ML20058L861

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Resolution of ISLOCA for Abwr. W/27 Oversize Encl
ML20058L861
Person / Time
Site: 05200001
Issue date: 04/30/1993
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GENERAL ELECTRIC CO.
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ML20058L859 List:
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NUDOCS 9305130053
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Resolution of Intersystem Loss of Coolant Accident for ABWR April 1993 Prepared by GE Nuclear Energy l

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9305130053 9304'30 PDR ADOCK 05200001 A pm

1 Page 1 Introduction Ar intersystem loss of coolant accident (ISLOCA) is postulated to occur when a series of failures or inadvertent actions occur that allow the high pressure from one system to be applied to the low design pressure of another system, which could potentially rupture the pipe and release coolant from the reactor system pressure boundary. This may also occur within the high and low pressure portions of a single system. Future ALWR designs like the ABWR are expected to reduce the possibility of a LOCA outside the containment by designing to the extent practicable all piping systems, major system components (pumps and valves), and subsystems connected to the reactor coolant pressure boundary (RCPB) to an ultimate rupture strength (URS) at least equal to the full RCPB pressure.

The general URS criteria was recommended by the Reference I and the NRC Staff recommended specific URS design characteristics by Reference 2.

ABWR Regulatory Requirements

. In SECY-90-016 and SECY-93-087 (References 3 and 4), the NRC staff resolved the ISLOCA issue for advanced light water reactor plants by requiring that low-pressure piping systems that interface with the reactor coolant pressure boundary be designed to withstand reactor pressure to the extent practicable. However, the staff believes that for those systems ,

that have not been designed to withstand full reactor pressure, )

evolutionary ALWRs should provide (1) the capability for leak testing the  !

pressure isolation valves, (2) valve position indication that is available in l the control room when isolation valve operators are deenergized and (3) high-pressure alarms to warn main control room operators when rising j reactor pressure approaches the design pressure of attached low-pressure systems or when both isolation valves are not closed. The staff noted that for some low-pressure systems attached to the RCPB, it may not be )

practical or ne-cessary to provide a higher system ultimate pressure capability for the entire low-pressure connected system. The staff will

Page 2 r

l evaluate such exceptions on a case-by-case basis during specific design certification reviews.

GE provided a proposed implementation of the issue resolution for the ,

ABWR in Reference 5. The staff in the Civil Engineering and Geosciences l Branch of the Division of Engineering completed its evaluation of this proposal. Specifically, as reported by Reference 2 and summarized below,  ;

the staff has evaluated the minimum pressure for which low-pressure systems should be designed to ensure reasonable protection against burst failure should the low-pressure system be subjected to full RCPB pressure.

Reference 2 found that for the ABWR the design pressure for the low-pressure piping systems that interface with the RCPB should be equal to 0.4 times the normal operating RCPB pressure of 1025 psig (i.e., 410 psig),

the minimum wall thickness of low-pressure piping should be no less than that of a standard weight pipe, and that Class 300 valves are adequate.

The design is to be in accordance with the ASME Boiler and Pressure Vessel Code,Section III, Subarticle NC/ND-3600. Furthermore, the staff will continue to require periodic surveillance and leak rate testing of the pressure isolation valves per Technical Specification requirements as a part of the ISI program.

Boundary Limits of URS i

Guidance given by Reference 3 provides provision for applying practical i considerations for the extent to which systems are upgraded to the URS design pressure. The following items form the basis of what constitutes practicality and set forth the test of practicality used to establish the I boundary limits of URS for the ABWR:

l 1. It is impractical to design large tank structures to the URS design

! pressure that are vented to atmosphere and have a low design 1 pressure. Tanks included in this category are:

Condensate storage tank, SLC main tank, i l

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Page 3 LCW receiving tank, HCW receiving tank, FPC skimmer surge tank, and FPC spent fuel storage pool and cask pit.

These are termed low pressure sinks for the purposes of this  ;

report. The suppression pool is also a low pressure sink that is impractical to upgrade its pressure since it is part of the containment structure, which is designed to contain the most severe LOCA.

2. It is impractical to consider a disruptive open flow path from reactor pressure to a low pressure sink. As a consequence, the furthest downstream valve in such a path is assumed closed l (with nominal leakage) so that essentially all of the static reactor pressure is contained by the URS upgrade. j l
3. It is impractical to design piping systems that are conne.cted to l low pressure sink features to URS design pressure when the t

pipmg is always locked open to a low pressure sink by locked i open valves. Nominal leakage past the last closed valve is the only pressure source that could pressurize the line, and that line is locked open to the low pressure sink vented to atmosphere.

As implied above, boundary limits of the URS design are established assuming slow rates of leakage between high and low pressure regions. A key assumption to understanding the establishment of the boundary limits from the above practicality basis is that only static pressure conditions are considered. Static conditions result by assuming that the valve adjacent to a low pressure sink remains closed, yet considering a slow leak rate that I would not over pressurize the down stream piping and components. Thus, the dynamic pressurization effects, violent high flow transients, and temperature escalations are precluded that would occur if the full RCPB pressure was connected directly to the low pressure sink. This means only  ;

l static pressurization with small leak flow needs to be considered and low pressure sinks do not pressurize because the path to the sink is open. In l

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summary, the components considered to be low pressure sinks in this  !

evaluation are:

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(1) Suppression Pool - Provides a normal low pressure sink, approximately 0.05 arg (0.75 psig) above atmospheric for its interfacmg i systems and the first closed valve is at least 28.8 atg (410 psig) rated. The ,

suppression pool is designed to Seismic Category L The large mass of suppression pool water is designed to absorb reactor l safety relief valve discharges or high energy LOCA discharges and can easily accept the ISLOCA pressure produced small leak flow from any of the interfacing systems. The RHR System can pump excess inventory to  :

radwaste, and any heat additions are removed by the RHR heat exchangers. Replacement of the lost inventory from the RCPB is available from the normal feedwater control source. Therefore, the suppression pool volume does not need to be designed to higher pressure and temperature than the current design.

