld added Segment RC-017 with Rev. I to plan and replaces weld 2-07 on line 6"-RC-18-1502, 11448-Wl\IKS-0122KI. RBIS! NOTE: Perfonn ITT/PT examination. RBISI. Plan Sorted by Dra'l\ing and l\lark No., SPSU13 Database Page 8 of 14 Print Date: /0:21197

Draning No.

              *                       !\lark No.               Line Number

• Period Category Item No. ISi Cl:tss Credit l\lethod 11448-Wl\lKS-0122Kl 2-09 6"-SI-48-1502 2 R-..\ RI.I I 1.-\ y LTT PT Relief Request Re\"ision 0 Comments CIRCUI\IFERENTUL PIPING WELD, (WEPCB). RBISI NOTE: Pcrfom1 LTT/PT Segment ECC-006 examination.

11448-WMKS-0122Kl 2-10 6"-Sl-48-1502 2 R-..\ RI.I I I..\ y l 1T/PT Relief Request Re\"ision 0 Comments CIRCUI\IFERENTI..\L PIPING WELD, (WEPCB). RBIS! NOTE: Perfonu LTT.PT Segment ECC-006 examination. 11448-WI\IKS-0123QI 0-05 l 2"-CS-2-153 2 R-A RI.II 2..\ y UT/PT Relief Request Re\"ision 0 Comments Circumferential Piping Weld, (\\'EPCB) 3/8 in. & > nominal wall thickness. RBIS! Segment CS-001 NOTE: Perfom1 ll"f/PT examination. 11448-WMKS-0124 ..\1-1 18 3"-RC-61-1502 3 R-..\ RI.I I I..\ y PT Relief Request Re,*ision 0 Comments SOCKET WELD, (WEPSOK). RBIS! NOTE: Perfonu PT examination. Segment RC-059 11448-WMKS-O 124..\ 1-1 19 3"-RC-35-1502 3 R-..\ RI.I I I..\ y PT Relief Request Re,*ision 0 Conunents SOCKET WELD, (WEPSOK). RBIS! NOTE: Perform PT examination. Segment RC-058 11448-Wl\lKS-0125 ..\1-2 3-07 J '.,"-RC-105-1502 3 R-..\ RI.I I I..\ y PT Relief Request Re,*ision 0 Conunents SOCKET WELD, (\\'EPSOK), Tenuinal End. RBISI NOTE: Perfonu PT Segment RC-060..\ examination. 11448-WMKS-0127CI 3-BF 10"-Sl-84-152 3 R-..\ RI.I I 2F y l 1TIPT Relief Request Re,*ision 0 Comments CIRCUI\IFERENTI..\L PIPING WELD, (WEPCB) RBIS! NOTE: Perform LTT/PT Segment LHl-008 examination. 11448-Wl\IKS-O I 27C I 3-JF IO"-Sl-150-153 3 R-..\ RI.I I 2F y l 1T'PT Relief Request Re,*ision 0 Comments CIRCUI\IFERENTIAL PIPING WELD, (\\'EPCB). RBIS! NOTE: Perfom1 ll"f/PT Segment LHl-009 examination. 11448-WMKS-O l 27E2 1-V 8"-SI-14-153 3 R-..\ RI.II 2F y LTTIPT Relief Request Re,*lslon 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB) RBISI NOTE: Perform UT/PT Segment LHl-007 examination. 11448-Wl\IKS-O 127G 1-1 1-ADF 6"-Sl-18-152 3 R-A RI.II 2F y vT-2 Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). RBISI NOTE: Perform vT-2 Segment LHl-018 examination. l 1448-WMKS-0127Gl-l 1-AKF 6"-Sl-19-152 3 R-..\ RI.I I 2F y vT-2 Relief Request Re,*ision 0 Comments CIRCUI\IFERENTI..\L PIPING WELD, (WEPCB). RBIS! NOTE: Perfom1 \*T-2 Segment LHl-018 examination. 11448-WMKS-0127Gl-l 1-AQF 6"-SI-78-152 3 R-..\ RI.I I 2F y UT/PT Relief Request Re\"lsion 0 Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perform UT/PT Segment LHl-018 examination. I 1448-WMKS-0127Gl-I 1-AUF 6"-Sl-78-152 3 R-..\ RI.I I 2F y VT-2 Relief Request Re,*lsion 0 Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perfonu vT-2 Segment LHi-018 examination. RBISI,Plan Sorted by Drawing and Mark No., SPSU13 Database Page 9of /4 Print Date: IO 21 9"'

Draning No.

• l\IarkNo. Line Number
• Period Categol)* Item No. ISi Class Credit l\lethod 11448-WMKS-0127G2 1-APF I O"-Sl-6-153 2 R-A RI.I I 2F y UT/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld. RBISINOTE: Perfonn l 1T'PT examination. Segment IIHl-001 11448-WMKS-0127G2 1-AYF 8"-SI-7-152 2 R-A RI.I I 2F y UT/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD. RBIS! NOTE: Perform UT/PT Segment HHl-002 examination.

11448-Wl\lKS-0127G2 1-BNF 8"-CH-206-152 2 R-A RI.I I 2F y UTIJ'T Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). RBIS! NOTE: Perform UT/PT Segment HHl-003 examination. 11448-\\'l\lKS-O l 27Jl 1-02 6"-RC-17-1502 3 R-A RI.I I IA y UT/PT Relief Req nest Re,*ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB). RBISI NOTE: Perform UT/PT Segment RC-041 examination. I 1448-Wl\!KS-0127JI 1-04 6"-RC-17-1502 R-A RI.I I IA y l'"T/PT Relief Request Re\'ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD 4 in. NPS & >, (\\'EPCB). RBIS! NOTE: Segment RC-041 Perfonu UT/PT examination. 11448-\Vl\lKS-0127Jl 1-05 6"-RC-17-1502 2 R-A RI. I I IA y UTiPT Relief Request Re,*ision 0 Comments CIRCUl\lFERENTIAL PIPING WELD, (\VEPCB). RBIS! NOTE: Perfom1 UT/PT Segment ECC-001 examination. 11448-\Vl\!KS-Ol27JI 1-09 2"-SI-74-1502 2 R-A RI.I I IA y PT Relief Request Re\'ision 0 Comments SOCKET WELD, (WEPSOK). RBIS! NOTE: Perform PT examination. Segment ECC-001 11448-Wl\!KS-0127J2 1-02 6"-RC-19-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB). 4 NPS in. & >. RBIS! NOTE: Segment RC-042 Perfonn UT/PT examination. 11448-WMKS-0127J2 1-04 6"-RC-19-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (\VEPCB). Terminal End. Weld added with Segment RC-042 Rev. I to plan, and replaces weld 1-03 on line 8"-RC-l l-2501R. RBIS! NOTE: Perform UT/PT examination. 11448-Wlv!KS-0127J2 1-05 6"-RC-19-1502 2 R-A RI.I I IA y UT/PT Relief Request Re\'ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB). 4 NPS in. & >. RBIS! NOTE: Segment ECC-002 Perform UT/PT examination. I 1448-WMKS-012712 1-06 6"-RC-19-1502 2 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB). 4 NPS in. & >. RBIS! NOTE: Segment ECC-002 Perform UT/PT examination. 11448-Wl\lKS-012713 1-02 6"-RC-20-1502 3 R-A RI.I I IA y UT/PT Relief Request Re,*ision 0 Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). NPS 4 in. & >. RBIS! NOTE: Segment RC-043 Perform UT/PT examination. RBISI, Plan Sorted by Draning and l\lark No., SPSU13 Database Page JO of 14 Print Date: JO 21 97

Draning No.

• Mark No. Line Number
• Period Category Item No. ISi Class Credit l\lethod 11448-WMKS-O 12713 1-03 6"-RC-20-1502 2 R-A Rl.11 IA y l 1T 1PT Relief Request Re\'ision 0 Conunents CIRCU!,!FERENTIAL PIPING WELD, (WEPC8). Terminal End. This weld added Segment RC-043 to plan with Rev. I and replaces weld 1-04 on line 6"-RC-20-1502, 11448-WMKS-012713. RBIS! NOTE: Perfom1 UT/PT examination.

11448-WMKS-0!27.13 1-04 6"-RC-20-1502 2 R-A Rl.11 IA y UT!PT Relief Request Re,*ision 0 Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB). This weld remo\*ed with Re\'. Segment ECC-003 to plan, and was replaced with weld I -03 on line 6"-RC-20-1502, I 1448-Wl\lKS-012713. RBIS! NOTE: Perfonn UT/PT examination. I 1448-Wl\lKS-012713 1-10 2"-SI 1502 2 R-A Rl.l I IA y PT Relief Request Re\'ision 0 Comments SOCKET WELD, (\VEPSOK). RBIS! NOTE: Perform PT examination. Segment ECC-003 I 1448-WMKS-0127.13 2-01 6"-Sl- I 53-1502 3 R-A Rl.l I 2A y UT,PT Relief Request Re,*ision 0 Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPC8). 3/8 in> & > Nominal Wall Segment LHl-010 Thickness. RBIS! NOTE: Perform UT/PT examination. I I 448-\\'l\lKS-1022A 10 1001 2 1 ,"-CC-205-151 R-A RI.I I 38 y l'T/1\IT Relief Request Re,*ision 0 Comments RBIS! Note: Perform UT/PT or UT/1\IT examination on weld nearest lo reactor Segment CC-033 shroud cooling cools on line 2\i,"-CC-205-151. Note there is no mark/weld number I 00 I, this is used to sort the ISi database only. I 1448-WMKS-1022:\2 1001 3"-CC-98-151 R-A RI.II 38 y UT/1\IT Relief Request Re\'lsion 0 Conunents RBIS! Note: Perform lff/PT or UT/1\IT on the !st weld from pump 1-RC-P-IA on Segment CC-025 line 3"-CC-98-151. Note there is no mark/weld number I 00 I, this is used to sort the ISi database only. 11448-Wl\lKS-!022A.2 1002 !W'-CC-97-151 R-A RI.I! 38 y PT Relief Request Re,*ision 0 Conunents RBIS! Note: Perform PT examination on the !st weld from pump 1-RC-P-!A on line Segment CC-025 1W'-CC-97-151. Note there is no mark/weld number 1002, this is used to sort the ISi database only. I 1448-WMKS-1022A5 1001 1"-CC-95-151 R-A Rl.11 38 y PT Relief Request Re\'ision 0 Conunents RBIS! Note: Perform PT examination on the 1st weld from pump 1-RC-P-IB on line Segment CC-030 I "-CC-95-151. Note there is no mark/weld number 100 I, this is used to sort the ISi database only. 11448-WMKS-1022A7 1001 3"-CC-91-151 R-A Rl.11 38 y UT/MT Relief Request Re,*ision 0 Conunents RBIS! Note: Perform UT/PT or UT/MT on the weld on 3" side of3"x2\i, reducer on Segment CC-030 line 3"-CC-91-151. Note there is no mark/weld number 1001, this is used to sort the ISi database only. 11448-WMKS-!022.-\9 1001 1"-CC-84-151 R-A Rl.11 38 y PT Relief Request Re,*ision 0 Conunents R81S1Note: Perform PT examination on weld at tee from line 1"-CC-84-151 to Segment CC-033 branch line goint to valve l-CC-RV-115C .. Note there is no mark/weld number 1001, this is used to sort the ISi database only. RBISI, Plan Sorted by Draning and Mark No., SPSU13 Database Page 11 of 14 Print Date: 10*2197

Dra'l\ing No.

                *                         !\lark No.               Line Number

• Period Categm1* Item No. ISi Class Credit l\lethod 11448-Wl\IKS-!022A9 1002 1"-CC-84-151 R-A RI.I I 38 y PT Relief Request Revision 0 Comments RBIS! Note: Perform PT examination on weld at tee on line 1"-CC-84-151 to branch Segment CC-033 line goint to \*al\'e I-CC-RV-115C. The weld to examine will he on the \'al\'e (J-CC-

76) side of the tee. Note there is no markiweld number I 002, this is used to sort the ISi database only.

11448-Wl\lKS-1022,\9 1003 l "-CC-84-151 R-A RI.I I 38 y PT Relief Request Revision 0 Conunents RBIS! Note: Perfonn PT examination on weld at tee on line 1"-CC-84-151 to branch Segment CC-033 line goint to valve l-CC-RV-115C. The weld to examine will be on the pump (l-RC-P-1 C) side of the tee. Note there is no marklweld number I 003, this is used to sort the ISi database only. 11448-Wl\lKS-! IOl:-\3 0-03 12"-CS-1-153 2 R-A RI.I I 2,\ y LT"f/PT 1 Relief Request Revision 0 Comments Circumferential Piping Weld, (WEPC8) 3 8 in. & > nominal wall thickness. RBIS! Segment CS-002 NOTE: Perform LT"f/PT examination. 11448-Wl\lKS-I 101:-\5 1-03 12"-RS-8-153 R-A Rl.16 2,\ y LT"f Relief Request Re,*ision 0 Comments CIRCUI\IFERENTI.-\L PIPING WELD, (WEPC8). 3.'8 in. & > Nominal Wall Segment RS-003..\ 1l1ickness. R8ISI NOTE: Perfonn L'T examination. 11448-Wl\lKS-I IOl..\5 1-06 12"-RS-7-153 3 R-A RJ.16 2A y l TT Relief Request Re,*ision 0 Comments CIRCUl\ffERENTI.-\L PIPING WELD, (WEPC8). 318 in. & > Nominal Wall Segment RS-004..\ Thickness. RBISI NOTE: Perform LT"f examination. 11448-Wl\lKS-110585 1-06 3"-CH-69-1503 2 R-A RI.I I 2:\ y UT11'T Relief Request Re,*ision 0 Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. RBISI Segment HHI-004C NOTE: Perform UT/PT examination. 11448-Wl\lKS-110585 2-Al\1-A 3"-CH-2-1503 2 R-A RI.I I 2,\ y LT"f/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. RBISI Segment HHl-005C NOTE: Perform UT/PT examination. 11448-Wl\lKS-! 105B5 2-AP 3"-CH-2-1503 2 R-A RI.I I 2,\ y L'TIPT Relief Request Revision 0 Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. RBISI Segment HHl-005,\ NOTE: Perform UT/PT examination. 11448-Wl\lKS-I !05B5 2-AS 3 "-CH-3-1503 2 R-A RI.I I 2,\ y LT"f/PT Relief Request Re,*lsion 0 Conunents Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. This Segment HHl-006C weld added to plan with Rev. 2 to plan to replace weld 2-A W, which was preserviced during the 1994 refueling outage. RBISI NOTE: Perform UT/PT examination. I I 448-Wl\lKS- I I 05 85 2-,\Z 3"-CH-3-1503 2 R-A RI.I I 2,\ y LT"f/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. R8ISI Segment HI-!l-006:\ NOTE: Perform L'T/PT examination. I 1448-Wl\lKS-! 105B5 2-N 3"-CH-2-1503 3 R-A RI.I I 2A y L'T.'PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. RBIS! Segment HHl-008 NOTE: Perform LTT/PT examination. RBISl Plan Sorted by Dra'l\ing and !\lark No., SPSU13 Database Page 12of 14 Prine Date: 10'2 l 9~

Draning No.

• l\lark No. Line Number
• Period Category Item No. ISi Class Credit Method 11448-Wl\lKS-110589 1-BCF 4"-CH-89-1503 3 R-A RI.I I 2,\ y UT/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. RBISI Segment HHl-009 NOTE: Perfonn UT/PT examination.

11448-Wl\lKS-1 !06.-\4 1-14 3"-SI-70-1503 3 R-A Rl.11 2.-\ y UT/PT Relief Request Revision 0 Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall Thickness. Segment HHI-012..\ RBIS! NOTE: Perfom1 UT/PT examination. 11448-WMKS-1 !06.-\4 3-47 2"-SI-71-1503 3 R-A RI.I I 2.-\ y PT Relief Request Re,*ision 0 Comments Socket Weld, (WEPSOK). RBIS! NOTE: Perform PT examination. Segment HHI-012..\ 11448-WMKS- l l 06.-\4 5-AF 3"-Sl-70-1503 3 R-A RI.I I 2,\ y UT!PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall TI1ickness. Segment HHI-011 RBIS! NOTE: Perfonn L1T/PT examination. 11448-WMKS-1106..\7 1-13 12"-Sl-1-153 3 R-A RI.I I 2,\ y Lr[JPT Relief Request Re,*ision 0 Comments CIRCUl\ffERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall Segment LHI-004 thickness. RBIS! NOTE: Perform UT/PT examination. 11448-Wl\lKS-1106.-\7 1-15 12"-Sl-2-153 3 R-A RI.I I 2.-\ y Lrr/PT Relief Request Re,*ision 0 Comments CIRCLTl\ffERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall Segment LHI-003 thickness. RBIS! NOTE: Perform UT/PT examination. 11448-Wl\lKS-! 106.-\7 2-18 12"-Sl-5-153 2 R-A RI.II 2.-\ y UT/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness. RBISI Segment ECC-000 NOTE: Perform UT/PT examination. 11448-Wl\lKS-! !06.-\7 4-02 !O"-SI-105-153 2 R-A Rl.16 2F y Lrf/PT Relief Request Re\"ision 0 Comments CIRCUl\lFERENTI.-\L PIPING WELD, (WEPCB). RBIS! NOTE: Perform UTIPT Segment LHI-002 examination. 11448-WMKS-l 106..\7 6-04 I O"-SI-106-153 2 R-A Rl.16 2F y UT/PT Relief Request Re,*ision 0 Conunents CIRCUl\ffERENTI.-\L PIPING WELD, (WEPCB) RBIS! NOTE: Perform UT/PT Segment LHI-001 examination. I 1448-Wl\lKS-1106Bl 0-25 3"-SI-146-1503 3 R-A RI.I I 2.-\ y UT/PT Relief Request Revision 0 Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. RBIS! Segment HHI-013 NOTE: Perform UT/PT examination. I 1448-WMKS-I !06B2 0-18 3"-SI-147-1503 3 R-A RI.I I 2,\ y UT/PT Relief Request Revision 0 Comments Circumferential piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. RBIS! Segment HHI-015 NOTE: Perform UT/PT examination. 11448-WMKS-l 106B5 0-16 3"-SI-72-1503 3 R-A RI.I I 2.-\ y UT/PT Relief Request Re,*ision 0 Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. RBIS! Segment HHI-017 NOTE: Perform UT/PT examination. RBIS~ Plan Sorted by Draning and l\larkNo., SPSU13 Database Page 13 of 14 Print Date: I 0/21 /97

Attachment 5 Currently Scheduled ISi Program Examinations

Dra'l\ing No.