(2) Condensate Storage Tank - Vented to atmosphere and its locked open valves and stainless steel piping insure it is a low pressure sink for its  ;

interfacing systems. The first closed valve of each interfacing system with  ;

URS upgrade is at least 28.8 atg (410 psig) rating.  ;

i The large water mass in the Condensate Storage Tank and its large excess volume can easily accept the ISLOCA pressure produced small leak flow addition from a potential ISLOCA event of any interfacing system. Excess inventory can be pumped to radwaste. Replacement of low inventory from the RCPB is available from the normal feedwater control source. Therefore, i the current design requirements are more than adequate.

I l (3) SLC main tank - Vented to atmosphere with the first closed valve at least 28.8 atg (410 psig) rating. The SLC main tank is designed to Seismic j Category I.

The SLC storage tank containing borated water can be used to accept ISLOCA pressure produced small leak flow, but dilution of the borated l

Page 5 solution in the tank should be avoided. The MUWP system interface to SLC ,

normally maintains a positive pressure above the SLC storage tank static head in the SLC pump suction piping connected to the SLC storage tank.

Any ISLOCA small leak flow would normally be received by the MUWP system interface through a normally open valve and an open path to the Condensate Storage Tank. ISLOCA pressure produced small leak flow would be accepted by the Condensate Storage Tank. In the rare event that the MUWP interface is closed, any ISLOCA small leak flow from the RCPB into the vented-to-atmosphere SLC tank would be removed in the normal manner. Therefore, the current design basis is appropriate and does not ,

need revision relative to ISLOCA effects.

(4) LCW Receiving Tank - Vented to atmosphere, and the first closed valve is at least 28.8 atg (410 psig) and one of the dual tank's inlet valves is locked open.

The availability of two LCW tanks overflowing to the radwaste LCW sump provides a large volume for accepting any ISLOCA pressure produced small leak flow. The inventory loss from the RCPB resulting from a small leak ISLOCA condition is replaced by the normal feedwater control system.

Therefore, the current design basis is appropriate and does not need revision relative to ISLOCA effects.

(5) HCW Receiving Tank - Vented to atmosphere, and the first closed valve is at least 28.8 atg (410 psig) and one of the dual tank's inlet valves is locked open.

The availability of two HCW tanks overflowing to the radwaste HCW sump provides a large volume for accepting any ISLOCA pressure produced small l leak flow. The inventory loss from the RCPB resulting from a small leak ISLOCA condition is replaced by the normal feedwater control system.

Therefore, the current design basis is appropriate and does not need revision relative to ISLOCA effects.

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(6) FPC Skimmer Surge Tank - The Fuel Pool Cooling Cleanup System's -

skimmer surge tank is open to the near atmospheric pressure of the refueling bay. The first closed valve is at least 28.8 atg (410 psig) rated.

The FPC skimmer surge tank is designed to Seismic Category I.

The dual skimmer surge tank volume is easily able to accept the ISLOCA pressure produced small leak flow from the interfacing RHR System. The skimmer surge tanks overflow directly into the large volume fuel pool.

Fuel pool evaporation would normally dissipate the small ISLOCA leak flows; however, if the ISLOCA flow should accumulate in the fuel pool, excess water can be pumped to radwaste by one of the RHR pumps.

Therefore, the current design basis is appropriate and does not need revision relative to ISLOCA effects.

(7) FPC Spent Fuel Storage Pool and Cask Pit - The Fuel Pool Cooling Cleanup System's spent fuel storage pool and cask pit is open to the near atmospheric pressure of the refueling bay. The first closed valve is at least 28.8 atg (410 psig) rated. The FPC spent fuel storage pool and cask pit is designed to Seismic Category I.

The spent fuel storage pool and cask pit volume is easily able to accept the ISLOCA pressure produced small leak flow from the interfacing RHR  !

System. Pool evaporation would normally dissipate the small ISLOCA leak -

I flows; however, if the ISLOCA flow should accumulate in the fuel pool, excess water can be pumped to radwaste by one of the RHR pumps.

Therefore, the current design basis is appropriate and does not need revision relative to ISLOCA effects.

Evaluation Procedure The pressure of each system piping boundary on all of the ABWR P&ID's was reviewed to identify where changes were needed to provide URS protection. Where low pressure piping interfaces with higher pressure piping connected to piping with reactor coolant at reactor pressure, design  !

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Page 7 pressure values were increased to 28.8 atg which is equivalent to 410 psig. ,

(1 at = 1 kg/cm2; arg is gage) The low pressure piping boundaries were upgraded to URS pressures and extend to the last closed valve connected to piping interfacing a low pressure sink, such as the suppression pool, condensate storage tank or other open configuration (identified pool or tank). Some upgraded boundaries were located at normally open valves, but the upgrading would be needed if the nonnormal closed condition occurred. Each interfacing system's piping was reviewed for upgrading.

For some systems, with low pressure piping and normally open valves, the ,

valves were changed to lock open valves to insure an open piping pathway  :

from the last URS boundary to the tank or low pressure sink.

Typical systems for this upgrade include the:

1. Radwaste LCW and HCW receiving tank piping, i
2. Fuel Pool Cooling System's RHR interface piping connected to the skimmer surge tanks,
3. Condensate Storage System's tank locked open supply valves,
4. Makeup Water Condensate and Makeup Water Purified Systems with locked open valves and pump bypass piping to the Condensate Storage Tank.

All test, vent and drain piping was upgraded where it interfaces with the piping upgraded to URS pressure. Similarly, all instrument and relief valve connecting piping was upgraded. The enclosed P& ids (referencing ABWR SSAR figures) were marked with the new pressure boundary values ,

identified with " clouds" and heavy piping lines to show the upgraded l piping, equipment and instruments. l l

Systems Evaluated The following twelve systems, interfacing directly or indirectly with the l RCPB, were evaluated.

SSAR l Figure No.

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! 1. Residual Heat Removal (RHR) System 5.4-10 l

2. High Pressure Core Flooder (HPCF) System 6.3-7 l
3. Reactor Core Isolation Cooling (RCIC) System 5.4  !
4. Control Rod Drive (CRD) System 4.6-8  :
5. Standby Liquid Control (SLC) System 9.3-1  ;
6. Reactor Water Cleanup (CUW) System 5.4 l 7. Fuel Pool Cooling Cleanup (FPC) System 9.1-1 i l 8. Nuclear Boiler (NB) System 5.1-3
9. Reactor Recirculation (RRS) System .5.4-4 l
10. Makeup Water (Condensate) (MUWC) System, 9.2-4
11. Makeup Water (Purified) (MUWP) System. 9.2-5 .i l 12. Radwaste System 11.2-2 J l

(LCW Receiving Tank, HCW Receiving Tank).

Appendix A contains a system-by-system evaluation of potential reactor ~

l pressure application to piping and components, discussing the URS boundary and listing the upgraded components. For some systems, certain l s

regions of piping and components not upgraded are also listed. l l  !

Pinine Desien Pressure for URS Compliance  ;

l Guidelines for URS compliance were established by Reference 2, which  !

concluded that for the ABWR that: l

1. The design pressure for the low-pressure piping systems that l l interface with the RCPB pressure boundary should be equal' to ,

l 0.4 times the normal operating RCPB pressure of 1025 psig (i.e., j

j. 410 psig), and  !

l 2. The minimum wall thickness of the low-pressure piping should be )

no less than that of a standard weight pipe. ]

Apolicability of URS Non-oiping Components Reference 2 also provided the NRC Staff's position - that:

1. The- remaining components in the low-pressure systems should also be designed to a design pressure of 0.4 times the normal-i

Page 9 operating reactor pressure (i.e., 410 psig). This is accomplished in the SSAR by the revised boundary symbols of the P& ids to the 28.8 atg design pressure, which includes all the piping and components associated with the boundary symbols.

2. A Class 300 valve is adequate for ensuring the pressure of the low-pressure piping system under full reactor pressure.

Results The results of this work are shown by the markups of the enclosed P& ids, which are SSAR figures. The affected sheets are listed below.

System SSAR Affected Sheet Ficure No. Nos

1. Residual Heat Removal (RHR) 5.4-10 1,2,3,4,6,7 System
2. High Pressure Core Flooder 6.3-7 1, 2 (HPCF) System
3. Reactor Core Isolation Cooling 5.4-8 1, 3 (RCIC) System
4. Control Rod Drive (CRD) 4.6-8 1, 3 System j
5. Standby Liquid Control (SLC) 9.3-1 1 i System
6. Reactor Water Cleanup (CUW) 5.4-12 1, 3 System
7. Fuel Pool Cooling and Cleanup 9.1-1 1, 2 (FPC) System
8. Nuclear Boiler (NB) System 5.1-3 1, 5 l

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9. Reactor Recirculation (RRS) 5.4-4 1 System
10. Makeup Water (Condensate) 9.2-4 1 (MUWC) System
11. Makeup Water (Purified) 9.2-5 1, 2, 3 (MUWP) System
12. Radwaste System (LCW l1.2-2 1, 3, 7 Receiving Tank, HCW Receiving Tank)

Also, see Appendix A for more detail.

In addition to the above 12 systems, the following two systems were identified as requiring an ISLOCA evaluation.

Condensate, Feedwater and Condensate Air Extraction (C.FDW,AO)

System Sampling (SAM) System However, these two systems are not in sufficient detail to perform an ISLOCA evaluation. Therefore, an ISLOCA evaluation for these two systems )

is cited in the SSAR as requirements for the COL applicant.

The design pressure of the following two tanks was upgraded as a result of the evaluations performed in Appendix A.

SLC test tank RCIC turbine barometric condenser tank Additional Operational Considerations J

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i The periodic surveillance testing of the ECCS injection valves that interface l with the reactor coolant system might lead to ISLOCA conditions if their l associated testable check valve was stuck open. To avoid this occurrence, j the RHR, HPCF, and RCIC motor operated injection valves will only be  ;

tested during low pressure shutdown operation. This practice follows from the guidance given by Reference 3, page 8, paragraph 7.

Although the following is not a new design feature, the RHR shutdown cooling suction line containment isolation valves are also only tested during shutdown operation. These valves are interlocked against opening for reactor pressure greater than the shutdown cooling setpoint approximately 9.49 kg/cm2 gage (135 psig).  ;

Summary Based on the NRC staff's new guidance cited in References 1 through 4, the ABWR is in full compliance. For ISLOCA considerations, a design pressure of 28.8 atg or (410 psig) and pipe having a minimum wall thickness equal to standard grade has been provided as an adequate margin with respect to the full reactor operating pressure of 72.1 arg (1025 psig) by applying the guidance recommended by Reference 2. This design pressure was applied to the low pressure piping at their boundary symbols on the P& ids, and therefore, impose the requirement on the associated piping, valves, pumps, tanks, instrumentation and all other equipment shown between boundary symbols. A note was added to each URS upgraded P&lD requiring pipe to have a minimum wall thickness equal to standard grade. Upgrading revisions were made to 12 systems.