              *                         !\lark No.              Line Number

• Pe1iod Category Item No. ISi Class Credit l\lethod I 1448-WMKS-I 10686 0-24 3 "-Sl-70-1503 3 R-A RI. I I 2A y l'T/PT Relief Request Re,*isiou 0 Comments Circumferential Piping Weld, (\\'EPCB). > 0.200 in. nominal ,,*all thickness. RBIS! Segment HHl-010 NOTE: Perfonn UT/PT examination.

UFSAR-FIG-148-16 1001 4 "-SLPD-50-153 R-A RI.I I NC y l'T/PT Relief Request Re,*ision 0 Comments RBJSI Note: Perform l 'T/PT on the weld nearest to the charging power cable tray on Segment AS-I line 4"-SLPD-50-153, as shown on UFSAR Figure 148-16. Note there is no mark/weld number IOO l, this is used to sort the ISi database only. UFSAR-FIG-148-16 1002 6"-SA-21 R-A RI.I I NC y l'T/MT Relief Request Re,*ision 0 Comments RBIS! Note: Perform l 1T/PT or UT/l\IT on the weld nearest to the component Segment AS-2 cooling water pumps on line 6"-SA-21 ( carbon steel), as shO\m on l 1FSAR Figure 148-16. Note there is no mark/weld number 1002, this is used to sort the IS! database only. Record Count: 142 RBIS~ Plan Sorted by Dra'l\ing and Mark No., SPSUI3 Database Page 14 of 14 Print Dare: 1021:9-:

Draning Number 11448-Wt-.lKS-0!22Ll Segment ACC-00 I Revision Relief Request Mark Number 1-14 Linc Number 12"-Sl-45-1502

• Period Category B-J Item No.

B9.I I ISi Class IA Augrnt No

                                                                                                                                                                                                      *l\lethod UT/PT Comments       CIRCUMFERENTIAL PIPING WELD 4 in. NI'S & >..c.,_,(_\\_'E_P_C_B-'-'),'-T_e_n_m_*n_al_E_n_d_.- - - - - - - - -

11448-Wt-.IKS-0122Ll 1-13 !2"-Sl-45-1502 I B-J B9.l I IA No UT/PT Segment ACC-00 I Revision Relief Req nest Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB), Tenninal End. Total Period: 2 11448-Wt-.lKS-O l 22Ll 1-16 12"-Sl-45-1502 2 B-J B9.II IA No UT1PT Segment ACC-00 I Revision Relief Req nest Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: l Total Segment: 3 11448-Wt-.IKS-O 122DI 1-14 12"-Sl-46-1502 B-J B9.l l IA No UT/PT Segment ACC-006 Revision Relief Req nest Comments CIRCUMFERENTIAL PIPING WELD4 in. NPS & >, (WEPCB), Terminal End. 11448-Wl\lKS-0!22Dl 1-13 12"-Sl-46-1502 1 B-J B9. I I IA No FfiPT Segment ACC-006 Revision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB), Tenninal End. Total Period: 2 l 1448-Wt-.lKS-0122Dl 1-19 12"-Sl-46-1502 3 B-J B9.l l IA No UT:PT Segment ACC-006 Revision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: 1 Total Segment: 3 11448-Wl\!KS-O 122.-\2 1-08 12"-Sl-47-1502 B-J B9.l I IA No UT/PT Segment ACC-011 Revision Relief Request Comments CIRCUMFERENTI..\L PIPING WELD 4 in. NI'S & >, (WEPCB). Terminal End. 11448-WMKS-0122A2 1-09 l 2"-Sl-47-1502 I B-J B9.ll IA No UT/PT Segment ACC-011 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NI'S & >, (WEPCB). Terminal End. Total Period: 2 11448-WMKS-O i 22A2 1-12 12"-SI-47-1502 2 B-J 89.11 IA No UT/PT Segment ACC-0 I I Revision Relief Request Comments CIRCUl\IFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: 1 Total Segment: 3 11448-Wl\lKS-0118A2-1 0-35 6"-W APD-1-601 C-F-2 C5.5 I 2A No l'T/t-.lT Segment AFW-014 Revision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall TI1ickness. Total Period: 1 Total Segment: l 11448-WMKS-0118Al 0-13 6"-WAPD-2-601 2 C-F-2 CS.SI 2A No UT/MT Segment . AFW-015 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD (WEPCB) 3/8 in. & > nominal wall thickness. RBIS! NOTE: Perform UT/PT or UT/MT examination. Total Period: 1 Segments on Gass 1 _Gass 2 piping welds, Sorted hy Segment (SPSU13 Datahase) Page I of 3: Print Date: 10*21 ,'97

Total Segment: Dra\\ing Number l\Iark Nwnber Line Number

• Period Catego~* Item No. ISi Oass Augmt

                                                                                                                                                                                                    *l\lethod 11448-Wl\lKS-0118A2-I                                                0-34            6"-WAPD-1-601                                  C-F-2         C5.51          2A                    No Segment    AFW-016        Re\"ision                     Relief Request                 Comments       CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness.

Total Period: 11448-Wl\IKS-O ! 18A2-1 0-27 6"-WAPD-51-601 2 C-F-2 C5.51 2A No UT/MT Segment AFW-016 Re\"ision Relief Request Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. Total Period: I Total Segment: 2 11448-Wl\lKS-0118A2-I 0-13 6"-WAPD-50-601 3 C-F-2 C5.5 I 2A No Segment AFW-028 Re,*ision Relief Request Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. 11448-Wl\IKS-0! 18A2-1 0-14 6"-WAPD-50-601 3 C-F-2 C5.51 2A No l 'T/l\!T Segment AFW-028 Rc,*ision Relief Request Comments CIRCL'l\IFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall 1l1ickness. Total Period: 2 Total Segment: 2 11448-Wl\IKS-O!OOAIZ 1-06 I 1'2"-CH-97-1502 B-J 89.40 IA No PT Segment CH-008 5 Relief Request Comments SOCKET WELD, (WEPSOK). Removed from plan with Rev. 3 to plan. Weld replaced by weld 1-0 I on same line No. & drawing No. New with Rev. 5 to plan: Added weld 1-06 back into the plan to replace weld 1-0 I, which is inaccessible. Total Period: 11448-Wl\IKS-O I OOAI Z 1-01 1'*,"-CH-97-1502 2 8-J B9.40 IA No PT Segment CH-008 Re,*ision 8 Relief Request SR-014 Conunents SOCKET WELD, (WEPSOK). New to plan with Rev. 3 to plan. Designated weld as tenninal end due to licensing conc~ms (John Lewis). See memo Paul to Lewis of8-16-94. Replaces weld 1-06 on same line No.

                                                                                                     & drawing No. New with Rev. 5 to Plan: Weld 1-01 reported as being inaccessible by Dan Jensen on 9                                                                                                       95. Weld 1-06 added back into plan in order to keep the weld selection percentages the same. Relief Request SR-014 submitted to report that tem1inal end weld (weld 1-01) cannot be examined unless the pump is disassembled. New with Rev. 8 to plan: Weld is scheduled for exam. during the 1997 refueling outage because the pump was disassembled. RBISI Note: Perfonn PT/VT-2 examination.

Total Period: l Total Segment: 2 11448-Wl\!KS-OIOIAIZ 1-06 I \~"-CH-95-1502 2 8-J 89.40 IA No PT Segment CH-009 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\lKS-O!OIAIZ 1-04 I W'-CH-95-1502 2 8-J 89.40 IA No PT Segment CH-009 Re,*ision 9 Relief Request SR-014 Conunents SOCKET WELD, (WEPSOK). New with Rev. 9 to plan: 1l1is weld is added to the plan to replace weld J-OI on the same drawing and line number. This weld is an additional weld and is scheduled for examination to ensure that 25% of examination category 8-J welds are examined in the event that weld 1-0 I is not examined. Weld 1-01 is inaccessible unless the RCP main flange is disassembled. See reliefrequest SR-014. RBIS! NOTE: Perform PT & VT-2 examination. 11448-WMKS-OlOIAIZ 1-01 I W'-CH-95-1502 2 8-J 89.40 IA No PT Segment CH-009 Re\"ision 3 Relief Request SR-014 Comments SOCKET WELD, (WEPSOK). Terminal End designator add with Rev. 3 to plan. RBIS! NOTE: Perfonn PT & VT-2 examination. Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 2 of3'"' Print Date: IO 2197

Draning Number J\Iark Number Line Nmnber

                                                                                                    *Total Period: 3 Period      Category            Item No.               [SI Class         Augmt
                                                                                                                                                                                                             *l\lethod 11448-\Vl\IKS-O!OIAIZ                                                1-01            I \*,"-CH-95-1502                     3       B-J                B9.40                 IA                     No          PT Segment    CH-009         ReYision       9              Relief Request      SR-014    Comments         New with Rev. 9 to plan: This weld ( 1-0 I) is inaccessible unless the RCP main flange is disassembled. This weld is scheduled in period 3 to ensure that the weld is examined if the RCP main flange is disassembled. See

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _re_l_ie_f_re~q~u_es_t_S_R_-0_1_4_._R_B_I_S_I_N_O_T_E_:_P_e_rfc_om_1_PT_,_ 1\_*1_*-_2_e_xa_n_1i_n_at_io_n_._ _ _ _ _ _ _ _ _ _ _ _ __ Total Period: l Total Segment: 4 l 1448-Wl\IKS-0102AIZ 1-02 I '.,"-CH-93-1502 2 B-J B9.40 IA No PT Segment CH-010 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\IKS-0!02AIZ 1-09 2"-CH-93-1502 2 B-J 89.40 IA No PT Segment CH-0 IO ReYision Relief Request Comments SOCKET WELD, (WEPSOK). I 1448-Wl\!KS-0102AIZ 1-01 1',"-CH-93-1502 2 B-J 89.40 IA No PT Segment CH-0 IO ReYision 9 Relief Request SR-014 Conunents SOCKET \\'ELD, (WEPSOK). New with Re\*. 9 to plan: This weld is added to the plan to ensure weld 1-0 I is examined if the RCP main flange is disassembled. Weld 1-01 is inaccessible unless the RCP main flange is disassembled. See relief request SR-014. RBIS! NOTE: Perfom1 PT & VT-2 examination. Total Period: 3 11448-Wl\!KS-0!02AIZ 1-04 1',"-CH-93-1502 3 B-J B9.40 IA No PT Segment CH-0 IO Re,*ision 9 Relief Request SR-014 Conunents SOCKET WELD, (WEPSOK). New with Re\'. 9 to plan: This weld is added to the plan to replace weld I-OI on the same drawing and line number. This weld is an additional weld and is scheduled for examination to ensure *that 25% of examination category B-J welds are examined in the event that weld 1-0 I is not examined. Weld 1-01 is inaccessible unless the RCP main flange is disassembled. See relief request SR-014. RBIS! NOTE: Perform PT & VT-2 examination. 11448-Wl\IKS-0102AIZ 1-01 1W' -CH l502 3 B-J B9.40

                                                                                                                                                                   - -IA    - - - - - - -No       - - - - -PT- - - - -

Segment CH-OIO Revision 3 Relief Request SR-014 Comments SOCKET WELD, (WEPSOK). Added to plan with Rev. 3 to plan. Designated weld as terminal end due to licensing concerns (John Lewis). See memo Paul to Lewis of 8-16-94. Replaces weld 1-35 on 11448-W.l\IKS-0102A2Z. RBIS! NOTE: Perform PT & VT-2 examination. Total Period: 2 Total Segment: 5 11448-Wl\IKS-O!OOAIZ 1-18 2"-CH-97-1502 B-J B9.40 IA No PT Segment CH-Oil Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\IKS-O!OOAIZ 1-17 2"-CH-97-1502 I B-J B9.40 IA No PT Segment CH-Oil ReYision Relief Request Conuuents SOCKET WELD, (WEPSOK). Total Period: 2 Total Segment: 2 11448-Wl\IKS-OIOIAIZ 1-16 2"-CH-95-1502 2 B-J B9.40 IA No PT Segment CH-012 Re,*isiou Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\IKS-O IO I Al Z 1-21 2"-CH-95-1502 2 B-J B9.40 IA No PT Segment CH-012 Re,*ision Relief Request Comments SOCKET WELD, (\l,'EPSOK). Total Period: 2 Segments on Class l .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page3 of 3: Print Dare: JO 21:9-:C

Dra\\ing Number Total Segment: 2

                                                                      !\lark Number Line Nmn her               Period  Category      Item No.      ISi Class      Augmt

• l\lethod 11448-W!\!KS-O 102:\IZ 1-13 2"-CH-93-1502 2 8-J 89.40 IA No PT Segment CH-013 Re\"ision Relief Request Comments SOCKET WELD, (WEPSOK).

11448-W!\!KS-0102AIZ 1-21 2"-CH-93-1502 2 8-J 89.40 IA No PT Segment CH-013 Re\"ision Relief Request Conunents SOCKET WELD, (WEPSOK). 11448-\\'1\!KS-0!02:\IZ 1-17 2"-CH-93-1502 2 8-J 89.40 IA No PT Segment CH-013 ReYision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 3 Total Segment: 3 11448-WMKS-OIOOA7Z 1-38 2"-CH-8-1503 8-J 89.40 IA No PT Segment CH-016 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK), Terminal End. 11448-W!\!KS-O I OOA7Z 0-01 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-016 Re\"ision Relief Request Comments Socket Weld, (WEPSOK) 11448-WMKS-OIOOA7Z 0-05 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-016 Re,*ision Relief Request Comments Socket Weld, (WEPSOK) Total Period: 3 Total Segment: 3 11448-WMKS-O IOOA7Z 1-07 2"-CH-8-1503 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-W!\!KS-OIOOA7Z 1-03 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK). 11448-WMKS-O!OOA6Z 1-15 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET \\'ELD, (WEPSOK) 11448-WMKS-O IO I A3Z 1-08 2"-CH-9-1502 I 8-J 89.21 IA No PT Segment CH-017 Re\"ision Relief Request Conunents CIRCU!\!FERENTIAL PIPING WELD, (WEPC8), < 4 in. NPS, Tern1inal End. 11448-WMKS-OIOOA7Z 1-11 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-O I OOA6Z 1-08 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK), Terminal End. 11448-W1\IKS-OIOOA6Z 1-11 2"-CH-8-1503 I 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK) Total Period: 7 11448-W!\!KS-O!OIA3Z 1-09 2"-CH-9-1502 2 8-J 89.21 IA No PT Segment CH-017 Re\"ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPC8), < 4 in. NPS. 11448-W!\IKS-OIOIA3Z 1-10 2"-CH-9-1502 2 8-J 89.21 IA No PT Segment CH-017 Re\"ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPC8), < 4 in. NPS, Terminal End. 11448-WMKS-O I OOA7Z 1-33 2"-CH-8-1503 2 8-J B9.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page4ofT" Print Date: IO 21. 97

Dr:ming Number I 1448-Wl\IKS-OIOOA7Z Segment CH-017 Revision Relief Request l\lark Numbe1* 1-28 Linc Number 2"-CH-8-1503 Comments

• Period 2

SOCKET WELD, (WEPSOK). Category 8-J Item No. 89.40 IA ISi Class Augmt No

• l\lcthod PT I 1448-Wl\!KS-O JOOA7Z 1-24 2"-CH-8-1503 2 8-J 89.40 IA No PT Segment CH-017 Revision Relief Reit uest Comments SOCKET WELD, (WEPSOK).