References

1. Dino Scaletti, NRC, to Patrick Marriott, GE, " Identification of New i Issues for the General Electric Company Advanced Boiling Water Reactor Review," September 6,1991

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2. Chester Poslusny, NRC, to Patrick Marriott, GE, " Preliminary Evaluation of the Resolution of the Intersystem Loss-of-Coolant Accident (ISLOCA) Issue for the Advanced Boiling Water Reactor (ABWR) - Design Pressure for Low-Pressure Systems " December j 2, 1992, Docket No.52-001
3. James M. Taylor, NRC, to The Commissioners, SECY-90-016

" Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements," Jan. 12, 1990

4. James M. Taylor, NRC, to The Commissioners, SECY-93-087

" Policy, Technical, and Licensing Issues Pertaining to ,

Evolutionary and Advanced Light-Water Reactor (ALWR)

Designs," April 2,1993

5. Jack Fox, GE, to Chet Posiusny, NRC, " Proposed Resolution of ISLOCA Issue for ABWR," October 8,1992 ,

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Annendix A System Evaluation General Comments About the Apnendix This Appendix discusses each of the systems evaluated in detail, presented in the order listed in the report, and following a repetitive outline format.

The first section " Upgrade Description," describes the changes made to the system and the reasons for placement of the URS boundary.

The second section, " Downstream Interfaces," discusses the systems that '

interface with the subject system, that could potentially be pressurized by reactor pressure passed through (downstream) the subject system. Each downstream system is dispositioned as being either not applicable for URS upgrading or applicable and the topic of another Appendix A section.

The third section, " Upgraded Components," provides a detailed listing of the components upgraded to the URS design pressure. Also, to indicate some components were not inadvertently overlooked, some components are shown as "No change." The listings are grouped in sections that describe a particular pressure travel path. This grouping may include more than the system of the subject section to detail the path to the tank or sink in which the pressure is dissipated after crossing the last closed I

valve at the URS boundary.

1. Residual Heat Removal System 1.1 Upgrade Description l The RHR System pump suction piping was low pressure and has been upgraded to the URS design pressure. The RHR has two suction sources, i

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Page A- 2.

one from the suppression pool and the other from the RPV as used for  !

shutdown cooling. The suction piping also includes the keep-fill pump and its piping.

The URS boundary was terminated at the last valve before the suppression pool, which is valve El1-F001. The suppression pool is a large structure, designed to 3.16 kg/cm2 gage (45 psig) and impractical to upgrade to the URS design pressure.

The other suction branch to the RPV is not a URS boundary because it interfaces to the high pressure RPV. The only portions of the RHR System that are not upgraded to the URS design pressure is unobstructed piping to the suppression pool.

1.2 Downstream Interfaces Other systems are listed below that interface with RHR and could possibly ,

be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

- Makeup Water (Condensate) System upstream of the injection valve for the purpose of providing a filling and flushing water source. Another interface with MUWC is between the pair of valves to the FPC System. The MUWC System is discussed in Section 10, where it is explained how certain ,

1 MUWC upgrades were made that provide an open path to the CST. The '

MUWC line cannot be pressurized because of the open communication to i 1

the CST, and the CST is vented to atmosphere. There is no source to '

pressurize the MUWC line because of closed valves in the RHR System's l URS region that limit any flow to a small leak.

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- High Conductivity Waste (Radwaste) for drainage located up stream of the pump suction. HCW upgrades are discussed in the Radwaste System, Section 12.

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- Low Conductivity Waste, (Radwaste) at the end of a branch off of the loop B mainline down stream of the RHR heat exchanger. The LCW upgrades are discussed in the Radwaste System, Section 12.

- Sampling System at the outlet of the RHR heat exchanger. The Sampling System's design pressure exceeds the URS design pressure l without upgrade.

- Fuel Pool Cooling and Cleanup System on an RHR System discharge branch. FPC System upgrades are discussed in Section 7.

l - Flammability Control System branches off the main discharge line downstream of the branch that returns to the suppression pool. The FCS design pressure exceeds the URS design pressure without upgrade. >

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- The Fire Protection System and the fire truck connection provide .

! water for the Alternating Current (AC) Independent Water Addition piping I

of RHR loop C upstream of the RPV injection, wetwell spray line, and drywell spray line. The Fire Protection System piping is designed for 14 atg and is protected from over pressure by two locked closed block and ,

bleed valves, RHR-F101 and RHR-F102, and a drain pipe between these l valves vented to the HCW sump in the Reactor Building. This design very effectively prevents reactor pressure from reaching the Fire Protection System. No upgrade to URS is practical or appropriate for the extensive j l

piping of the Fire Protection System since the system function is not related to ISLOCA nor is its interconnection a normal plant operational pathway.

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Page A - 4 i 1.3 Upgraded Components A detailed listing of the components upgraded for the RHR System follows, including identification of those interfacing system components not requiring upgrade.

2P, l RESIDUALHEATREMOVALSYSTEM, Sheets 1 through 7. (atg - Kg/cm ssp): Figure 5.4-10,CEDrawing103E1797Rev.

P RHR Subsystem A suction piping from the suppression pool. I Reference Components Press./ Temp./Desi5n/ Seismic Class Remarks  :

Sheet 3 RHR Pump C001A 35 atg, 182 C,3B.As No change  ;

450A-RHR-002 Pipe 28.8 atg, 182 C,3B,As Was 14 atg .

20A-RHR-701 Pipe. 28.8 atg, 182 C,3B,As Was 14 atg f 20A-RHR-F701A Valve 28.8 atg, 182 C,3B,As Was 14 atg  ;

20A-RHR-PX002A Press.Pt.28.8 atg, 182 C,3B.As Was 14 atg l 450A-RHR-D002A Temp.Str. 28.8 atg,. 182 C,3B,As Was 14 atg f 20A-RHR-700 Pipe- 28.8 atg, 182 C,3B.As Was 14 atg 20A-RHR-F700A Valve 28.8 atg, 182 C,3B,As Was 14 atg ,

20A-RHR-PI001A Press.I 28.8 atg, 182 C,3B.As Was 14 atg 50A-RHR-018 Pipe 28.8 atg, 182 C,3B,As Was 14 atg i 50A-RHR-F026A Valve 28.8 atg, 182 C,3B,As Urs 14 atig r 450A-RHR-F001A MO Valve 28.8 atg, 182 C,3B,As Was 14 atg l Sheet 2 450A-RHR-001 Pipe 3.16atg, 104 C,3B.As No unange  !