Total Period: 5 I 1448-Wl\IKS-OIOIAJZ 1-11 2"-CH-9-1502 3 8-J 89.21 IA No PT Segment CH-017 Re,*ision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPC8), < 4 in. NPS, Terminal End. 11448-Wl\lKS-0!02A3Z 1-19 2"-CH-10-1503 3 8-J 89.40 ),\ No PT Segment CH-017 Revision Relief Re11 uest Conunents SOCKET WELD, (WEPSOK). 11448-Wl\IKS-0102A3Z 1-15 2"-CH-10-1503 3 8-J 89.40 IA No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\!KS-0102A3Z 1-11 2"-CH-10-1503 3 8-J 89.40 I,\ No PT Segment CH-017 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK), Terminal End. 11448-Wl\!KS-O 102A3Z 1-10 2"-CH-10-1503 3 8-J 89.40 IA No PT Segment CH-0 I 7 Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK), Tem1inal End. Total Period: 5 Total Segment: 17 I 1448-\\'l\!KS-0125AIZ 0-AX 2"-CH-68-1502 3 8-J 89.40 IA No PT Segment CH-023 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-0125AIZ 0-AL 2"-CH-68-1502 3 8-J 89.40 IA No PT Segment CH-023 Revision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\IKS-O 125AIZ 0-AT 2"-CH-68-1502 3 8-J 89.40 I,\ No PT Segment CH-023 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\IKS-O 125AIZ 1-17 2"-CH-68-1502 3 8-J 89.40 IA No PT Segment CH-023 Re\"ision Relief Request Comments SOCKET WELD, (WEPSOK), Removed "tenuinal end" designator with Rev. I to plan. 11448-Wl\!KS-0125AIZ 0-AP 2"-CH-68-1502 3 8-J 89.40 IA No PT Segment CH-023 Revision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 5 Total Segment: 5 11448-Wl\!KS-0123Ql 0-05 12"-CS-2-153 2 C-F-1 CS.I I 2,\ No UT/PT Segment CS-00 I Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPC8) 3/8 in. & > nominal wall thickness. RBIS! NOTE: Perform UT/PT examination. Total Period: 1 11448-Wl\IKS-1101..\3 0-08 12"-CS-2-IS3 3 C-F-1 CS.I I 2A No LTT/PT Segment CS-00 I Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPC8) 3/8 in. & > nominal wall thickness. 11448-Wl\lKS-110 IA3 0-07 12"-CS-2-IS3 3 C-F-1 CS.I I 2A No UT/PT Segment CS-00 I Revision Relief Request Conunents Circumferential Piping Weld, (WEPC8) 3/8 in. & > nominal wall thickness. Total Period: 2 Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database)

• Page5 of 3: Print Date: I 0.*21 /97

Draning Number Total Segment: 3 l\lark Number Line Number

• Period Category Item No. ISi Class Augmt
• l\lethod 11448-Wl\!KS-0123Pl 0-06 12"-CS-l-lS3 C-F-1 CS.11 2A No l'T/PT Segment CS-002 Revision Relief Request Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness.

Total Period: 11448-\Vl\!KS-l IO 1..\3 0-03 12"-CS-l-lS3 2 C-F-1 CS. I I 2A No l'T/PT Segment CS-002 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness. RBIS! NOTE: Perfonn l'T/PT examination. 11448-\Vl\!KS-1101..\3 0-02 12"-CS-l-!S3 2 C-F-1 CS.! I 2A No l'T/PT Segment CS-002 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 2 Total Segment: 3 11448-\Vl\!KS-0123Ql 0-09 12"-CS-2-IS3 C-F-1 CS.II 2A No l'TiPT Segment CS-003 Revision Relief Request Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: l Total Segment: l 11448-\\'l\!KS-0123Pl 0-10 12"-CS-1-153 C-F-1 C5.ll 2A No Segment CS-004 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 11448-\VMKS-0123Kl 1-04 8"-CS-33-153 3 C-F-1 CS.II 2F No Segment CS-004 Revision 3 Relief Req nest Comments Circumferential Piping Weld, (WEPCB). Weld added to replace weld 0-08 on 11448-WMKS-O 123Ql, with Re\'. 3 to plan. Weld was switched in response to NRC Ltr. 94-414 of 6-8-94 as stated in \"irginia Power Ltr. 94-414 of9-12-94 .. Total Period: 1 Total Segment: 2 11448-WMKS-I IO 1:\6 0-02 16"-SI-5-153 3 C-F-1 CS.II 2A No l'T/PT Segment ECC-000 Revision Relief Request Comments CIRCUl\ffERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal \Vall Thickness. Total Period: I Total Segment: l 11448-WMKS-0127JI 1-08 2"-SI-74-1502 2 B-J B9.21 IA No PT Segment ECC-00 I ReYision Relief Request Comments CIRCUl\ffERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. Total Period: 1 Total Segment: l 11448-Wl\!KS-0127J2 1-07 6"-RC-19-1502 B-J B9.ll IA No UT/PT Segment ECC-002 Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: l Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 6of3; Print Date: IO 21 9-:-

Dr:ming Number I 1448-WMKS-012712 Segment ECC-002 Re\'ision l\lark Number 1-13 Relief Request Line Number 2"-Sl-85-1502 Conunents

• Period 3

Category B-1 Item No. 89.21 CIRCL'l\!FERENTIAL PIPING WELD, (\\'EPCB), < 4 in. NPS. IA ISi Class Augmt No

• l\lethod PT Total Period: l Total Segment: 2 I 1448-WMKS-012713 1-06 6"-Sl-153-1502 B-1 89.11 IA No UT/PT Segment ECC-003 Re\'ision Relief Request Conunents CIRCL'l\!FERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB).

Total Period: I Total Segment: I I 1448-WMKS-1106A3 2-24 2"-Sl-73-1503 C-F-1 CS.30 2A No PT Segment ECC-004 Re\'ision Relief Request Comments Socket Weld, (WEPSOK). I 1448-WMKS-0122Kl 6-0IBC 2"-Sl-80-1502 I C-F-1 C5.41 2A Yes PT Segment ECC-004 Re,*ision 2 Relief Request Conunents Pipe Branch Connection, Circumferential \\'eld, (\\'EPBC). TS Item 2.1.2; Examine a minimum of2.5% of the welds e,*ery refueling outage with all complete by the end of the interYal. This weld was changed from a Technical Specification Item 2.1.3 to a Teclmical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. 11448-Wl\!KS-1106 ...\3 0-15 2"-SI-72-1503 I C-F-1 CS.JO 2A No PT Segment ECC-004 Re,*ision Relief Request Comments Socket Weld, (WEPSOK). 11448-Wl\!KS-012211 2-12 6"-Sl-50-1502 I

• C-F-1 CS.I I 2A Yes l'T:PT Segment ECC-004 Re,*ision 2 Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.2; Examine a minimum of2.5% of the welds e\"e!)' refueling outage with all complete by the end of the interYal. This weld was changed from a Technical Specification Item 2.J. l to a Teclmical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications.

11448-Wl\!KS-0122Hl 2-07 6"-Sl-49-1502 I C-F-1 CS.I I 2..\ Yes l'T/PT Segment ECC-004 Re,*ision 2 Relief Request Comments CIRCL11\!FERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.2; Examine a minimum of 2.S% of the welds e\"e!)* refueling outage with all complete by the end of the int=*al. This weld was changed from a Technical Specification Item 2.1.1 to a Tedmical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Total Period: 5 l 1448-Wl\IKS-0122Kl 3-16 6"-Sl-48-1502 2 C-F-1 CS.I I 2A No UT/PT Segment ECC-004 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). 3/8 in. & > Nominal Wall Thickness. 11448-\\'l\!KS-1106A2 0-21 3"-SI-147-1 S03 2 C-F-1 CS.21 2A No UT/PT Segment ECC-004 Re,*ision Relief Request Comments CIRCL'l\lFERENTIAL PIPING WELD, (WEPCB). > 0.200 in. Nominal Wall Thickness. 11448-Wl\!KS-0122KI 3-12 6"-SI-48-1502 2 C-F-1 CS.I I 2A No UT/PT Segment ECC-004 ReYision Relief Request Comments Circumferential Piping Weld, (WEPCB). 3/8 in. & > Nominal Wall Thickness. 11448-Wl\lKS-0122Kl 1-22 6"-SI-S0-1502 2 C-F-1 CS.I I 2A Yes l 1TiPT Segment ECC-004 Re\'ision 2 Relief Request Comments Circumferential Piping Weld, (WEPCB). TS Item 2.1.2; Examine a minimum of2.S% of the welds eve!)' refueling outage with all complete by the end of the inten*al. This weld was changed from a Technical Specification Item 2.1.1 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page-: ofr Print Date: /0*21-97

Dra\\ing Nmnber I I 448-\\'l\lKS-O I 22K IBZ Segment ECC-004 Revision 2 Relief Request

                                                                        !\lark Number 1-12 Line Number 2"-Sl-81-1502 Comments

• Period 2

Category C-F-1 Item No. C5.30 ISi Class 2A

                                                                                                                                                                                      ..\ugml Yes Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the welds e\"e1y* refi.1eling
                                                                                                                                                                                                      *l\lethod PT outage with all complete by the end of the inter.al. TI1is weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment I 87 to Teclmical Specifications.

l 1448-WMKS-OI22JI 0-04 2"-SI-79-1502 2 C-F-1 C5.41 2..\ Yes PT Segment ECC-004 Revision 8 Relief Request Comments Piping Branch Connection, (\\'EPBC). TS Item 2.1.2; Examine a minimum of 2.5% of the welds e\"e!y' refueling outage with all complete by the end of the inten*al. This weld was changed from a Technical Specification Item 2.1.3 to a Teclmical Specifications Item 2.1.2 (with Re\". 2 to plan) due to amendment 187 to Technical Specifications. Changed year to 2000 and period to 2 with Rev. 8 to plan, to ensure 2.5% of the welds are examined eve1y* refueling outage. 11448-Wl\lKS-0122Kl 7-0IBC 2"-SI-81-1502 2 C-F-1 C5.41 2..\ Yes PT Segment ECC-004 Revision Relief Request Comments Piping Branch Connection, Circumferential Weld, (WEPBC). TS Item 2.1.2; Examine a minimum of 2.5% of the welds e,*e1y* refueling outage with all complete by the end of the inten-al. lbis weld was changed from a Technical Specification Item 2. I .3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Total Period: 7

• t t448-Wl\lKS-Ol22KIAZ 1-14 2"-Sl-80-1502 3 C-F-1 C5.30 2..\ Yes PT Segment ECC-004 Re,*ision 2 Relief Request Comments Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of 2.5% of the welds eve1y* refueling outage with all complete by the end of the inten*al. This weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment I 87 lo Teclmical Specifications.

11448-WMKS-1106..\3 0-01 3"-SI-72-1503 3 C-F-1 C5.21 2A No l 1T/PT Segment ECC-004 Re,*ision Relief Request Conunents Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\lKS-I 106..\3 1-27 2"-Sl-77-1503 3 C-F-1 C5.30 2A Yes PT Segment ECC-004 Re,*ision 8 Relief Request Comments Socket Weld. (WEPSOK) TS Item 2.1.2; Examine a minimum of2.5% of the welds ew1y* refueling outage with all complete by the end of the inten*al. This weld was changed from a Tedmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due lo amendment I 87 to Technical Specifications. Changed year to 2003 and period to 3 with Rev. 8 to plan, to ensure 2.5% of the welds are examined every refueling outage. 11448-Wl\!KS-0122KIBZ 1-10 2"-Sl-81-1502 3 C-F-1 C5.30 2A Yes PT Segment ECC-004 Re,*ision 8 Relief Request Comments Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the welds eve1y* refueling outage with all complete by the end of the interval. This weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment I 87 to Technical Specifications. Changed year to 2001 with Rev. 8 to plan, to ensure 2.5% of the welds are examined every refueling outage. 11448-WMKS-0122KI.-\Z 1-17 2"-Sl-80-1502 3 C-F-1 C5.30 2A Yes PT Segment ECC-004 Revision 8 Relief Request Comments Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the welds eve1y* refueling outage with all complete by the end of the inten*al. This weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Changed year to 2003 with Rev. 8 to plan, to ensure 2.5°,i, of the welds are examined every refueling outage.

• l 1448-Wl\lKS-Ol22JI 2-05 6"-Sl-50-1502 3 C-F-1 C5.l 1 2A No UT/PT Segment ECC-004 Re,*ision Relief Request Comments CIRCU!v!FERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness.

l 1448-Wl\!KS-Ol22Kl 4-19 6"-Sl-49-1502 3 C-F-1 C5. I 1 2A No UT/PT Segment ECC-004 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). 3/8 in. & > Nominal Wall Thickness. Segments on Class 1 _Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page8of37 Print Date: 1021 '97

Drawing Number 11448-Wl\lKS-1106A3 Segment ECC-004 Relief Request l\lark Number 3-FF Line Number 3"-SI-72-1503 Conunents

• Period 3

Category C-F-1 Item No. CS.21 2A ISI Class Circumferential Piping Weld (\\'EPCB). > 0.200 in. nominal wall thickness. Augmt No I\Iethod VT/PT 11448-Wl\lKS-O ! 22J\ 2-01 6"-Sl-50-1502 3 C-F-1 C5. I 1 2A No Segment ECC-004 Re\'ision Relief Re11 uest Conunents CIRCUl\lFERENTJAL PIPING WELD, (\\'EPCB) 3/8 in. & > nominal wall thickness. I 1448-Wl\lKS-1 !06A3 3-PF 3"-SI-72-1503 3 C-F-1 C5.21 2A No LTT,l'T Segment ECC-004 Revision Relief Request Conunents Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\lKS-0!22JI 0-03 2"-SI-79-1502 3 C-F-1 CS.30 2A No PT Segment ECC-004 Relief Request Comments Socket Weld, (WEPSOK). Total Period: I I Total Segment: 23 I 1448-Wl\lKS-OIOOGI 1-19 14"-WFPD-17-601 2 C-F-2 C5.51 2A No LTT/1\IT Segment FW-015 Relief Request Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB), 3/8 in. & > nominal wall thickness. Total Period: I Total Segment: I 11448-Wl\lKS-0\02GI 1-17 14"-\\'FPD-9-601 3 C-F-2 C5.5 I 2A No LTT/1\IT Segment FW-016 Relief Reit uest Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB), 318 in. & > nominal wall thickness. Total Period: I Total Segment: I 11448-Wl\lKS-O!OIGI 1-13 14"-\\'FPD-13-601 C-F-2 C5.51 2A No LTT/1\IT Segment FW-017 Revision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (\\'EPCB). 3,8 in. & > nominal wall thickness. Total Period: I Total Segment: I 11448-Wl\lKS-O!OOGl 1-18 14"-WFPD-17-601 2 C-F-2 C5.51 2A No LTT/l\lT Segment FW-018 Relief Request Comments CIRCUl\IFERENTIAL PIPING WELD, (WEPCB), 3/8 in. & > nominal wall thickness. Total Period: I Total Segment: l 11448-Wl\lKS-0102Gl 1-16A 14"-WFPD-9-601 3 C-F-2 CS.SI 2A No LTT/l\lT Segment FW-019 Re\'ision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB), 3/8 in. & > nominal wall thickness. "A" added to weld number with Rev. 5 to drawing due to piping being replaced during the 1997 refueling outage. Total Period: l Total Segment: l 11448-Wl\lKS-OIOIGI 1-12 14"-WFPD-13-601 C-F-2 CS.51 2A No UTil\lT Segment FW-020 Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD , (WEPCB). 3}8 in. & > nominal wall thickness. Total Period: l Segments on Oass 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 9 ofr Print Date: JO '21*9-:

Total Segment: Drm,ing Number l\lark Number Line Number

• Period Category Item No. ISi Class Augmt

                                                                                                                                                                                                          *l\lethod 11448-Wl\lKS-110585                                                     2-BD-A          2"-CI 1-20-1503                               C-F-1           C5.30           2A                    No           PT Segment     HHl-004..\     Revision                       Relief Req nest                Comments        Socket Weld, (WEPSOK).

Total Period: I 11448-Wl\lKS-110585 1-01 3"-CH-81-1503 3 C-F-1 C5.21 2A No UT/PT Segment HHl-004..\ Revision Relief Request Comments Circumferential Piping \Veld (WEPCB) > 0.200 in. nominal wall thickness. 11448-Wl\lKS-110585 1-03 3"-CH-81-1503 3 C-F-1 C5.21 2A Yes l'TIPT Segment HHl-004:\ Re,*ision 8 Relief Request Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. TS Item 2.1.2. added to plan with Rev. 2 to plan due to a Teclmical Specification change, amendment 187 .. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the intern!. Changed year to 200 I with Rev. 8 to plan, to ensure 2.5% of the welds are examined e\*ery refueling outage. Total Period: 2 Total Segment: 3 11448-Wl\lKS-110589 1-..\NF 3"-CH-69-1503 2 C-F-1 C5.21 2A No UT/PT Segment HHI-004C Re,*ision Relief Request Comments Circumferential Piping Weld (\\'EPCB). > 0.200 in. nominal wall thickness. 11448-\\'l\lKS-110585 1-06 3"-CH-69-1503 2 C-F-1 C5.21 2..\ No l'T/PT Segment HHI-004C Re,*ision Relief Req nest Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. RB!Sl NOTE: Perfonn UTiPT examination. Total Period: 2 Total Segment: 2 11448-Wl\lKS-110585 2-BP 3"-CH-2-1503 C-F-1 C5.41 2A No PT Segment HHl-005:\ Revision Relief Request Comments Circumferential Piping Weld (Branch Connection), (WEPBC) 2 in. & > NPS. Total Period: I Total Segment: I 11448-Wl\IKS-110585 2-AJ 3"-CH-2-1503 2 C-F-1 C5.21 2A No UT/PT Segment HHI-005C Revision 2 Relief Request Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. This weld added to plan with Re\'. 2 to plan, and replaces weld 2-AN, which was presen*iced during the 1994 refueling outage. TotalPeriod: I Total Segment: l 11448-Wl\IKS-1105B13 0-11 3"-CH-251-1502 C-F-1 C5.21 2A No l'T/PT Segment HHl-006C Revision Relief Request Comments Circumferential Piping Weld, (WEPCB) > 0.200 in. nominal wall thickness. l l448-Wl\1KS-1105B13 0-12 3"-CH-251-1502 1 C-F-1 C5.21 2A No L'T/PT Segment HHl-006C Re,*ision Relief Req nest Comments Circumferential Piping Weld, (WEPCB) > 0.200 in. nominal wall thickness. Total Period: 2 I__ Segments on Class 1 _Class 2 piping welds, Sorted b~* Segment (SPSU13 Database) Page10of37 Print Date: 1021/97

Drawing Number 11448-Wl\!KS-1105B5 Segment HHI-006C Re\'ision 2 Relief Request I\1a1*k Number 2-:\S Line Number 3 "-CH-3-1503 Comments

• Period 2

Category C-F-1 Item No. C5.21 ISi Class 2:\ Augmt No

                                                                                                                                                                                                    *l\lethod l 1T/PT Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. This weld added to plan with Rev. 2 to plan to replace weld 2-AW, which was preser\'iced during the 1994 refueling outage. RBIS!