450A-RHR-D001A Suct.Str. 3.16atg, 104 C,3B,As No change

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RHR Subsystem A suction piping from the reactor presssure vessel.

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Reference Components Press./ Temp./ Design / Seismic Class Remarks .

Sheet 3 350A-RHP.-011 Pipe 28.8 atg, 182 C,3B,As Was 14 atg  !

350A-RHR-F012A MO Valve 28.8 atg,- 182 C,3B,As Was 14 atg '

25A-RHR-032 Pipe 28.8 atg, 182 C,3B.As Was 14 atg  !

25A-RHR-F042A Rel. Valve 28.8 atg, 182 C,3B,As Was 14 atg  !

20A-RHR-707 Pipe 28.8 atg, 182 C,3B,As' Was 14 atg i 50A-RHR-F712A Valve 28.8 atg. 182 C,3B,As Was 14 atg  ;

20A-RHR-PT009A Press.T 28.8 atg, 182 C,35,As Was 14 atg  ;

Sheet 2 350A-RHR-011 Pipe 28.8 atg, 182 C,3B,As Was 14 atg f

! ** 100A-RHR-031 Pipe 28.8 atg, 182 C,3B,As Was 14 atg i

  • To LCW funnel drain to LCW Sump.
    • To MUW(Concensate) Sytem interface.

- - , . . . - - , ,. , ,. - . _ - . . _ , m -. , ,,-, . . _ , - . . - . _ - _ ,

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RHR Subsystem A discharge fill pump suction piping from the suppression pool. i Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 40A-RHR-C002A Pump 28.8 arg, 182 C,3B.As Was 14 atg 40A-RHR-015 Pipe 28.8 atg, 182 C,3B.As Was 14 atg l 40A-RHR-F022A Valve 28.8 arg, 182 C,3B.As Was 14 atg  ;

40A-RHR-D008A Temp.Str. 28.8 atg, 182 C,3B,As Was 14 atg i 20A-RHR-708 Pipe 28.8 atg. 182 C,3B.As Was 14 atg l 20A-RHR-F713A Valve 28.8 atg. 182 C,3B,As Was 14 atg  !

20A-RHR-PX010APress.Pt. 28.8 atg. 182 C,3B,As Was 14 atg i 25A-RHR-017 Pipe 28.8 arg, 182 C,3B,As Was 14 atg 25A-RHR-F025A Valve 28.8 atg, 182 C,3B,As Was 14 atg l 25A-RHR-D009A RO 28.8 atg, 182 C,3B,As Was 14 atg-  ;

RER Subsystem A discharge from relief valves and test line valve directly to the suppression pool without restriction. j Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 250A-RHR-008 Pipe 3.16 atg, 104 C,3B.As No change  !

100A-RHR-025 Pipe 3.16 atg, 104 C,3B,As No change l 100A-RHR-014 Pipe 3.16 atg, 104 C,3B,As No change' l 50A-RHR-037 Pipe 3.16 arg, 104 C,3B,As No change  :

50A-RHR-033 Pipe 3.16 atg, 104 C,3B,As No change  !

l 50A-RHR-021 Pipe 3.16 arg, 104 C,3B,As No change ,

Sheet 2 250A-RHR-008 Pipe 3.16 atg, 104 C,3B.As No change  ;

Suppression Pool  ;

l RHR Subsystem A flushing line interface at branch discharging to feedwater.

i Reference Components Press./ Temp./ Design / Seismic Class Remarks

Sheet 3 100A-RHR -F032A Valve 35 atg, 182 C,3B.As No. change i 100A-RHR -026 Pipe 35 atg, 182 C,3B.As No change  !

100A-RHR -F033A Check V. 35 atg, 182 C,3B,As 'No change {

j RHR Subsystem A flushing line interface at suction shutdown branch from RPV.  !

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 100A-MUWC-133 Pipe 14 atg, 66 C,4D,B No change ]

l 1 l- Sheet 3 100A-RHR -F040A Valve 28.8 atg, 182 C,38,As Was 14 atg I

( 100A-RHR -031 - Pipe- 28.8 atg, 182 C.3B,As Was 14 atg i 100A-RHR -F041A Check V. 28.8 atg. 182 C,3B.As Was 14 atg l

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i RER Subsystem B suction piping from the suppression pool.

l Reference Components Press./ Temp./ Design / Seismic Class Remarks i Sheet 4 RHR Pump C001B 35 atg, 182 C,3B,As No Change 450A-RHR-102 Pipe 28.8 atg, 182 C,3B,As Was 14 atg i 20A-RHR-731 Pipe 28.8 atg, 182 C,3B,As Was 14 'atg  !

20A-RHR-F701B Valve 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-PX002B Press.Pt.28.8 atg, 182 C,3B,As Was 14 atg 450A-RHR-D002B Temp.Str. 28.8 arg, 182 Was 14 arg 20A-RHR-730 Pipe 28.8 atg, 182,C,3B,As-C,3B,As Was 14 atg  ;

20A-RHR-F700B Valve 28.8 arg, 182 C,3B.As Was 14 atg 20A-RHR-P1001B Press.I 28.8 arg, 182 C,3B,As Was 14 atg i 50A-RHR-124 Pipe 28.8 atg. 182 C,3B,As Was 14 atg i 50A-RHR-F026B Valve 28.8 atg, 182 C,3B,As Was 14 atg l 450A-RHR-F001B MO Valve 28.8 atg, 182 C,3B,As Was 14 atg {

Sheet 2 450A-RHR-101 Pipe 3.16atg, 104 C,3B,As No change  ?

450A-RHR-D001B Suct.Str. 3.16atg. 104 C,3B,As Zo change j l

RHR Subsystem B suction piping from the reactor presssure vessel. '

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 4 350A-RHR-111 Pipe 28.8 arg, 182 C,3B,As. Was 14 atg  ;

350A-RHR-F012B MO Valve 28.8 atg, 182 C,3B,As Was 14 atg j l 25A-RHR-1.59 Pipe. 28.8 atg, 182,C,38,As Was 14 atg  ;

l 25A-RHR-F042B Rel. Valve 28.8 arg, 182 C,3B,As Was 14 atg l 50A-RHR-140 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-737 Pipe 28.8 atg. 182 C,3B,As Was 14 atg l 20A-RHR-F712B Valve 28.3 atg, 182 C,3B,As Was 14 atg l 20A-RHR-PT009B Press.T 28.8 atg, 182 C,3B As Was 14 atg i Sheet 2 350A-RHR-111 Pipe 28.8 atg, 182 c,3B,As Was 14 at5 l

    • 300A RHR-114 28.8 arg, 182 C,3B,As Pipe Was 14 atg
  • =** 100A-RHR F041B Check V. 28.8 arg, 182 C,3B,As Was 14 atg  !
  • To LCW funnel drain to LCW Sump. ** To FPC System interface, j
      • To MUW(Concensate) Sytem interface.  !

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j 1.3 continued i RHR Subsystem 8 discharge fill pump suction piping from the suppression pool. j Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 4 40A-RHR-C002B Pipe 28.8 atg, 182 C,3B.As Was 14 atg i 40A-RHR-121 Pipe 28.8 arg, 182 C,3B As Was 14 atg 40A-RHR-F022B Valve 28.8 arg, 182 C,3B.As Was 14 atg 40A-RHR-D008B Temp.Str. 28.8 atg, 182 C,3B,As Was 14 atg '

20A-RHR-738 Pipe 28.8 atg, 182 C,3B As Was 14 arg l 20A-RHR-F713B Valve 28.8 atg. 182 C,3B.As Was 14 atg i 20A-RHR-PX010BPress.Pt. 28.8 atg. 182 C,38,As Was 14 atg 25A-RHR-123 Pipe 28.8 atg, 182 C,3B.As Was 14 atg .  ;

25A-RHR-F0258 Valve 28.8 atg,- 182 C,3B,As Was 14 atg i 25A-RER-D009B RO 28.8 atg. 18? C,3B.As Was 14 atg ,j RHR Subsystem E flushing line interface at branch discharging to RPV. -l i

Reference Components Press./ Temp./ Design / Seismic Class Remarks .j Sheet 1 100A-MUWC-137 Pipe 14 atg, 66 C,4D,B. No change j Sheet 5 100A-RHR -F032B Valve 35 arg, 182 C,3B.As No change  ;

100A-RHR -132 Pipe 35 arg, 182 C,3B,As No change '

100A-RHR -F0338 Check V. 35 arg, 182 C.3B,As No change j i

RHR Subsystem B flushing line interface at suction of shutdown branch from RPV. l l Reference Components Press./ Temp./ Design / Seismic Class Remarks

Sheet 1 100A-MUWC-136 Pipe 14 atg, 66 C,4D,B No change ,

Sheet 2 100A-RHR -F040B Valve 28.8 atg, 182 C,3B.As Was 14 atg l l 100A-RHR -138 Pipe 28.8 atg. 182 C,3B,As Was 14 atg {i l 100A-RHR -F041B Check V. 28.8 atg, 182 C,3B.As Was 14 atg RHR Subsystem C suction piping from the suppression pool. j Reference Components Press./ Temp./ Design / Seismic Class Remarks  !

Sheet 6 RHR Pump C001C 35 arg, 182 C,3B,As No change 450A-RHR-202 Pipe 28.8 atg, 182 C,3B.As Was 14 atg )

20A-RHR-761 Pipe 28.8 atg, 182 C,3B.As Was 14 atg l' 20A-RER-F701C Valve 28.8 atg. 182 C,3B,As Was 14 atg 20A-RHR-PX002C Press.Pt. 28.8 arg, 182 C,3B As Was 14 atg 450A-RHR-D002C Temp.Str.-28.8 atg, 182 C,3B,As Was 14 'atg 20A-RHR-760 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-F700C Valve 28.8 atg. 182'C,3B,As Was 14 atg 20A-RHR-PI001C Press.1 28.8 atg, 182 C,3B.As .Was'14 atg 50A-RHR-225 Pipe 28.8 atg, 182 C,3B.As Was 14 atg 50A-RHR-F026C Valve 28.8 arg, 182 C,3B,As Was-14 atg 450A-RHR-F001C MO Valve 28.8 atg. 182 C,3B.As Was 14 atg Sheet 2- 450A-RHR-201 Pipe . 3.16atg, 104 C,3B,As .No change 450A-RHR-D001C Suct.Str. 3.16atg. 104 C,38,As No change l

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Page A - 8 1.3 continued RHR Subsystem B discharge from relief valves and test line valve directly to the suppression pool without restriction.

Reference Components Press./ Temp./ Design / Seismic Class Remarks ,

Sheet 4 250A-RHR-109 Pipe 3.16 arg, 104 C,35,As No change l 100A-RHR-131 Pipe 3.16 atg, 104 C,3B,As No change .

100A-RHR-120 Pipe 3.16 arg, 104 C,3B,As No change j 50A-RHR-145 Pipe 3.16 atg, 104 C,3B,As No change 50A-RHR-140 Pipe 3.16 ate, 104 C,3B As No change 50A-RHR-127 Pipe 3.16 atg, 104 C,3B,As No change l Sheet 2 250A-RHR-109 Pipe 3.16 atg, 104 C,3B,As No change l Suppression Pool i RHR Subsytem B interface with Radwaste System. '

l Reference Components Press./ Temp./ Design / Seismic Class Remarks  !