NOTE: Perfonn UT/PT examination. Total Period: 11448-Wl\!KS-I IOSBS 0-01 3"-CH-71-1503 3 C-F-1 CS.21 2:\ No UT/PT Segment HHl-006C Re\'ision Relief Request Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. Total Period: l Total Segment: 4 11448-Wl\!KS-I IOSBS 0-1 3"-CH-113-1503 C-F-1 C5.21 2:\ No UTIPT Segment HHl-007 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB) > 0.200 in. nominal wall thickness. Total Period: 1 11448-Wl\!KS-l I OSBS 2-BL 2"-CH-20-1503 2 C-F-1 CS.30 2,\ No PT Segment HHI-007 Re,*ision Relief Request Comments Socket Weld, (WEPSOK) 11448-W1'!KS-I I05BS 2-BY 2"-CH-21-1503 2 C-F-1 CS.30 2:\ No PT Segment HHl-007 Re,*ision Relief Request Comments Socket Weld, (WEPSOK) Total Period: 2 11448-Wl\!KS-I IOSBS 2-Cl\! 2"-CH-22-1503 3 C-F-1 C5.30 2,\ No PT Segment HHI-007 Re,*ision Relief Request Comments Socket Weld, (WEPSOK) Total Period: 1 Total Segment: 4 11448-Wl\!KS-l lOSB6 0-10 3"-CH-11-1503 C-F-1 C5.21 2:\ No l 1T/PT Segment HHI-008 Re\'ision Relief Req nest Comments Circumferential piping Weld, (WEPCB). > 0.200 nominal wall thickness. 11448-Wl\!KS-l !OSB7 0-1 I 2"-CH-11-1503 I C-F-1 C5.2 I 2:\ No UT/PT Segment HHl-008 Re,*lsion Relief Request Comments Circumferential piping Weld, (WEPCB). > 0.200 nominal wall thickness. 11448-Wl\!KS-1105B6 0-09 4"-CH-80-1503 I C-F-1 C5.21 2:\ No Ff/PT Segment HHl-008 Re,ision Relief Request Comments Circumferential piping Weld, (WEPCB). > 0.200 nominal wall thickness. Total Period: 3 11448-Wl\[KS-1106B6 0-30 3"-SI-70-1503 2 C-F-1 C5.21 2:-\ No L1T/PT Segment HHI-008 Re\'ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\!KS-1105B5 2-T 3 "-CH-2-1503 2 C-F-1 C5.21 2:-\ No UT/PT Segment HHl-008 Re,*ision Relief Request Comments Circumferential Piping Weld (WEPCB) > 0.200 in. nominal wall thickness. l l448-W1'!KS-l l06B4 0-07 3"-SI-57-1503 2 C-F-1 C5.2 l 2:\ No UT/PT Segment HHl-008 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall Thickness. 11448-Wl\!KS-1106B4 0-05 3"-SI-57-1503 2 C-F-1 C5.21 2A No UTtPT Segment HHl-008 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall Thickness. 11448-Wl\!KS-1106B3 0-23 3 "-SI-147-1503 2 C-F-1 C5.2 I 2:\ No l 1T/PT Segment HHl-008 Re,*lsion Relief Request Comments Piping Circumferential Weld, (WEPCB). > 0.200 in. nominal wall thickness. Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSUI3 Database) Page 11 ofJ'.' Print Date: JO 21 9 7

Segment Draning Nmnher 11448-Wl\!KS-110585 HHI-008 ReYision Relief Request

                                                                      !\lark Number 0-03 Line Number 4"-CH-80-1503 Comments

• Period 2

Category C-F-1 Item No. C5.21 ISi Class 2.-\ Circumferential Piping Weld, (WEPCB) > 0.200 in. nominal wall thickness. Augmt No l\lethod Total Period: 6 11448-Wl\!KS-110686 0-09 3"-Sl-90-1503 3 C-F-1 C5.21 2.-\ No UT/PT Segment HHI-008 ReYision Relief Request Conunents Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. 11448-WMKS-1105810 0-10 3"-CH-79-1503 3 C-F-1 C5.21 2.-\ No Segment HHl-008 ReYision Relief Request Comments Circumferential Piping Weld, (WEPCB) > 0.200 in. nominal wall thickness. Total Period: 2 Total Segment: l l 11448-Wl\!KS-110681 0-07 3"-Sl-146-1503 C-F-1 C5.2I 2.-\ No UT!PT Segment HHI-009 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 11448-Wl\lKS-110589 1-BGS 2"-CH-8-1503 2 C-F-1 C5.21 2A No L1TiPT Segment HHl-009 ReYision Relief Request Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 11448-Wl\!KS-110589 I-RS 4"-CH-89-1503 3 C-F-1 C5.21 2.-\ No UT1PT Segment HHl-009 Re,*ision Relief Request Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. 11448-WMKS-110589 1-BFS 4"-CH-89-1503 3 C-F-1 C5.21 2.-\ No UT/PT Segment HHl-009 Re,*ision Relief Request Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\lKS-110589 1-YF 3"-CH-70-1503 3 C-F-1 C5.21 2A No UT/PT Segment HHI-009 Re,*ision Relief Request Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\lKS-110685 0-03 3"-SJ-72-1503 3 C-F-1 C5.21 2.-\ No L1T,PT Segment HHl-009 Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\!KS-110685 0-14 3"-SJ-72-1503 3 C-F-1 C5.2! 2.-\ No LIT/PT Segment HHI-009 Re\'lsion Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. ! 1448-Wl\lKS-110589 1-AAF 3"-CH-70-1503 3 C-F-1 C5.21 2A No L*f/PT Segment HHl-009 Re\'ision Relief Request Comments Circumferential Piping Weld (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 6 Total Segment: 8 1 !448-Wl\lKS-110686 0-25 3"-Sl-70-1503 2 C-F-1 C5.2! 2.-\ No l1TiPT Segment HHl-010 Re,*ision Relief Req nest Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 11448-Wl\!KS-110686 0-19 3"-Sl-70-1503 3 C-F-1 C5.21 2.-\ No UT1PT Segment HHl-010 ReYision Relief Request Conunents Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 1 Total Segment: 2 Segments on Class 1 _Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page 12ofr Print Date: IO 2 /. 9:

/ Dr:ming Number I 1448-WMKS-1106A4 Segment HHI-012A Re\"ision* I\Iark Number 4-28 Relief Request Line Number 2"-Sl-70-1503 Conunents

• Period Socket Weld, (WEPSOK).

CategorJ C-F-1 Item No. C5.30 2A ISi Class Augmt No

                                                                                                                                                                                                       *Method PT Total Period: l I 1448-WMKS- I I 06A4                                               1-16           3"-Sl-70-1503                        2       C-F-1             C5.21            2A                     Yes          l'T/PT Segment        I-IHI-012A  Re\"ision   2              Relief Request                Comments       Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall Thickness. TS Item 2.1.2. added to plan with Rev. 2 to plan due to a Technical Specification change, amendment 187. Examine a minimum of2.5%

of the welds every refueling outage with all complete by the end of the inter.al. I 1448-Wl\lKS-I I 06A4 3-48 2"-Sl-71-1503 2 C-F-1 CS.30 2A Yes PT Segment HHI-0 I 2A Re\"ision 2 Relief Request Conunents Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of 2.5% of the welds every refueling outage with all complete by the end of the interval. This weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2. I .2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. 11448-\\'l\lKS-l !06A4 2-35 2"-Sl-76-1503 2 C-F-1 CS.30 2A No PT Segment HHI-0\2A Re\"ision Relief Request Comments Socket Weld, (WEPSOK). I 1448-Wl\!KS-l !06A4 2-40 2"-SI-76-1503 2 C-F-1 CS.30 2A Yes PT Segment I-IHI-012A Re,*islon 2 Relief Request Comments SOCKET WELD, (WEPSOK). TS Item 2. I .2; Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. This weld was changed from a Technical Specification Item 2. I .3 to a Technical Specifications Item 2. I .2 (with Re,*. 2 to plan) due to amendment 187 to Technical Specifications. I I 448-\\'l\!KS- l l 06A4 2-51 B\\' 2"-Sl-76-1503 2 C-F-1 CS.21 2A No l1T!PT Segment HHI-012A Re,*ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall Thickness. Total Period: 5 I 1448-Wl\!KS- l l 06A4 1-05 3 "-SI-70-1503 3 C-F-1 C5.21 2A No l1T/PT Segment HHl-012A Re\"ision Relief Request Comments Circumferential Piping Weld, (WEPCB). > 0.200 in. Nominal Wall TI1ickness. Total Period: l Total Segment: 7 I 1448-WMKS- l l 06A4Z 1-27 2"-Sl-74-1502 C-F-1 C5.30 2A Yes PT Segment HHI-0128 Revision 2 Relief Request Comments Socket Weld, (\VEPSOK). TS Item 2. I .2; Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. This weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Total Period: l I 1448-Wl\!KS-l l 06A4Z 1-34 2"-Sl-74-1502 2 C-F-1 C5.30 2A '{es PT Segment HHI-0128 Re,*ision 2 Relief Request Comments Socket Weld, (\VEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. TI1is weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Re,*. 2 to plan) due to amendment I 87 to Technical Specifications. I 1448-Wl\!KS-1106A4Z 1-35 2"-SI-74-1502 2 C-F-1 C5.30 2A Yes PT Segment HHl-0128 Revision 2 Relief Request Comments Socket Weld, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5'l*o of the welds every refueling outage with all complete by the end of the interval. TI1is weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment I 87 to Technical Specifications. Segments on Gass 1 .Gass 2 piping welds, Sorted hy Segment (SPSU13 Database) Page J3ofr Print Date: JO 2/:97

Dra,,ing Number  !\lark Number Line Number Total Period: 2 Pe1iod Category Item No. ISi Class Augmt

                                                                                                                                                                                                   *Method 11448-Wf\lKS-1106A4Z                                                  1-32           2"-Sl-74-1502                        3      C-F-1             C5.30           2A                   Yes          PT Segment    HHl-0128       Re,*ision      8              Relief Request                Comments      Socket \\'eld, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the \\'elds e\'ery refueling outage \\'ith all complete by the end of the interval. This weld was changed from a Technical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Changed year to 2001 with Rev. 8 to plan, to ensure 2.5% of the welds are examined every refueling outage.

Total Period: 1 Total Segment: 4 l 1448-WMKS-0127J2Z 1-26 2"-Sl-85-1502 C-F-1 C5.30 2A Yes PT Segment HHl-012C Re,*ision 5 Relief Request Comments SOCKET \\'ELD, (WEPSOK). TS Item 2.1.2; Examine a minimum of2.5% of the \\'elds ewry refueling outage with all complete by the end of the inter\'al. This weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Re,*. 2 to plan) due to amendment 187 to Technical Specifications. Added to plan with Rev. 5 to plan to replace weld 1-25 on drawing 11448-\\'f\lKS-0127J2Z, which is co,*ered by support H009. Total Period: 11448-Wf\lKS-0127J2Z 1-29 2"-Sl-85-1502 3 C-F-1 C5.30 2..\ Yes PT Segment HHl-0 l 2C Re,*ision 2 Relief Request Comments SOCKET WELD, (WEPSOK). TS Item 2.1.2; Examine a minimum of 2.5% of the welds e,wy refueling outage with all complete by the end of the inter\'al. This weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Re\'. 2 to plan) due to amendment 187 to Technical Specifications. l 1448-WMKS-0127J2Z 1-28 2"-Sl-85-1502 3 C-F-1 C5.30 2A Yes PT Segment HHl-012C Re,*ision 2 Relief Request Conunents SOCKET WELD, (\\'EPSOK). TS Item 2.1.2; Examine a minimum of2.s*.*;, of the welds ern*y refueling outage with all complete by the end of the interval. ll1is weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Re\'. 2 to plan) due to amendment 187 to Technical Specifications*. Total Period: 2 Total Segment: 3 l 1448-WMKS-0127J3Z 1-24 2"-Sl-75-1502 C-F-1 C5.30 2A No PT Segment HHl-012D Redsion 5 Relief Request Comments Socket Weld, (WEPSOK). This weld added to plan with Rev. 5 to plan to replace weld 1-23 on the same line and drawing No. 11448-WMKS-0127J3Z 1-22 2"-Sl-75-1502 C-F-1 C5.30 2A Yes PT Segment HHI-012D Rel'ision 2 Relief Request Comments SOCKET WELD, (WEPSOK). TS Item 2.1.2; Examine a minimum of 2.5% of the welds e\'ery refueling outage with all complete by the end of the inter\'al. 1l1is weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specifications Item 2.1.2 (with Rev. 2 to plan) due to amendment 187 to Technical Specifications. Total Period: 2 11448-\VMKS-l l 06A4 4-27 2"-Sl-75-1502 3 C-F-1 C5.30 2A No PT Segment HHl-012D Re\'ision Relief Request Comments Socket Weld, (WEPSOK). Total Period: 1 Total Segment: 3 Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page /4 of 3: Print Date: JO 21 9:

Drm\ing Number 11448-WI\IKS-110681 _S~cg~n_1_en_t___H_H_I_-O_l_3___R_e_,_*is_i_on l\lark Number 0-08 Line Number. 3"-Sl-146-1503 _ _ _ _ _ _ _ _R_c_l_ic_f_R_c~q~u-es_t_ _ _ _ _ _ _ _ _Comments

• Period Category C-F-1 Item No.

C5.21 ISi Class 2.-\ Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Augmt No

                                                                                                                                                                                                          *Method llTiPT 1 !448-WI\IKS-110681                                                             0-26             3"-SI-146-1503                      I     C-F-1          CS.21           2A                 No           llT/PT Segment          HHI-013        Rc\"ision                   Relief Request                          Comments       Circumferential Piping Weld, (WE PCB).> 0.200 in. nominal wall thickness.

Total Period: 2 Total Segment: 2 11448-WI\IKS-1106.-\l 0-02 3"-Sl-146-1503 C-F-1 CS.21 2.-\ No L'T/PT Segment HHI-014 Re,*ision Relief Request Comments CIRClll\lFERENTIAL PIPING WELD, (WEPCB). > 0.200 in. NOl\!IN ...\L W...\LL THICKNESS. 11448-Wl\!KS-1106.-\l 0-01 3"-Sl-146-1503 I C-F-1 C5.21 2.-\ No llTiPT Segment HHI-014 Re,*ision Relief Request Comments CIRCL11\IFERENTI...\L PIPING WELD, (WEPCB). > 0.200 in. NOI\IIN ...\L W...\LL THICKNESS. Total Period: 2 Total Segment: 2 11448-\\'I\IKS-110682 0-09 3"-SI-147-1503 C-F-1 C5.21 No L1TiPT Segment HHl-015 Re,*ision Relief Request Comments Circumferential piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. 11448-Wl\!KS-110682 0-01 3"-SI-147-1503 I C-F-1 C5.21 2.-\ No L'TiPT Segment HHI-015 Re,*ision Relief Request Comments Circumferential piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: 2 11448-WI\IKS-I I 0682 0-25 3"-SI-147-1503 2 C-F-1 C5.21 2.-\ No FfiPT Segment HHI-015 Re\"ision Relief Request Comments Circumferential piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: I Total Segment: 3 I 1448-\\'I\IKS-1106.-\2 0-01 3"-SI-147-1503 C-F-1 C5.21 2.-\ No L'T/PT Segment HHl-016 Re\"islon Relief Request Comments CIRCLT!\IFERENTIAL PIPING WELD, (\\'EPCB). > 0.200 in. Nominal Wall Thickness. Total Period: l 11448-Wl\lKS-l l06A2 0-02 3"-SI-147-1503 2 C-F-1 C5.21 2.-\ No L'T/PT Segment HHI-016 Re,*ision Relief Request Conunents CIRCLT!\IFERENTI...\L PIPING WELD, (WEPCB). > 0.200 in. Nominal Wall Thickness. Total Period: l Total Segment: 2 I ! 448-Wl\lKS-110685 0-22 3 "-SI-72-1503 3 C-F-1 C5.21 2A No LTTIPT Segment HHI-017 Re\"ision Relief Request Conunents Circumferential Piping Weld, (WEPCB). > 0.200 in. nominal wall thickness. Total Period: I Total Segment: I Segments on Oass 1 _Class 2 piping welds, Sorted b)* Segment (SPSU13 Database) Page 15 ofr' Print Date: IO 2 J. 9-:

Dral\ing Number 11448-\V~IKS-1106A7 Segment LHl-00 I Re,*ision 3

                                                                      !\lark Number 0-32L Relief Request Line Nwnber 12"-Sl-2-153 Comments

• Pe1iod 2

Category C-F-1 Item No. C5.I2 ISi Oass 2.-\ Augmt No

                                                                                                                                                                                                    *l\lethod l 1TiPT Longitudinal Piping Weld, (Fitting), (WEPSEhl) > 3/8 in. nominal wall thickness. Examine 2.5t (0.937 in.)

at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination volume of welds 1-17 and 1-

18. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld.

11448-\V~IKS-I 106A7 1-18 12"-Sl-2-153 2 C-F-1 C5.l l 2A No UT!PT Segment LHl-001 Re\"ision Relief Request Comments CIRCL1~1FERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 2 I 1448-\VMKS-1 !06A7 1-19 12"-SI-2-153 3 C-F-1 C5.l l 2A No l'TiPT Segment LHl-001 Re,*ision Relief Request Comments CIRCL1~1FERENTIAL PIPING WELD, (\VEPCB) 3/8 in. & > nominal wall thickness. Total Period: l Total Segment: 3 11448-\V~IKS-1106A7 O-I8L 12"-Sl-1-153 C-F-1 C5.12 2A No UTiPT Segment LHl-002 Re,*lsion 3 Relief Request Comments Piping weld (WEPSE~I) 3/8 in. & > nominal wall thickness, longitudinal, (fitting). Examine 2.5t (0.937 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area indudes only that length of the longitudinal weld within the circumferential weld examination ,*olume of welds 1-10 and I-I I. Examination requirements must be met for both trans\'erse & parallel flaws in the examination area of the longitudinal weld. 11448-WMKS-l I06A7 1-10 12"-SI-1-153 I C-F-1 CS.I I 2A No UT/PT Segment LHl-002 Re,*ision Relief Request Comments CIRCLT~lfERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 2 Total Segment: 2 11448-WMKS-1106A7 1-15 12"-SI-2-153 3 C-F-1 C5.l l 2A No UT/PT Segment LHI-003 Re,*ision Relief Request Comments CIRCU~IFERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness. RBIS! NOTE: Perform UT/PT examination. Total Period: l Total Segment: l 11448-\\'MKS-OI27C2 3-AGF 10"-SI-148-153 2 C-F-1 CS. I I 2F No UT/PT Segment LHI-007 Re,*ision 3 Relief Request Comments CIRCU~IFERENTIAL PIPING WELD, (WEPCB). Weld added with Rev. 3 to plan. Weld added in response to NRC Ltr. 94-414 of 6-8-94 as stated in Virginia Power Ltr. 94-414 of9- l 2-94. Total Period: l Total Segment: I I 1448-W~!KS-0127Cl 3-AAF 10"-SI-15!-153 3 C-F-1 CS.I I 2F No UT/PT Segment LHI-008 Re,*ision 3 Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Weld added with Rev. 3 to plan. Weld added in response to NRC Ltr. 94-414 of6-8-94 as stated in Virginia Power Ltr. 94-414 of9-12-94. Total Period: I Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 16 of3: Print Date: 10:'2},9'.'

Dra\\ing Number Total Segment: 1

                                                                      !\lark Number   Line Nwnber

• Period Category Item No. ISi Class Augmt

                                                                                                                                                                                               *l\lethod 11448-WMKS-0!27JI                                                    2-12            6"-Sl-145-1502                               C-F-1          C5.l l          2A                  No          L1T/PT Segment LHl-010          Revision                      Relief Request                 Comments         CIRCL1!,IFERENTIAL PIPING WELD, (\VEPCB). 3!8 in. & > Nominal \Vall Thickness.

11448-WMKS-O 127Jl 2-01 6"-SI-145-1502 I C-F-1 C5.l I 2A No l1TiPT Segment LHI-010 Revision Relief Re11uest Conunents CIRCU~IFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. 11448-WMKS-0127C2 1-11 10"-SI-152-1502 I C-F-1 C5.l l 2A No L1T/PT Segment LHI-010 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD , (WEPCB). 3i8 in. & > nominal wall thickness. 11448-W~IKS-0127Jl 2-03 6"-Sl-145-1502 I C-F-1 CS.II 2A No l1T.1PT Segment LHI-010 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). 318 in. & > Nominal Wall Thickness. 11448-\VMKS-0!27J5 2-13 6"-SI-144-1502 I C-F-1 C5. l I 2A No L1TiPT Segment LHI-010 Re\'ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). 3,g in. & > Nominal Wall Thickness. 11448-WMKS-0!27J2 2-01 6"-SI-144-1502 I C-F-1 CS.I I 2A No L1TPT Segment LHI-010 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB) 3/8 in. & > Nominal Wall Thickness. Total Period: 6 11448-WMKS-0127J5 3-35 6"-SI-153-1502 2 C-F-1 CS.I I 2A No L1T/PT Segment LHI-010 Re,*ision Relief Request Comments CIRCU1v!FERENTIAL PIPING WELD, (WEPCB). 3.18 in. & > Nominal Wall Thickness. 11448-\V~IKS-0127C2 1-07 10"-SI-152-1502 2 C-F-1 CS.I I 2A No L1T/PT Segment LHI-010 Re,*ision Relief Request Comments CIRCU~IFERENTIAL PIPING WELD, (WEPCB). Weld placed in plan to replace weld 3-KF. Weld 3-KF was removed from plan because it was detennined to be Class 2F. 11448-\VMKS-0!27C2 1-04 6"-SI-153-1502 2 C-F-1 C5.l l 2A No Ll'f/PT Segment LHI-010 Re,*ision Relief Request Conunents CIRCLIJ\ffERENTIAL PIPING WELD , (WEPCB). 3/8 in. & > nominal wall thickness. 11448-WMKS-0127J4 1-29 6"-Sl-153-1502 2 C-F-1 CS.I I 2A No L1T/PT Segment LHI-010 Re,*ision Relief Request Comments CIRCU~IFERENTIAL PIPING WELD, (\VEPCB). 3/8 in. & > Nominal Wall Thickness. Total Period: 4 I 1448-WMKS-0127J4 1-26 6"-SI-l S3-l 502 3 C-F-1 CS.I I 2.-.\ No l1T!PT Segment LHI-010 Re,*ision Relief Request Comments CIRCLIJ\ffERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. 11448-W~IKS-0!27]4 1-21 6"-Sl-153-1502 3 C-F-1 C5. l l 2.-.\ No Ll'f/PT Segment LHl-010 Re\'ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Weld added to plan with Rev. I, to replace weld 1-22, which has been removed from the plan. Total Period: 2 Total Segment: 12 l 1448-\VMKS-OI27C2 2-09 6"-Sl-48-!S02 2 C-F-1 CS.I I 2A No L1T!PT Segment LHI-011 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 1 Total Segment: 1 11448-W~IKS-0!22Kl 5-01 6"-Sl-49-1502 3 C-F-1 CS.I I 2A No UT/PT Segment LHl-012 Revision Relief Request Comments Circumferential Piping \Veld, (WEPCB). 3/8 in. & > Nominal Wall Thickness. l 1448-WMKS-0!27Cl 2-05 6"-SI-49-1502 3 C-F-1 CS.I I 2,.\ No L1T.1PT Segment LHl-012 Re,*islon ReliefRequest Comments Circumferential Piping \Veld, (WEPCB) 3/8 in. & > nominal wall thickness. Segments on Class 1 _Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page J'.'ofT' Print Date: 1021:97

Drawing Number

               *                                                        !\lark Number   Line Number

• Total Period: 2 Period Category Item No. ISi Class Augml

                                                                                                                                                                                                     *l\Ielhod Total Segment: 2 11448-WMKS-0!02DI                                                      1-1             32"-SHP-3-601                        3       C-F-2            CS.51           2.-\                    No        t rr l\lT Segment    l\lS-003       Re\"ision                     Relief Re11 uest                Comments       C!RCL1l\lFERENTIAL PIPING WELD, (WEPCB), 3/8 in. & > nominal wall thickness.

Total Period: I Total Segment: I l 1448-WMKS-0103A2-I 2-26 30"-SHP-1-601 C-F-2 CS.51 2A Yes L'T/MT Segment l\lS-004 Re\'ision Relief Request Comments CIRCL1l\lFERENTIAL PIPING WELD , (WEPCB). 3/8 in. & > nominal wall thickness. 11448-WMKS-O I 03.-\2-1 0-3L 30"-SHP-1-60 I I C-F-2 CS.52 2A Yes L'Til\lT Segment l\lS-004 Re\"ision 3 Relief Request Comments Piping Weld 3!8 in. & > nominal wall thickness (Longitudinal Weld). Examine 2.5t (2.5 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Re,*. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination \'olume of welds 2-27 and 2-

28. Examination requirements must be met for both trans,*erse & parallel flaws in the examination area of the longitudinal weld.

11448-WMKS-0103.-\2-1 2-28 30"-SHP-1-60 I I C-F-2 CS.51 2A No L'T/MT Segment l\lS-004 Re,*ision Relief Request Comments CIRCL1l\lFERENTIAL PIPING WELD , (WEPCB). 3/8 in. & > nominal wall thickness. 11448-Wl\lKS-0103.-\2-1 2-34L 30"-SHP-1-601 I C-F-2 CS.52 2A No L'T1l\lT Segment l\lS-004 Re\"ision 3 Relief Request Comments LONGITUDINAL PIPING WELD 3/8 in. & > nominal wall thickness. Examine 2.5t (2.5 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Re\'. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination ,*olume of welds 2-26 and 2-

11. Examination requirements must be met for both trans\'erse & parallel flaws in the examination area of the longitudinal weld.

Total Period: 4 11448-WMKS-0103.-\2-1 2-11 30"-SHP-1-601 3 C-F-2 CS.SI 2A Yes UT/1'.IT Segment l\lS-004 Re,*ision Relief Request Comments CIRCL'l\lFERENTIAL PIPING WELD , (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Examination changed from Period I to Period 3 and l\lT examination added with Rev. I to Plan. Total Period: I Total Segment: 5 11448-WMKS-0103A2-2 4-10 30"-SHP-2-60 I 2 C-F-2 C5.51 2A Yes L'T/1\IT Segment l\lS-005 Re,*ision Relief Request Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPCB). Augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Also perform ASI\IE Section XI examination. Note added with Re\'. I to Plan. l 1448-WMKS-0103.-\2-2 0-4L 30"-SHP-2-60 I 2 C-F-2 CS.52 2A No l'T/1\IT Segment l\lS-005 Revision 3 Relief Request Conunents Piping Weld 3/8 in. & > nominal wall thickness (Longitudinal Weld). Examine 2.5t (2.5 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination ,*olume of welds 4-27 and 4-

28. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld.

Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Pagel8of37 Print Date: JO 21 97

Dra\\ing Number 11448-WMKS-0103:\2-2 Segment MS-005 Re,*ision J\lark Number 4-25 Relief Request Line Number 30"-SHP-2-601 Comments

• Period 2

Category C-F-2' Item No. C5.51 ISi C1ass 2A CIRCUJ\IFERENTIAL PIPING \\'ELD, (\\'EPCB), 3:8 in. & > nominal wall thickness. Augmt No

                                                                                                                                                                                                    *J\lethod l'T/1\IT Total Period: 3 Total Segment: 3 11448-WMKS-O I 03A2-3                                                3-07            30"-SHP-3-60 I                       3        C-F-2             CS.SI           2A                   Yes         l'T/1\ff Segment    l,!S-006       Re,*ision                     Relief Request                Comments       CIRCUMFERENTIAL PIPING WELD. (WEPCB). Augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Also perform ASJ\!E XI examination. Note added with Re\', I to Plan.

11448-WMKS-O 103A2-3 0-4L 30"-SHP-3-601 3 C-F-2 C5.52 2A Yes l'T/1\ff Segment l\ !S-006 Re,*ision 7 Relief Request Comments Piping Weld 3/8 in. & > nominal wall thickness (Longitudinal Weld). Examine 2.5t (2.5 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Re\'. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination \"Olume of welds 3-24 and 3-

25. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. TS 4.15 requirement added with Rev. 7 to the plan due to weld selection being changed for TS 4.15 to the 1989 Code.

Total Period: 2 Total Segment: 2 11448-Wl\!KS-0103:\2-2 l-07A 6"-SHP-46-601 2 C-F-2 C5.5 I 2A Yes UT!l\lT Segment l\!S-0 I I Re,*ision 7 Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB), 318 in. & > nominal wall thickness. TS 4.15 requirement added with Rev. 7 to plan due to updating TS 4.15 to 1989 Edition of the Code. Total Period: 1 Total Segment: 1 11448-Wl\!KS-0103:\2-3 1-04 6"-SHP-47-601 2 C-F-2 C5.5 l 2A Yes llT/1\ff Segment l\!S-012 Re,-ision 7 Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Added with Rev. 5 to plan. TI1is weld is added to replace weld 2-06 on drawing 11448-Wl\!KS-0103,\2-3, which was< 0.375" wall thickness and did not qualif)* as a C5.5 I weld, therefore remo\'ed from the plan with Re\'. 5. TS 4.15 requirement added with Re\'. 7 to the plan due to changing weld selection to the 1989 Code. Total Period: 1 11448-Wl\!KS-O I 03 A2-3 1-07 6"-SHP-47-60 I 3 C-F-2 C5.51 2A Yes UT/1\IT Segment l\!S-012 Re\ision 7 Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB), 3/8 in. & > nominal wall thickness. TS 4.15 added to plan with Re\'. 7 to the plan due to weld selection of TS 4. 15 being changed to the 1989 Code. Total Period: 1 Total Segment: 2 11448-Wl\lKS-0103A2-4 l-I3BC 30"-SHP-22-60 l C-F-2 C5.81 2A Yes UT/1\IT Segment l\lS-019 Re,*ision Relief Request Comments Pipe Branch Collllection CIRCUMFERENTIAL WELD. Augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Also perform ASJ\IE XI examination. Examination changed from Period 3 to Period l with Rev. I to Plan and note added. Total Period: 1 Total Segment: 1 Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page J9of3:'" PrintDate: /0 12/:97

Dra\\ing Number Segment 11448-WMKS-O 103.-\2-2 l\lS-020 Revision 3 l\lai*k Number 0-IL Relief Request Line Number 30"-SHP-23-60 I Comments

• Period 2

Category C-F-2 Item No. C5.52 2A ISi Oass Augmt No

                                                                                                                                                                                                    *l\lethod l'Til\lT Piping Weld 3 '8 in. & > nominal wall thickness (Longitudinal Weld). Examine 2.51 (2.5 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld.

Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination \"Olume of welds 4-1 IBC and 2-12BC sho\\n on drawing 11448-Wl\!KS-0103A.2-4. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. 11448-\Vl\IKS-O 103.-\.2-2 4-llBC 30"-SHP-23-601 2 C-F-2 C5.81 2A Yes l'T/1\IT Segment MS-020 Re,*ision Relief Request Comments Pipe Branch Co1mection; CIRCL'l\!FERENTIAL WELD. Augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Also perform AS!\IE Section XI examination. Note added with Rev. I to Plan. Total Period: 2 Total Segment: 2 11448-WMKS-O I 03.-\2-4 3-10 30"-SHP-24-601 3 C-F-2 C5.51 2A No l'T/1\IT Segment MS-021 Re,*ision Relief Request Comments CIRCL'MFERENTIAL PIPING WELD, (WEPCB). Total Period: l Total Segment: 1 11448-WMKS-OIOOAZ-1 1-0IDM 29"-RC-1-250 IR 8-F 85.10 IA No L1T Auto Segment RC-00 I Re,*ision Relief Request SR-001 Comments REACTOR VESSEL - NOZZLE TO SAFE END BUTT WELD. Per Relief Request (SR-00 I) perform a full volumetric examination from the ID (with 5% notch sensitiYity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perfom1 UT examination. Total Period: 11448-WMKS-OIOOAZ-I 1-02 .29"-RC-1-250 IR 3 8-J B9.ll IA No L'TiPT Segment RC-00 I Re,*ision Relief Request Comments CIRCU!\IFERENTIAL PIPING WELD, (WEPCB). 4 in. NPS & >. Total Period: l Total Segment: 2 11448-Wl\!KS-OIOIAZ-1 1-0IDM 29"-RC-4-2501R 8-F 85.10 IA No UT Auto Segment RC-002 Re,*ision Relief Request SR-001 Comments REACTOR VESSEL- NOZZLE TO SAFE END BL'TT WELD. Per Relief Request (SR-001) perform a full volumetric examination from the ID (with 5'% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform L'T examination. Total Period: l Total Segment: l 11448-WMKS-0102AZ-1 1-0ID!\1 .29"-RC-7-2501R B-F 85.10 IA No L1T Auto Segment RC-003 Re,*ision Relief Request SR-001 Comments REACTOR VESSEL- NOZZLE TO SAFE END BUTT WELD. Per Relief Request (SR-001) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBISI NOTE: Perform UT examination. Total Period: 11448-W.I\IKS-0102AZ-1 1-0.2 29"-RC-7-250 IR 3 8-J 89.11 IA No LlT/PT Segment RC-003 Re,*ision Relief Request Comments CIRCL'l\!FERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Segments on Class l _Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page 20of3'.' Print Date: 10 219:-

Dra\\ing Number

• l\lark Number Line Number Total Period: 1 Period Category Item No. ISi Class Augmt

                                                                                                                                                                                                   *l\lethod Total Segment: 2 11448-WMKS-OIOOAZ-I                                                  1-0501\[        29"-RC-l-2501R                               8-F              85.70            IA                  No           Ff/PT Segment       RC-004         Re,*ision                 Relief Request       SR-012    Comments        STE..\!\! GENERATOR- NOZZLE TO SAFE END BUTT WELD.