Sheet 4 150A-RHR-129 Pipe 35 atg, 182 C,3B.As No change j l 150A-LCW-F006 Valve 28.8 arg, 66 C,4D,B Was 10 atg '

150A-LCW-CS Pipe 10 - atg, 66 C,4D,B No change l 200A-LCW-CS Pipe 10 arg, '66 C,4D B No change i 200A-LCW-CS Valve ID 10 atg, 66 C,4D,B No change '

l 200A-LCW-CS AO Valve 10 atg, 66 C,4D,B No change

  • LCW Collector Tank A 0 atg, 66 C,4D,B No change _

200A-LCW-CS Valve ID 10 atg, 66 C,4D,B No change  :

200A-LCW-CS A0 Valve 10 atg, 66 C,4D,B No change  !

  • LCW Collector Tank B 0 arg, 66 C,4D,B No change '
  • Each LCW collector tank is served by the HVAC tank vent system exhausting tank air through filter to RW Stack.

RHR Subsystem C suction piping from the reactor presssure vessel.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 6 350A-RHR-212 Pipe 28.8 arg, 182 C,3B,As Was 14 atg 350A-RHR-F012C MO Valve 28.8 arg, 182 C,3B As Was 14 atg  !

25A-RHR-240 Pipe 28.8 atg, 182,C,3B,As Was 14 ats  ;

25A-RHR-F042C Rel. Valve 28.8 atg, 182 C,3B,As - Was 14 atg  !

50A-RHR-241 Pipe 28.P arg, 182 C,3B,As Was 14 atg 20A-RHR-767 Pipe 28.8 atg, 182 C,3B,As Was 14 arg  ;

50A-RHR-F712C Valve 28.8 atg, 182 C,3B.As Was 14 atg j 20A-RER-PT009C Press.T 28.8 atg, 182,C,3B.As Was 14 atg  ;

Sheet 2 350A-RHR-212 Pipe 28.8 atg, 182 C,3B,As Was 14 atg i

-25A-RHR-238 Pipe 28.8 atg, 162 C,3B,As- Was 14 atg  !

  • To LCW funnel drain to LCW Sump. ** To FPC System interface. .l
      • To MUW(Concensate) Sytem interface. l I

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I Page A - T j 1 3 continued '

i RER Subsystem C discharge fill pump suction piping from the suppression pool. j Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 6 40A-RHR-C002C Pump 28.8 atg, 182 C,3B,As Was 14 atg l 40A-RHR-222 Pipe 28.8 atg, 182 C,3B.As Was 14 atg l 40A-RHR-F022C Valve 28.8 atg, 182 C,3B.As Was 14 atg l 40A-RHR-D008C Temp.Str. 28.8 arg, 182 C,3B As Was 14 atg i 20A-RHR-768 Pipe 28.8 atg, 182 C,3B.As Was 14 atg 20A-RHR-F713C Valve 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-PX010C Press.Pt. 28.8 atg, 182 C,3B,As Was 14 atg 25A-RHR-224 Pipe 28.8 atg. 182 C,3B,As Was 14 atg  !

25A-RHR-F025C Valve 28.8 atg. 182 C,3B,As Was 14 atg 25A-RHR-D009C RO 28.8 arg, 182 C,3B,As Was 14 atg RHR Subsystem C discharge from relief. valves and test line valve direct to the f suppression pool without restriction.  ;

I l Reference Components Press./ Temp./Desi p/ Seismic Class Remarks i

Sheet 3 250A-RHR-209 Pipe 3.16 atg, 104 C,3B,As- No change l 100A-RHR-232 Pipe 3.16 atg, 104 C,3B.As No change 100A-RHR-221 Pipe 3.16 atg, 104 C,3B As No change' i

, 50A-RHR-246 Pipe 3.16 arg, 104 C,3B,As No change  !

! 50A-RHR-241 Pipe 3.16 atg, 104 C,3B,As No change l 50A-RHR-228 Pipe 3.16 atg, 104 C,3B,As No change  !

! Sheet 2 250A-RHR-209 Pipe 3.16 atg, 104 C,3B,As No change'  !

Suppression Pool l

RER Subsystem C flushing line interface at branch discharge to RPV. l l

Reference Components Press./ Temp./ Design / Seismic Class Remarks i Sheet 1 100A-MWC-140 Pipe 14 arg, 66 C,4D B -No change  !

100A-RHR -F032C Valve 35 arg, 182 C,3B,As No change 100A-RHR -233 Pipe 35 atg, 182 C,3B,As No change  !

100A-RHR -F033C Check V. 35 arg, 182 C,3B,As No change RHR Subsystem C flushing line interface at suction of shutdown branch from RPV. l Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 1 100A-MWC-140 Pipe 14 at5, 66 C,4D,B No change i 100A-RHR -F040C Valve 28.8 atg, 182 C,3B.As ~ Was 14 atg l 100A-RHR -239 Pipe 28.8 arg, 182 C,38,As Was 14 atg l 100A-RHR -F041C Check V. 28.8 atg, 182 C,3B,As Was 14 atg

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Page A - 10 1.3 continued RER Subsystem C outdoor fire truck connection in RER pump discharge pipe to i RPv. i l

Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 7 100A-RHR -F103 Valve 28.8 arg,- 66 C,7E,C Was 16 atg 100A-RHR -F104 Check V. 28.8 atg, 66 C,7E,C Was 16 arg  ;

100A-RHR -249 Pipe 28.8 atg, 66 C,7E,C Was 16 atg i 100A-RHR -247 Pipe 28.8 arg, 66 C,7E C Was 16 atg l 100A-RHR -F100 Check V. 28.8 atg, 66 C,7E,C Vas 16 atg  !