Total Period: l Total Segment: l 11448-Wl\!KS-O IO I AZ- I 1-0501\[ 29"-RC-4-250 IR 2 8-F B5.70 IA No LIT/PT Segment RC-005 Re\'ision Relief Request Comments STE ..\!\! GENERATOR - NOZZLE TO SAFE END BUTT WELD. Total Period: l Total Segment: 1 11448-\\'l\lKS-O 102AZ-l 1-0501\[ 29"-RC-7-2501R 3 8-F B5.70 IA No lYfiPT Segment RC-006 Re,*islon Relief Re<1uest Comments STE..\!\! GENERATOR- NOZZLE TO SAFE END BlrIT WELD. Total Period: I Total Segment: l 11448-\\'l\IKS-OIOOAZ-I 1-0601\[ 31"-RC-2-2501R I B-F B5.70 IA No l1T,PT Segment RC-007 Re\'ision Relief Request SR-012 Comments STEM! GENERATOR- NOZZLE TO SAFE END Bl1TT WELD. Total Period: I 1448-\\'l\ !KS-0 I OOAZ- I 1-20 3 I "-RC-2-250 IR 3 8-J B9.12 IA No lYJ"/PT Segment RC-007 Re,*ision 3 Relief Request Comments Longitudinal Piping Weld, (WEPSEl\l). Examine O in. to 12 in. (0 Ref. intersection of welds 1-20 & 1-11). Added with Re,*. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length ofthe longitudinal weld (weld J-20) within the circumferential weld examination volume of weld 1-11. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. 11448-Wl\!KS-OIOOAZ-1 1-11 3 l "-RC-2-2501R 3 8-J 89. l I IA No UT/PT Segment RC-007 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB), Terminal End. 11448-Wl\!KS-OIOOAZ-1 1-2 I 3 l "-RC-2-2501R 3 8-J 89. I 2 IA No UT/PT Segment RC-007 Re,*ision 3 Relief Request Comments Longitudinal Piping Weld, (WEPSEM). Examine O in. to 12 in. (0 Ref. intersection of welds 1-21 & 1-11). Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length ofthe longitudinal weld (weld 1-21) within the circumferential weld examination volume of weld 1-11. Examination requirements must be met for both trans,*erse & parallel flaws in the examination area of the longitudinal weld. Total Period: 3 Total Segment: 4 11448-WMKS-OIOlAZ-I 1-06DM 31 "-RC-5-250 IR 2 8-F 85.70 IA No UT/PT Segment RC-008 Re,*ision Relief Request Comments STEA!\! GENERATOR - NOZZLE TO SAFE END BUTT WELD. Segmenis on Class I .Oass 2 piping welds, Sorted by Segment (SPSUl3 Database) Page 21 ofr Print Date: J0/2//9i

Drawing Number 11448-\VI-.IKS-O l OI AZ-I Segment RC-008 ReYision 3

                                                                      !\lark Numbe1*

1-21 Line Number 31 "-RC-5-250 IR

• Period 2

Category 8-J Item No. 89.12 ISi Class 1.-\ Augmt No

                                                                                                                                                                                                          *Method L1T/PT Relief Request                 Comments          Longitudinal Piping Weld, (WEPSEM). Examine O in. to 12 in. (0 Ref. intersection of welds 1-21 & 1-11 ).

Added with Re\'. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld (weld 1-21) within the circumferential weld examination \'olume of weld 1-11. Examination requirements must be met for both trans\"erse & para!lel flaws in the examination area of the longitudinal weld. 11448-WMKS-OlOIAZ-1 1-11 31 "-RC-5-250 IR 2 8-J 89.11 IA No UT/PT Segment RC-008 Re,*ision Relief Request Comments CIRCL'MFERENTIAL PIPING WELD 4 in. NPS & >, (WEPC8), Terminal End. I 1448-Wt-.lKS-OlOlAZ-I 1-20 31"-RC-5-2501R 2 8-J 89.12 IA No l'T/PT Segment RC-008 Re,*ision 3 Relief Request Comments Longitudinal Piping Weld, (WEPSEM). Examine O in. to 12 in. (0 Ref. intersection of welds 1-20 & 1-11). Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length ofthe longitudinal weld (weld 1-20) within the circumferential weld examination ,*olume of weld 1-11. Examination requirements must be met for both trans\'erse & para!lel flaws in the examination area of the longitudinal weld. Total Period: 4 Total Segment: 4 11448-WMKS-0102.-\Z-l 1-21 31 "-RC-8-2501 R 8-J B9.12 IA No L1TIPT Segment RC-009 Re,*ision 3 Relief Request Comments LONGITL'DINAL PIPING \\'ELD, (WEPSEl-.1). Weld added with Re,*. I to Plan. Weld replaces weld 1-

19. Examine O" to 12" (0 Ref. intersection of welds 1-21 & 1-11 ). Added with Re\'. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld (weld 1-21) within the circumferential weld examination rnlume of weld 1-11. Examination requirements must be met for both trans\'erse & parallel flaws in the examination area of the longitudinal weld.

l 1448-Wt-.!KS-Ol02AZ-1 1-11 31"-RC-8-2501R I B-J 89.11 IA No LfTIPT Segment RC-009 Re\"lsion Relief Request SR-010 Comments CIRCL't-.lFERENTIAL PIPING WELD 4 in. NPS & >, (WEPC8), Terminal End. l l448-WMKS-Ol02AZ-I 1-20 31"-RC-8-2501R I 8-J 89.12 IA No l'T/PT Segment RC-009 ReYision 3 Relief Request SR-Oil Comments LONGITL'DINAL PIPING \\'ELD, (WEPSHI). Weld added with Rev. I to Plan. Weld replaces weld I-I 8. Examine O" to 12" (0 Ref. intersection of welds 1-20 & 1-11 ). Added with Re\". 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld (weld 1-20) within the circumferential weld examination \"olume of weld 1-11. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. Total Period: 3 l l448-WMKS-Ol02AZ-l 1-06Dl\.! 31 "-RC-8-250 IR 3 8-F B5.70 IA No UTIPT Segment RC-009 Revision Relief Request Comments STE ...\11.! GENERATOR - NOZZLE TO SAFE END BlfTT WELD. Total Period: l Total Segment: 4 11448-Wl-.!KS-OIOOAZ-1 1-12 27 1.1,"-RC-3-250 IR 3 B-J 89.11 IA No UT/PT Segment RC-010 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB), Tem1inal End. 11448-Wt-.!KS-1103A5 3-0lBC l 'l,"-RC-125-1502 3 8-J B9.32 IA No PT Segment RC-010 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD < 4 IN., (WEP8C). Total Period: 2 Total Segment: 2 Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 22of3'.' Print Date: JO 21 9-

Dra'l\ing Number 11448-\\'l\lKS-O!OIAZ-l Segment RC-011 Re,*ision Relief Request

                                                                      !\lark Number 1-12 Line Number 1

Comments 27 ,"-RC-6-250 IR Period 2 Catego1:r 8-J Item No. 89.11 ISi Class IA CIRCL1l\lFERENTIAL PIPING WELD 4 in. ~PS & >, (\\'EPCB), Tem1inal End. Augmt No

• l\lethod UT1PT Total Period: 1 11448-WMKS-I I 03A4 3-0IBC  !'*2"-RC-60-1502 3 8-J 89.32 IA No PT Segment RC-011 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD < 4 IN., (\\'EPBC).

Total Period: 1 Total Segment: 2 11448-Wl\lKS-OI02AZ-l 1-12 27'1>"-RC-9-250 IR 8-J 89.11 IA No UT/PT Segment RC-012 Re,*ision Relief Request SR-009 Comments CJRCL1l\lFERENTIAL PIPING WELD 4 in. NI'S & >, (WEPCB), Terminal End. Total Period: 1 11448-\\'l\lKS-I I03A6 3-01 BC l '.,"-RC-141-1502 3 8-J B9.32 IA No PT Segment RC-012 Re,*islon Relief Request Comments BRANCH PIPE CONNECTION WELD < 4 IN., (\\_'E_P_B_C~)-_ _ _ _ _ _ _ _ _ _ _ _ __ Total Period: 1 Total Segment: 2 11448-Wl\lKS-OIOOAZ-l l-17DM 27 1.;-RC-3-250IR 3 8-F 85.10 IA No UT Auto Segment RC-013 Re,*ision Relief Request SR-001 Comments REACTOR VESSEL- NOZZLE TO SAFE END BL1TT WELD. Per Relief Request (SR-001) perfonu a full volumetric examination from the ID (with 5% notch sensitiYity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perform L'T examination. Total Period: l Total Segment: l 11448-\\'l\lKS-OIOIAZ-l l-17DM 27\',"-RC-6-2501R 3 B-F 85.10 IA No L'TAuto Segment RC-014 Re,*ision Relief Request SR-001 Comments REACTOR VESSEL - NOZZLE TO SAFE END BL'Tr WELD. Per Relief Request (SR-00 I) perform a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBIS! NOTE: Perfonn L'T examination. Total Period: 1 Total Segment: l 11448-Wl\lKS-0102AZ-l 1-17DM 27\*',"-RC-9-2501R 3 8-F 85.10 IA No L'T Auto Segment RC-015 Re\'ision Relief Request SR-001 Comments REACTOR VESSEL - NOZZLE TO SAFE END BL1Tr WELD. Per Relief Request (SR-00 I) perfonn a full volumetric examination from the ID (with 5% notch sensitivity on the OD) in lieu of the surface examination from the OD. RBISI NOTE: Perfonn L'T examination. Total Period: 1 Total Segment: 1 11448-Wl\!KS-0122Hl 1-08 6"-RC-16-1502 8-J 89.11 IA No UT/PT Segment RC-016 Re\'ision Relief Request Comments CJRCL1l\lFERENTIAL PIPING WELD, (WEPCB). Tenuinal End. TI1is weld added to plan with Rev. I and replaces weld 1-05 on line 6"-RC-16-1502, !1448-Wl\lKS-0122Hl. RBISINOTE: Perfom1 L'TiPT examination. Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 23 of3'"' Print Date: IO 2 I 9'"'

Dr.ming Number  !\lark Number Line Number Total Period: Period Category Item No. ISi Class ..\ugmt

                                                                                                                                                                                      *l\lethod 11448-Wl\!KS-0122HI                                                 1-0IBC         6"-RC-16-1502                     2       8-J            89.31        IA                 No          L1T/PT Segment    RC-016       Re\'ision                     Relief Request                Comments      BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >.

Total Period: 1 Total Segment: 2 l !448-WMKS-0122KI 2-06 6"-RC-18-1502 B-J 89.11 IA No UT/PT Segment RC-017 Re\'ision Relief Request Comments CIRCUJ\IFERENTI,-\L PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: I 1 !448-Wl\lKS-0!22Kl 2-018C 6"-RC-18-1502 2 8-J 89.31 IA No l'TiPT Segment RC-017 Re\'ision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEP8C), 4 IN. NPS & >. Total Period: l 11448-WMKS-0122Kl 2-08 6"-RC-18-1502 3 B-J 89.11 IA No l 1T/PT Segment RC-017 Re,*ision Relief Request Comments CIRCUJ\IFERENTIAL PIPING WELD, (WEPC8). Terminal End. This weld added with Re\". I to plan and replaces weld 2-07 on line 6"-RC-18-1502, 11448-Wl\IKS-0!22Kl. RBIS! NOTE: Perfonn UT/PT examination. Total Period: 1 Total Segment: 3 11448-WMKS-012211 1-0IBC 6"-RC-21-1502 8-J 89.31 IA No Ff/PT Segment RC-018 Re\"ision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. 11448-Wl\lKS-0122Jl 1-02 6"-RC-21-1502 I 8-J 89.11 IA No L'T/PT Segment RC-018 Re,*ision Relief Request Comments CIRCL1l\lFERENTIAL PIPING WELD 4 in. NPS & >, (WEPC8). Total Period: 2 11448-WMKS-0!22Jl 1-08 6"-RC-21-1502 2 8-J 89.11 IA No UT/PT Segment RC-018 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPC8). Terminal End. This weld added with Rev. I to plan and replaces weld 2-03 on 6"-RC-18-1502, 11448-Wl\lKS-0122KI. RBIS~NOTE: Perform UT/PT examination. Total Period: I Total Segment: 3 11448-Wl\lKS-1103A7 1-02 12"-RC-I0-250lR 8-J 89.11 IA No L1T/PT Segment RC-019 Re\'ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPC8). Total Period: I 11448-Wl\lKS-1103A7 1-07 12"-RC-I0-2501R 2 8-J 89.11 IA No UT/PT Segment RC-019 Revision Relief Request Comments CIRCUI\IFERENTIAL PIPING WELD, (WEPC8), 4 in. NPS & >. Total Period: I 11448-Wl\lKS-1 !03A7 1-0IDI\I 12"-RC-I0-2501R 3 8-F 85.40 IA No L'T/PT Segment RC-019 Revision Relief Request Comments PRESSURIZER - NOZZLE TO SAFE END BL'TT WELD. Examine 100% Segments on Oass 1 .Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page24ofr Print Date: IO 21 :9-:

Segment Dra\\ing Number 11448-WI\IKS-l 103A7 RC-019 Re,*ision Relief Request

                                                                      !\lark Number 1-098C Line Number 12"-RC-I0-2501R Comments Period 3

Category 8-J Item No. 89.31 ISi Class IA Augmt No BRANCH PIPE CONNECTION WELD, (WEP8C). 4 IN. NPS &_>_._ _ _ _ _ _ _ _ _ _ _ _ __

                                                                                                                                                                                   *l\lethod l'TiPT Total Period: 2 Tcital Segment: 4 11448-WI\IKS-O 117Al-1                                                1-0IBC         14"-RH-1-1502                          8-J            89.31          IA             No           l'T/PT Segment RC-020            Re,*ision                     Relief Request                Comments      BRANCH PIPE CONNECTION WELD, (WEP8C), 4 IN. NPS & >.

11448-Wl\!KS-0117Al-l 1-05 14"-RH-1-1502 I 8-J 89.11 IA No l'T/PT Segment RC-020 Re,*ision Relief Request Comments CIRCl'I\IFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB), Tem1inal End. Total Period: 2 Total Segment: 2 11448-\\'l\!KS-1103Al 1-04 8"-RC-11-250 IR 3 8-J B9.l l IA No l'TiPT Segment RC-021 Re,*ision Relief Request Comments C!RCl'l\!FERENTIAL PIPING WELD, (WEPCB), 4 in. NPS & >, Tenninal End. Total Period: 1 Total Segment: 1 11448-Wl\!KS-1103A3 1-03 8"-RC-12-250 IR 3 B-J B9.l l IA No Segment RC-022 Re,*ision Relief Request Conunents C!RCL11\lFERENTIAI.. PIPING WELD, (\\'EPCB), 4 in. NI'S & >. 11448-WI\IKS-1103A3 1-04 8"-RC-12-250IR 3 8-J B9.l l IA No l'TIPT Segment RC-022 Re\"ision Relief Request Conunents CIRCU!\!FERENTIAL PIPING WELD, (WEPC8), 4 in. NI'S & >, Tenninal End. Total Period: 2 Total Segment: 2 I 1448-WI\IKS-I 103 ..\2 1-04 8"-RC-13-250IR 3 B-J 139.11 IA No l'T/PT Segment RC-023 Re\"ision Relief Request Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB), 4 in. NPS & >, Tenninal End. Total Period: 1 Total Segment: 1 11448-Wl\!KS-1103AIZ 1-0IBC 2"-RC-45-1502 2 8-J B9.32 IA No PT Segment RC-024 Re,*ision Relief Request Conunents BRANCH PIPE CONNECTION WELD< 4 IN., (WEPl3C). 11448-WI\IKS-I 103AIZ l-178C 2"-RC-45-1502 2 8-J 89.32 IA No PT Segment RC-024 Re\"ision Relief Request Comments BRANCH PIPE CONNECTION WELD< 4 IN., (WEP8C). Total Period: 2 11448-WI\IKS-1103AIZ 1-06 2"-RC-45-1502 3 8-J 89.40 I,\ No PT Segment RC-024 Re\"ision Relief Request Comments SOCKET WELD, (WEPSOK). I 1448-WMKS-I !03AIZ 1-10 2"-RC-45-1502 3 8-J 89.40 IA No PT Segment RC-024 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). I 1448-WMKS-I 103AIZ 1-14 2"-RC-45-1502 3 8-J 139.40 IA No PT Segment RC-024 Re\"ision Relief Request Comments SOCKET WELD, (WEPSOK). Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 25 ofr Print Dare: JO 21 9:C

Dra\\ing Number

• l\Ia1*k Number Line Number
• Period Total Period: 3 Category Item No. ISi Class Augmt

                                                                                                                                                                               *l\Iethod Total Segment: 5 11448-Wl\lKS-1103A3Z                                                 1-0IBC           2"-RC-46-1502                   2    8-J            89.32      IA              No          PT Segment      RC-025       ReYision                      Relief Request                 Comments        BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC).

Total Period: 1 11448-Wl\lKS-1103A3Z l-17BC 2"-RC-46-1502 3 8-J 89.32 IA No PT Segment RC-025 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC). I 1448-Wl\lKS-l !03A3Z 1-12 2"-RC I 502 3 8-J 89.40 IA No PT Segment RC-025 Re\"ision Relief Request Comments SOCKET WELD, (WEPSOK). I 1448-Wl\lKS-I 103:\3Z 1-04 2"-RC-46-1502 3 8-J 89.40 IA No PT Segment RC-025 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). I 1448-Wl\lKS-I I03A3Z 1-07 2"-RC-46-1502 3 8-J 89.40 IA No PT Segment RC-025 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 4 Total Segment: 5 I 1448-Wl\lKS-1103A2Z 1-0IBC 2"-RC-44-1502 2 8-J 89.32 IA No PT Segment RC-026 Re,*ision Relief Request Conunents BRANCH PIPE CONNECTION WELD, (WEPBC) < 4 in. NPS. I 1448-Wl\lKS-I I03A2Z l-17BC 2"-RC-44-1502 2 8-J 89.32 IA No PT Segment RC-026 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC). Total Period: 2 I 1448-Wl\lKS-I 103A2Z 1-15 2"-RC-44-1502 3 8-J 89.40 IA No PT Segment RC-026 Re,*ision Relief Request Conunents SOCKET Wl;LD, (WEPSOK). 11448-Wl\lKS-1103A2Z 1-11 2"-RC-44-1502 3 8-J 89.40 IA No PT Segment RC-026 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 2 Total Segment: 4 I I 448-Wl\lKS-O IOOA4Z 1-07 2"-RC-53-1502 B-1 89.40 IA No PT Segment RC-027 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). RBISI NOTE: Perform PT examination. l l448-Wl\lKS-O!OOA4Z 1-0IBC 2"-RC-53-1502 I B-1 89.32 IA No PT Segment RC-027 Re,*ision Relief Request Conunents BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. Total Period: 2 Total Segment: 2 11448-Wl\lKS-OIOIA2Z 1-0IBC 2"-RC-57-1502 I B-1 89.32 IA No PT Segment RC-028 Re\"ision Relief Request Comments BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. RBIS! NOTE: Perfom1 PT examination. Total Period: I Segments on Class 1 .Class 2 piping welds, Sorted bJ Segment (SPSU13 Database) Page 26 of 3: Print Date: 10'21.97

Drmling Number Total Segment: 1

• l\lai*k Number Line Number
• Period Catego~* Item No. ISi Class Augmt

                                                                                                                                                                                *l\lethod 11448-Wl\!KS-0102.-\2Z                                               1-0IBC          2"-RC-58-1502                  I   B-J           B9.32       1.-\                No          PT Segment      RC-029      Revision                     Relief Rcq uest                 Comments      BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS.

Total Period: l 11448-Wl\IKS-0102.-\2Z 1-09 2"-RC-58-1502 2 B-J 89.40 1.-\ No PT Segment RC-029 Revision Relief Request Comments SOCKET WELD, (WEPSOK), Terminal End. RBIS! NOTE: Perfomt PT examination. 11448-Wl\!KS-0102.-\2Z 1-06 2"-RC-58-1502 2 8-J B9.40 I.-\ No PT Segment RC-029 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-O I 02A2Z 1-03 2"-RC-58-1502 2 8-J B9.40 1.-\ No PT Segment RC-029 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 3 Total Segment: 4 11448-Wl\lKS-OI00.-\5Z 1-26 2"-RC-53-1502 I 8-J B9.40 I.-\ No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\!KS-OI00.-\5Z 1-23 2"-RC-53-1502 1 8-J 139.40 1.-\ No PT Segment RC-030 Re,*islon Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\!KS-0100.-\5Z 1-19 2"-RC-53-1502 I 8-J 89.40 1.-\ No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-0100.-\5Z 1-16 2"-RC-53-1502 1 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-\\'l\lKS-0100.-\5Z 1-11 2"-RC-53-1502 1 8-J B9.40 1.-\ No PT Segment RC-030 Revision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\!KS-O I 00.-\SZ 1-08 2"-RC-53-1502 I 8-J 89.40 IA No PT Segment RC-030 Revision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\lKS-O 100.-\SZ 1-01 2"-RC-53-1502 1 8-J 89.40 1.-\ No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-O I 00.-\4Z 1-45 2"-RC-53-1502 1 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). l 1448-WMKS-Ol00A4Z 1-15 2"-RC-53-1502 1 8-J B9.40 IA No PT Segment RC-030 Re,ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-0100.-\4Z 1-32 2"-RC-55-1502 I 8-J B9.40 I.-\ No PT Segment RC-030 Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK). Terminal End. 11448-Wl\lKS-0100.-\4Z 1-49 2"-RC-53-1502 1 8-J 89.40 1.-\ No PT Segment RC-030 Redsion Relief Request Conunents SOCKET WELD, (, (WEPSOK)K). 11448-WMKS-O I 00.-\4Z 1-11 2"-RC-53-1502 I 8-J B9.40 1.-\ No PT Segment RC-030 Revision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 12 l 1448-WMKS-0101A2Z 1-17 2"-RC-57-1502 2 8-J B9.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Segments on Oass 1 .Oass 2 piping welds, Sorted by Segment (SPSU13 Database) Page2'.'of3"' Print Date: IO 2 I 9'.'

Drm\ing Number I 1448-WMKS-0102A2Z

                                                                      !\lark Number 1-17 Line Number 2"-RC-58-1502

• Period 2

Category B-J Item No. 89.40 ISi Class IA

                                                                                                                                                              ..\ugmt No
                                                                                                                                                                              *l\lethod PT Segment RC-030            Re,*ision                     Relief Request                Comments       SOCKET WELD, (\\'EPSOK), Tenuinal End.

11448-WMKS-OIOIA2Z 1-41 2"-RC-57-1502 2 B-J 89.40 IA No PT Segment RC-030 ReYision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\lKS-OIOIA.2Z 1-12 2"-RC-57-1502 2 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 1 !448-Wl\lKS-OIOIA.2Z 1-37 2"-RC-56-15.02 2 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-Wl\lKS-0102A2Z 1-16 2"-RC-58-1502 2 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET WELD, (\VEPSOK), Tenuinal End. Total Period: 6 I !448-Wl\!KS-0102A2Z 1-39 2"-RC-59-1502 3 8-J 89.40 IA No PT Segment RC-030 Re,*ision Relief Request Comments SOCKET \\'ELD, (\VEPSOK). Total Period: l Total Segment: 19 11448-Wl\!KS-OI00..\4Z 1-25 2"-RC-55-1502 B-J 89.40 IA No PT Segment RC-031 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-OI00..\4Z 1-22 2"-RC-55-1502 I 8-J 89.40 I..\ No PT Segment RC-031 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Terminal End. 11448-\VMKS-OI00..\4Z 1-18BC 2"-RC-55-1502 B-J 89.32 IA No PT Segment RC-031 Re,*ision Relief Request Comments BRANCH CONNECTION WELD, (WEP8C), < 4 IN. NPS. Total Period: 3 Total Segment: 3 l 1448-WMKS-OIOIA2Z 1-228C 2"-RC-56-1502 8-J 89.32 IA No PT Segment RC-032 Re,*ision Relief Request Comments BRANCH CONNECTION WELD, (WEP8C), < 4 IN. NPS. Total Period: I I 1448-Wl\!KS-OIOl..\2Z 1-23 2"-RC-56-1502 2 8-J 89.40 IA No PT Segment RC-032 Revision Relief Request Comments SOCKET WELD, (WEPSOK). 11448-WMKS-O IO I ..\2Z 1-25 2"-RC-56-1502 2 8-J 89.40 IA No PT Segment RC-032 Re,*lsion Relief Request Comments SOCKET WELD, (WEPSOK). I !448-WMKS-OIOIA2Z 1-33 2"-RC-56-1502 2 8-J 89.40 IA No PT Segment RC-032 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 3 Total Segment: 4 11448-WMKS-0102A2Z 1-22 2"-RC-59-1502 2 8-J 89.40 IA No PT Segment RC-033 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). I !448-WMKS-0102..\2Z 1-25 2"-RC-59-1502 2 8-J 89.40 IA No PT Segment RC-033 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 28of3: Print Date: /0 219'.'

Segment RC-033 Draning Nwnber 11448-Wl\!KS-0102A2Z ReYision Relief Request

                                                                      !\lark Number 1-30 Line Number 2"-RC-59-1502 Conunents Period 2

Category B-J SOCKET WELD, (WEPSOK), Tem1inal End. Item No. 89.40 IA ISi Class Augmt No

• l\lethod PT 11448-\\'l\!KS-0102A2Z l-18BC 2"-RC-59-1502 2 B-J 89.32 IA No PT Segment RC-033 ReYision Relief Request Comments BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS.

Total Period: 4 Total Segment: 4 11448-Wl\!KS-1103A5 1-0IBC 3"-RC-131-1502 3 B-J 89.32 IA No PT Segment RC-034 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC). 11448-Wl\!KS-1103A5 1-02 3"-RC-131-1502 3 B-J 89.21 IA No PT Segment RC-034 ReYision Relief Request Comments C!RCU!v!FERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. Total Period: 2 Total Segment: 2 11448-Wl\!KS-1103A4 1-0IBC 3"-RC-116-1502 3 B-J 89.32 IA No PT Segment RC-035 Re,*ision Relief Request Conunents BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC). 11448-Wl\!KS-l 103A4 1-02 3"-RC-116-1502 3 B-J 89.40 IA No PT Segment RC-035 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). Total Period: 2 Total Segment: 2 11448-WMKS-l 103A6 1-02 3"-RC-147-1502 3 B-J 89.21 IA No PT Segment RC-036 ReYision Relief Request Conunents CIRCL'l\!FERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. 11448-\\'l\!KS-1103A6 1-0lBC 3"-RC-147-1502 3 B-J B9.32 IA No PT Segment RC-036 ReYision Relief Request Comments BRANCH PIPE CONNECTION WELD< 4 IN., (WEPBC). _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Total Period: 2 Total Segment: 2 I 1448-Wl\!KS-Ol00A6Z 1-03 2"-RC-198-1502 8-J 89.40 IA No PT Segment RC-037 Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK). RBISI NOTE: Perfonn PT examination. 11448-Wl\!KS-OlOOA6Z 1-0IBC 2"-RC-198-1502 I B-J B9.32 IA No PT Segment RC-037 ReYision Relief Request Conunents BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. Total Period: 2 Total Segment: 2 l 1448-Wl\!KS-Ol01A3Z 1-0lBC 2"-RC-199-1502 l B-J B9.32 IA No PT Segment RC-038 Re,*ision Relief Request Comments BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. Total Period: 1 Total Segment: 1 Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 29 of37 PrintDate: 10.,21197

Segment Dra\\ing Nwnber l 1448-Wl\lKS-0102A3Z RC-039 Re,*ision Relief Request

                                                                       !\lark Number 1-0IBC Line Number 2"-RC-200-1502 Conunents Period 2

Category 8-J Item No. 89.32 BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. IS[ Class IA Augmt No

                                                                                                                                                                                          *l\lethod PT Total Period: I 11448-Wl\lKS-O I 02A3Z                                                1-04            2"-RC-200-1502                    3       8-J             89.40       IA                 No           PT Segment RC-039            Re,*ision                     Relief Request                 Comments      SOCKET WELD, (WEPSOK).

11448-Wl\lKS-0102A3Z 1-07 2"-RC-200-1502 3 8-J 89.40 IA No PT Segment RC-039 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). RBIS! NOTE: Perform PT examination. Total Period: 2 Total Segment: 3 11448-Wl\lKS-OIOOA2Z 1-12 2"-CH-5-1502 8-J 89.21 IA No PT Segment RC-040 Re,*ision Relief Request Comments CIRCLil\ffERENTIAL PIPING WELD < 4 in. NPS. I 1448-Wl\lKS-OIOOA2Z 1-0IBC 2"-CH-5-1502 8-J 89.32 lA No PT Segment RC-040 Re,*ision Relief Request Comments BRANCH CONNECTION WELD, (WEPBC), < 4 IN. NPS. 11448-Wl\lKS-OIOOA2Z 1-05 2"-CH-5-1502 1 8-J 89.21 IA No PT Segment RC-040 Re\"ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD < 4 in. NPS. I 1448-Wl\lKS-O I 00,\2Z 1-09 2"-CH-5-1502 I 8-J 89.21 IA No PT Segment RC-040 Re,*ision Relief Re11uest Comments ClRCUl\lFERENTIAL PIPING WELD< 4 in. NPS. I 1448-Wl\lKS-0100:\2Z 1-03 2"-CH-5-1502 I 8-J 89.21 IA No PT Segment RC-040 Re,*ision Relief Request Comments CIRClll\lFERENTIAL PIPING WELD < 4 in. NPS. Total Period: 5 Total Segment: 5 11448-Wl\lKS-0127JI 1-04 6"-RC-17-1502 8-J 89.11 IA No Ff!PT Segment RC-041 Re\"ision Relief Request Comments CIRCUl\lFERENTUL PIPING WELD 4 in. NPS & >, (WEPCB). RBIS! NOTE: Perfonn LIT/PT examination. Total Period: 11448-Wl\IKS-O 12711 1-0IBC 6"-RC-17-1502 3 8-J 89.31 IA No LIT/PT Segment RC-041 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: l Total Segment: 2 11448-Wl\IKS-012712 1-0IBC 6"-RC-19-1502 3 8-J 89.3 I IA No Segment RC-042 Re\"ision Relief Request Conunents BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. 11448-Wl\IKS-012712 1-04 6"-RC-19-1502 3 8-J 89.11 IA No VT/PT Segment RC-042 Re,*ision Relief Request Conunents CIRClll\ffERENTIAL PIPING WELD, (WEPCB). Terminal End. Weld added with Rev. I to plan. and replaces weld 1-03 on line 8"-RC-l l-2501R. RBIS! NOTE: Perfom1 LIT/PT examination. Total Period: 2 Total Segment: 2 Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 30 of 3: Print Date: IO 2 I 9'.'

Dra\\ing Number Segment I I 448-\\'M KS-0 I 27 .13 RC-043 Re\"ision Relief Request

                                                                       !\lark Number 1-03 Line Number 6"-RC-20-1502 Comments

• Period 2

Category 8-J Item No. 89.J I ISi Class IA Augmt No

                                                                                                                                                                                                    *l\lethod UT/PT CJRCL1l\lFERENTIAL PIPING WELD, (\\'El'C8). Tenninal End. TI1is weld added to plan with Re\'. I and replaces weld 1-04 on line 6"-RC-20-1502, 11448-Wl\lKS-012713. RBIS[ NOTE: Perfom1 UT/PT examination.

Total Period: I 1448-Wt-.IKS-0127.13 1-0JBC 6"-RC-20-1502 3 8-J 89.31 IA No UT/PT Segment RC-043 Re\"ision Relief Request Comments BRANCH PIPE CONNECTION WELD, (\\'EP8C), 4 IN. NPS & >. Total Period: I Total Segment: 2 I 1448-\\'l\IKS-0125Al-1 1-11 4"-RC-14-1502 2 8-J 89.J I IA Yes UT/PT Segment RC-044 Re\"ision 2 Relief Request Conunents CIRCUI\IFERENTIAL PIPING WELD, (\\'EPCB), 4 in. NPS & >, Tenninal End. TS Item 2.1.1 added to plan with Rev. 2 to plan due to amendment I 87 to Technical Specifications. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the intern!. 11448-Wt-.IKS-0125 ..\1-1 1-04 4"-RC-14-1502 2 8-J 89. l I IA No UT/PT Segment RC-044 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB), 4 in. NPS & >. 11448-Wl\IKS-0125AI-I 1-0IBC 4"-RC-14-1502 2 8-J 89.31 IA No L'T/PT Segment RC-044 Re\"ision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: 3 I !448-Wl\IKS-0125Al-1 1-18 4"-RC-14-1502 3 8-J 89.11 IA Yes FfiPT Segment RC-044 Re,*ision 8 Relief Request Conunents CIRCUI\IFERENTIAL PIPING WELD, (WEPC8), Tenninal End. TS Item 2.1.1 added to plan with Rev. 2 to plan due to amendment 187 to Teclmical Specifications. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the inter\"al. Changed year to 2003 with Rev. 8 to plan, to ensure 5% of the welds are examined e\"ery refueling outage. 11448-Wl\IKS-0125AI-J 1-12 4"-RC-14-1502 3 8-J 89.11 IA Yes L'TtPT Segment RC-044 Re\"ision 8 Relief Req nest Comments CIRCL'l\lFERENTIAL PIPING WELD, (WEPC8), Tem1inal End. TS Item 2.1.1 added to plan with Rev. 2 to plan due to amendment 187 to Technical Specifications. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the inten*al. Added year 200 I with Rev. 8 to plan, to ensure 5% of the welds are examined e\"ery refueling outage. Total Period: 2 Total Segment: 5 11448-Wl\IKS-0125Al-2 2-08 4"-RC-15-1502 2 8-J 89.11 IA Yes UT/PT Segment RC-045 8 Relief Req nest Conunents CIRCUMFERENTIAL PIPING WELD, (\\'EPCB). TS Item 2.1.1 added to plan with Rev. 2 to plan due to amendment 187 to Technical Specifications. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the inten'al. Changed year to 2000 with Rev. 8 to plan, to ensure 5% of the welds are examined e\"C!)' refueling outage. Total Period: I 11448-Wl\IKS-0125..\1-2 2-0IBC 4"-RC-15-1502 3 8-J 89.31 IA No L'T/PT Segment RC-045 Re\"ision Relief Req nest Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: I Total Segment: 2 Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 31 of 3'.' Print Date: 10:2//97

Dra\\ing Nwnber 11448-WMKS-0122LI Segment RC-046 Revision 5 Relief Request l\lark Number 1-05 Line Number 12"-RC-22-1502 Comments

• Period 2

Category B-J Item No. B9.ll IA ISi Class Augmt No l\lethod l 1T/PT CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (\VEPCB). Period changed from I to 2 with Re\". 5 to plan. 11448-Wl\lKS-0122Ll 1-0IBC 12"-RC-22-1502 2 B-J B9.31 IA No L'TiPT Segment RC-046 Revision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: 2 11448-\Vl\!KS-0!22LI 1-09 12"-RC-22-1502 3 B-J B9.I I IA No l'T'PT Segment RC-046 Re,*ision Relief Request Comments CIRCL'1'.IFERENTIAL PIPING WELD, (WEPCB). Terminal End. Weld added to plan with ReY. I and replaces weld 1-03 on line 8"-RC-13-2501R, 11448-WMKS-1103A2. Total Period: 1 Total Segment: 3 11448-Wl\IKS-0122DI 1-0IBC I 2"-RC-23-1502 B-J B9.31 IA No l 1TPT Segment RC-047 Revision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: l 11448-Wl\lKS-0!22DI 1-09 l 2"-RC-23-1502 2 B-J B9.l l IA No l'T PT Segment RC-047 Revision Relief Request Comments Circumferential Piping Weld (WEPCB). Terminal End. This weld added with Re,*. I to plan. This weld replaces weld 1-07 on line 12"-RC-23-1502, 11448-Wl\!KS-0122DI. Total Period: l Total Segment: 2 11448-Wl\!KS-O 122A2 1-04 12"-RC-24-1502 B-J B9.ll IA No L1TiPT Segment RC-048 Revision Relief Request Comments CIRCL1l\lFERENTIAL PIPING WELD, (WEPCB). Terminal End. ll1is weld added to plan with Rev. I to plan. This weld replaces weld 1-03 on line 12"-RC-!0-2501R, 11448-Wl\lKS-1103,\7. 11448-Wl\!KS-0122:\2 1-0IBC 12"-RC-24-1502 I B-J B9.3 I IA No L'T 1PT Segment RC-048 Revision Relief Request Comments BRANCH PIPE CONNECTION WELD, (WEPBC), 4 IN. NPS & >. Total Period: 2 11448-WMKS-O 122A2 1-03 12"-RC-24-1502 2 B-J B9.11 IA No L'T/PT Segment RC-048 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: l Total Segment: 3 11448-WMKS-1 !05C4 1-0IBC 3 "-CH-1-1502 3 B-J B9.32 IA No PT Segment RC-049 Re,*ision Relief Request Comments BRANCH PIPE CONNECTION WELD < 4 IN., (WEPBC). 11448-WMKS-1 !05C4 1-02 3"-CH-1-1502 3 B-J B9.21 IA No PT Segment RC-049 Re,ision Relief Request Comments CIRCUl\lFERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. Total Period: 2 Total Segment: 2 11448-WMKS-0!25Al-2 2-25DM 4"-RC-15-1502 2 B-F B5.40 IA No l 1TiPT Segment RC-051 Re,*ision Relief Request Comments PRESSURIZER - NOZZLE TO SAFE END BUTT WELD. Examine I 00% Segments on C1ass 1 _C1ass 2 piping welds, Sorted by Segment (SPSU13 Database) Page 32 of37 Print Date: IO 21 9'."

Dra\\ing Number* l\lark Number Line Nwnber Total Period: 1 Period Category Item No. ISi Class Augmt

                                                                                                                                                                                               *Method 11448-WMKS-0125.-\1-2                                               2-24            4"-RC-15-1502                     3       8-J             89.11            1.-\                 Yes          l'T/PT Segment      RC-051          Re,*ision  8              Relief Request                Comments      CIRCL'l\!FERENTIAL PIPING WELD, (WEPCB), Tem1inal End. TS Item 2.1.1 added to plan with Rev. 2 to plan. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Changed year to 2003 with Rev. 8 to plan, to ensure 5% of the welds are examined every refueling outage.

11448-Wl\!KS-0125.-\1-2 2-20 4"-RC-15-1502 3 8-J 89.11 1.-\ No l'T/PT Segment RC-051 Re\'isioQ Relief Request Comments CIRCL'l\!FERENTI.-\L PIPING WELD, (WEPCB), 4 in. NPS & >, Terminal End. 11448-Wl\!KS-0125.-\1-2 2-19 4"-RC-15-1502 3 8-J 89.11 I.-\ No Ff/PT Segment RC-051 Revision Relief Request Conunents CIRCUMFERENTIAL PIPING \\/ELD, (WEPCB), 4 in. NPS & >, Terminal End. 11448-Wl\!KS-0125.-\1-1 1-20 4"-RC-14-1502 3 8-J 89.11 I.-\ No Ff.PT Segment RC-051 Re,*ision Relief Request Comments ClRCL1l\lFERENTI...\L PIPING WELD, (WEPCB), 4 in. & >, Tem1inal End. Total Period: 4 Total Segment: 5 I I 448-Wl\!KS-O I 24.-\ 1-1 1-02 6"-RC-39-1502 8-J 89.11 I.-\ No L'T/PT Segment RC-052 Re,*ision Relief Request Conunents ClRCUl\lFERENTI...\L PIPING WELD 4 in. NPS & >, (\\'EPCB), Tem1inal End. 11448-\\'l\!KS-0124.-\1-1 1-0IDl\l 6"-RC-39-1502 I 8-F 85.40 I.-\ No L'T'PT Segment RC-052 Re,*ision Relief Request Comments PRESSURIZER - NOZZLE TO S...\FE END BUTT WELD. Examine 100%. Total Period: 2 11448-Wl\!KS-O 124.-\1-1 1-08 6"-RC-39-1502 2 8-J 89.11 I.-\ No L'T!PT Segment RC-052 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB), 4 in NPS & >, Tem1inal End. Total Period: 1 Total Segment: 3 11448-Wl\!KS-0124.-\1-1 2-02 6"-RC-38-1502 2 B-J 89.11 I.-\ No l'TIPT Segment RC-053 Revision Relief Request Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB), 4 in NPS & >, Terminal End. 11448-Wl\!KS-0124.-\1-1 2-08 6"-RC-38-1502 2 B-J 89.11 1.-\ No L'T/PT Segment RC-053 Re,*ision Relief Request Comments CIRCUMFERENTI...\L PIPING WELD, (WEPCB), 4 in. NPS & >, Tenninal End. 11448-Wl\!KS-0124.-\1-1 2-0IDM 6"-RC-38-1502 2 8-F 85.40 I.-\ No L'T/PT Segment RC-053 Revision ~elief Request Comments PRESSURIZER - NOZZLE TO S...\FE END BUTT WELD. Examine I 00%. Total Period: 3 Total Segment: 3 11448-Wl\!KS-0124.-\1-1 4-08 6"-RC-37-1502 2 8-J 89.11 1.-\ No l'T'PT Segment RC-054 Re,*ision Relief Request Comments CIRCL'MFERENTI...\L PIPING WELD, (WEPCB), 4 in. NPS & >, Tem1inal End. 11448-Wl\!KS-0124.-\1-1 4-02 6"-RC-37-1502 2 8-J 89.11 1.-\ No L'T/PT Segment RC-054 Re,*ision Relief Request Comments CJRCUMFERENTI...\L PIPING WELD, (\\'EPCB), 4 in. NPS & >, Tem1inal End. 11448-WMKS-0124.-\1-1 4-0IDM 6"-RC-37-1502 2 8-F 85.40 I.-\ No L'T/PT Segment RC-054 Revision Relief Request Comments PRESSURIZER-NOZZLE TO S...\FE END BUTT WELD. Examine 100%. Total Period: 3 Segments on Class 1 _Gass 2 piping welds, Sorted by Segment (SPSU13 Database) Page33 ofr Print Date: 1021 97

Dra\\ing Number Total Segment: 3

                                                                     !\lark Number    Line Number

• Period Category Item No. ISi Class Augmt

                                                                                                                                                                                                     *l\Iethod 11448-Wl\lKS-0124Al-1                                               3-07BC          3"-RC-3 5-1502                       2       8-J              89.32            IA                     No           PT Segment    RC-057        Re,*ision      2              Relief Request      SR-017    Comments        BRANCH CONNECTION WELD, (WEPBC). TS item 2.1.3 Remo\'ed Technical Specification reference from plan with Re,*. 2 to plan due to amendment 187 to Teclmical Specifications.

11448-WMKS-0124Al-1 3-0IDM 4"-RC-34-1502 2 8-F 85.40 IA No L'T/PT Segment RC-057 Re,*ision Relief Request Comments PRESSL1RIZER - NOZZLE TO SAFE END BUTf WELD. Examine I 00%. 11448-Wl\!KS-0124Al-1 3-02 4"-RC-34-1502 2 8-J 89.11 IA No L'T/PT Segment RC-057 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB), 4 in. NPS & >, Terminal End. Total Period: 3 Total Segment: 3 11448-Wl\lKS-0124Al-1 3-10 3"-RC-35-1502 2 8-J B9.21 IA No PT Segment RC-058 Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. Total Period: I 11448-Wl\lKS-0124Al-l 19 3"-RC-35-1502 3 B-J 89.40 IA No PT Segment RC-058 Re,*ision Relief Request Comments SOCKET WELD, (WEPSOK). RBIS! NOTE: Perfom1 PT examination. Total Period: I Total Segment: 2 11448-Wl\lKS-0124Al-I 3-16 3 "-RC-61-1502 2 8-J 89.21 IA No PT Segment RC-059 Re,*ision Relief Request Comments CIRCUl\!FERENTIAL PIPING WELD, (WEPCB), < 4 in. NPS. Total Period: I Total Segment: I I 1448-Wl\lKS-0125Al-2 3-07 1'.,"-RC-105-1502 3 8-J B9.40 IA No PT Segment RC-060A Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK), Terminal End. RBISI NOTE: Perform PT examination. I !448-Wl\lKS-0125Al-2 3-05  !',',"-RC-105-1502 3 B-J 89.40 IA No PT Segment RC-060A Re\'ision Relief Request Conunents SOCKET WELD, (WEPSOK) I 1448-WMKS-0125Al-2 3-0IBC I W'-RC-105-1502 3 B-J 89.32 IA Yes PT Segment RC-060A Re\'ision 8 Relief Request Comments BRANCH CONNECTION WELD, (WEPBC). TS item 2. I. I Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. This weld was changed from a Teclmical Specification Item 2.1.3 to a Technical Specification Item 2.1.1 (with Re\'. 2 to plan) due to amendment 187 to Technical Specifications. Changed year to 2003 with Rev. 8 to plan, to ensure 5% of the welds are examined every refueling outage. Total Period: 3 Total Segment: 3 I 1448-Wl\lKS-0125Al-2 3-1 I H~"-RC-105-1502 3 B-J 89.40 IA No PT Segment RC-0608 Re,*ision Relief Request Conunents SOCKET WELD, (WEPSOK) Total Period: I Segments on Oass I .Oass 2 piping welds, Sorted by Segment (SPSUIJ Database) Page 34 of37 Print Date: I 0.'21/97

Dra\\ing Number Total Segment:

• l\lat*k Number Line Number
• Period Category Item No. ISi Class Augmt

                                                                                                                                                                                                        *Method I 1448-WMKS-0125Al-2                                                 4-0IBC           2"-Cl!-68-1502                       2       B-J              89.32            IA                   No              PT Segment       RC-061        Re,*ision                   Relief Request                 Comments       BRANCH CONNECTION WELD< 4 IN. (WEPBC)

Total Period: I 11448-\\'l\lKS-0125AIZ 1-04 2"-CH-68-1502 3 B-J B9.40 IA No PT Segment RC-061 Revision Relief Request Comments SOCKET WELD. (WEPSOK). Tem1inal End. This weld added to plan with Re,*. I.. and replaces weld 1-02 on line 2"-CH-68-1502. Total Period: l Total Segment: 2 11448-\\'l\lKS-0117.-\1-1 0-01 L 14"-RH-18-602 C-F-1 C5.12 2A No l 1TiPT Segment RH-003 Re,*ision 3 Relief Request Comments Piping Weld 3/8 in. & > nominal wall thickness. longitudinal (fitting). Examine 2.5t (1.095 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld ....\dded with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination \'Olume of welds 2-0 I and 2-02. Examination requirements must be met for both trans\'erse & parallel flaws in the examination area of the longitudinal weld. J \448-\\'l\!KS-0117...\1-1 2-01 14"-RH-18-602 C-F-1 C5.I I 2A No l'T'PT Segment RH-003 Re\'lsion Relief Request Comments CIRCl!l\IFERENTI...\L PIPING WELD (WEPCB) 3.8 in. & > nominal wall thickness. 11448-\\'l\lKS-O 122.-\1 2-16 IO"-RH-16-1502 I C-F-1 CS.I I 2A No L'T!PT Segment RH-003 Re,*ision Relief Request Comments CIRCl!l\lFERENTI...\L PIPING WELD (WEPCB). 3/8 in. & > nominal wall thickness. Total Period: 3 11448-\\'l\lKS-0117 ...\2 2-26 12"-RH-19-602 2 C-F-1 CS.II 2.-\ No l 1TtPT Segment RH-003 Revision Relief Request Comments CIRCL1MFERENTI...\L PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness. 11448-Wl\lKS-0117...\1-2 3-11 I 2"-RH-6-602 2 C-F-1 C5. I 1 2A No l!T/PT Segment RH-003 Revision Relief Request Comments CIRCl!l\lFERENTI...\L PIPING WELD (\\'EPCB) 3.'8 in. & > nominal wall thickness. 11448-Wl\lKS-0117.-\1-1 0-13L I 4"-RH-2-602 2 C-F-1 C5.12 2.-\ No L'T/PT Segment RH-003 Revision 3 Relief Request Comments Piping Weld 3/8 in. & > nominal wall thickness, longitudinal. Examine 2.5t (l.095 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination \'olume of welds 2-06 and 2-

07. Examination requirements must be met for both transwrse & parallel flaws in the examination area of the longitudinal weld.

11448-Wl\lKS-0117.-\1-1 2-07 l 4"-RH-2-602 2 C-F-1 C5. I 1 2.-\ No UT/PT Segment RH-003 Revision Relief Request Comments CIRCUMFERENTI...\L PIPING WELD (WEPCB) 3/8 in. & > nominal wall thickness. Total Period: 4 11448-Wl\IKS-0117...\2 0-14L l 2"-RH-19-602 3 C-F-1 C5.12 2.-\ No l!T/PT Segment RH-003 Re,*ision 3 Relief Request Comments Piping weld 3/8 in. & > nominal wall thickness, longitudinal. Examine 2.5t (0.937 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination ,*olume of welds 2-28 and 2-

29. Examination requirements must be met for both trans\'erse & parallel flaws in the examination area of the longitudinal weld.

Segments on Class 1 _Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 35 of 3'.' Print Date: /0 21*97

Dra'\\ing Number 11448-\VMKS-O 117 A2 Segment RH-003 Re,*ision

                                                                      !\lark Number 2-03 Relief Request Line Number I 2"-RH-12-602 Comments

• Period 3

Category C-F-1 Item No. CS. I I 2A ISi Class CIRCL'l\!FERENTl,\L PIPING WELD, (WEPCB) 3/8 in. & > nominal wall thickness. Augrnt No

                                                                                                                                                                                                    *Method l 1T/PT 11448-WMKS-0117A2                                                    2-29            I 2"-RH-19-602                       3       C-F-1            CS. I I         2A                   No Segment RH-003            ReYision                      Relief Request                 Comments      CIRCL'MFERENTIAL PIPING WELD, (\VEPCB) 3/8 in. & > nominal wall thickness.

11448-Wl\!KS-0! 17.J..1. 0-16L 12"-RH-12-602 3 C-F-1 CS.12 2A No Segment RH-003 Re,*ision 3 Relief Request Comments Piping weld 3/8 in. & > nominal wall thickness, longitudinal. Examine 2.5t (0.937 in.) at both intersecting circumferential welds, i.e., examine both ends of the longitudinal weld. Added with Rev. 3 to plan: Per Code Case N-524 & NRC Ltr. 94-569, the examination area includes only that length of the longitudinal weld within the circumferential weld examination Yolume of welds 2-02 and 2-

03. Examination requirements must be met for both tra11S\'erse & parallel flaws in the examination area of the longitudinal weld.

Total Period: .J Total Segment: 11 11448-\Vl\!KS-0122Al 2-09 6"-RH-14-602 C-F-1 C5.l I 2A No lTT;PT Segment RH-003B Re,*ision Relief Request Comments CIRCL1l\ffERENTI.-\L PIPING WELD (WEPCB). 3/8 in. & > nominal wall thickness. RBIS! NOTE: Perfomt LIT examination. Total Period: l Total Segment: I 11448-WMKS-0!22Dl 2-01 IO"-RH-16-1502 B-J B9.ll IA No LTTIPT Segment RH-008 Re,'ision Relief Request Comments CIRCLIMFERENTIAL PIPING WELD, (WEPCB). Total Period: I l 1448-WMKS-0122Al 1-11 10"-RH-16-1502 2 13-J 139.11 IA No lTT/PT Segment RH-008 Re,*ision Relief Request Comments CJRCL1l\!FERENTI.-\L PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: I 11448-\VMKS-O 122A I 1-12 10"-RH-16-1502 3 B-J B9.l l IA No LIT/PT Segment RH-008 Re,*islon Relief Request Conunents CIRCL'MFERENTIAL PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: I Total Segment: 3 11448-WMKS-0!22A2 2-04 I O"-RH-17-1502 2 B-J 89.11 IA No LTT/PT Segment RH-009 Re,*ision Relief Request Comments CIRCL'MFERENTI.-\L PIPING WELD 4 in. NPS & >, (WEPCB). Total Period: l Total Segment: I 11448-WMKS-I JOIA5 1-03 l 2"-RS-8-153 C-F-1 CS.I I 2A No l 1T/PT Segment RS-003A Re\'ision Relief Request Comments CIRCL'MFERENTI.-\L PIPING WELD, (WEPCB). 318 in. & > Nominal Wall il1ickness. RBIS! NOTE: Perform UT examination. Total Period: l Total Segment: l Segments on Class 1 .Class 2 piping welds, Sorted by Segment (SPSU13 Database) Page 36 of 3'.' Print Date: 10'21/97

Segment Draning Number 11448-W~IKS-! IO!A5 RS-003 B Re,*ision Relief Request

                                                                       !\lark Number 1-02 Line Number 12"-RS-8-153 Comments

• Period Category C-F-1 Item No.

CS.I I 2A ISi Class Augmt No CIRCL1~IFERENTIAL PIPING WELD, (WE°PCB). 3 18 in. & > Nominal \\'all ll1ickness.

                                                                                                                                                                                       *Method L'T/PT Total Period: 1 Total Segment: I 11448-WMKS-! IOIAS                                                    1-06            12"-RS-7-153                   3      C-F-1         C5. I 1      2A                    No          L'T/PT Segment    RS-004.-\      Re\"ision                      Relief Request                Comments     CIRCUMFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. RBIS! NOTE:

Perform UT examination. Total Period: I Total Segment: 1 11448-W~IKS-I IOl.-\5 1-05 12"-RS-7-153 2 C-F-1 CS. I I 2.-\ No Segment RS-004B Re,*ision Relief Request Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). 3/8 in. & > Nominal Wall Thickness. Total Period: I Total Segment: I Record Count: 389 Segments on Class 1 _Class 2 piping n*elds, Sorted by Segment (SPSU13 Database) PageJ'."'ofr Print Date: IO 21 9-}}