100A-RER -F101 Key Lock V.35 atg, 182 C,3B,As No change' l 100A-RHR -248 Pipe 35 atg. 182 C,38,As No change 20A-RHR -769 Pipe 35 atg. 182 C,3B,As No change 20A-RHR -F790 Globe V. 35 arg, 182 C,3B.As No change 20A-RHR -PI-099 Press I 35 atg, 182 C,3B,As No change 20A-RHR -570 Pipe 35 atg, 182 C,3B,As No change- ,

  • 20A-RHR -F592 Globe V.1D 35' atg, 182 C,35,As No change i 20A-RHR -571 Pipe 35 arg, 182 C,3B,As No change j l
    • 20A-RHR -F591 Clobe V.NC 35 atg, 182 C,3B.As No change  !

100A-RHR -F102 Key Lock V.35 arg, -182 C,3B,As No change  !

20A-RHR -FE-100 Flow El. 35 atg. 182 C,3B,As No change  !

*** 300A-RHR -205 Pipe 35 atg. 182 C,3B.As No change i
  • Funnel drain to LCU sump in Reactor Building.  ;
    • Test valve. . .

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      • Injection pipe to RPV at outboard isolation valve M0 F-005C. l i

No other low pressure components of the RHR System were identified l for upgrading to the higher design pressure as shown on the marked  !

P & ID's. Interface with the LCU Reactor Building sump which is vented j to atmosphere, is through open funnel drains with low pressure piping ~l to the sump.  !

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Page A- 1 (

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2. High Pressure Core Flooder System 2.1 Upgrade Description The HPCF System pump suction piping was low pressure and has been l

upgraded to the URS design pressure. The HPCF has two suction sources, i the primary source being the condensate storage tank (CST) and the suppression pool as an alternate.

The URS boundary was terminated at the last HPCF valve in the pipeline to the CST, E22-F001. Beyond this valve, the pipeline is open to the CST except for three locked open maintenance valves in parallel adjacent to the CST. The pipeline to the CST is a large pipe (20 inch) providing a common supply to the HPCF, RCIC, and SPCU System. Because of the open communication to the CST, and the CST is vented to atmosphere, this line' cannot be pressurized. The CST is a large structure, impractical to upgrade to the URS design pressure.

The URS boundary was terminated at the last valve before the suppression pool, which is valve E22-F006 and is normally closed. The suppression pool is a large structure, impractical to upgrade to the URS design pressure.

The only portions of the HPCF System that are not upgraded to the URS design pressure is unobstructed piping to the suppression pool.

2.2 Downstream Interfaces Other systems are listed below that interface with HPCF and could possibly be exposed to reactor pressure. A description of the interface location and ,

a statement of its applicability to ISLOCA is given. l l

- Makeup Water (Condensate) System upstream of the injection valve for the purpose of providing the piping keep-fill water source and a filling and flushing water source. The MUWC System is discussed in Section 10, where it is explained how certain MUWC changes were made that provide  !

an open path to the CST. The MUWC line cannot be pressurized because of the open communication to the CST, and the CST is vented to atmosphere. l 1

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Page A- 12.,

There is no source to pressurize the MUWC line because of closed valves in i the HPCF System's URS region that limit any flow to a small leak. i

- High Conductivity Waste System for drainage is located down stream of CST suction check valve. HCW is discussed in Section 12.

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I Page A - l3 2.3 Upgraded Components  :

A detailed listing of the components upgraded for the HPCF System follows, with  :

identification of interfacing system components not requiring upgrade. j i

i HIGH PRESSURE 1P, Sheets 1 and 2.CORE (atg FIDODER

- Kg/cm : SYSTEg), SSAR Figure 6.3-7, GE Drawing 107E6008  ;

HPCF Subsystem B suction piping from the suppression pool. l Reference Components Press./ Temp./DesignfSeismicClass Remarks  ;

Sheet 2 400A-HPCF-006 Pipe 28.8 atg. 100,C,3B,As Was 14 atg i 20A-HPCF-701 Pipe 28.8 atg, 100 C,3B,As Was 14 atg i 20A-HPCF-F701B Valve 28.8 atg. 100 C,3B,As Was 14 atg i 20A-HPCF-PX004B Press. Pt.28.8 atg. 100 C,3B,As Was 14 atg l 20A-HPCF-D001B Temp. Str.28.8 atg, 100 C,3B As Was 14 atg l 400A-HPCF-010 Pipe 28.8 atg, 104 C,3B,As Was 14 atg ,

20A-HPCF 700 Pipe 28.8 atg, 100 C,3B,As Was 14 atg {

20A-HPCF-F700B Valve 28.8 atg, 100 C,3B,As Was 14 atg .

20A-HPCF-PI001B Press.Ind.28.8 atg, 100 C,3B,As Was 14 atg l 20A-HPCF-PT002B Press.Trn.28.8 atg,. 100 C,3B,As Was 14 atg i 20A-HPCF-PT003B Press.Trn.28.8 atg, 100 C,3B,As Was 14 atg  !

25A-HPCF-023 Pipe 28.8 atg,- 100 C,3B,As Was 14 atg i 25A-HPCF-F020B Relief V. 28.8 atg, 100 C,3B,As Was 14 ,atg l 400A-HPCF-F007B Check V. 28.8 atg, 100 C,3B,As Was 14 atg j 20A-HPCF-025 Pipe 28.8 atg, 100 C,3B As Was 14 atg  ;

20A-HPCF-F022B T. Valve & cap 28.8 atg, 100 C,3B,As Was 14 atg i 400A-HPCF-F006B MO. Valve 28.8 atg, 104 C,3B,As' Was 14 atg 400A-HPCF-009 Pipe 3.16atg. 104 C,3B,As No change-400A-HPCF-D003B Suction Str.3.16atg, 104 C,38,As No change ,

Suppression Pool l HPCF Subsystem B suction piping from the Condensate Storage Tank. l Reference Components Press./ Temp./DesignfSeismicClass Remarks 400A-HPCF-006 Pipe 28.8 atg, 100 C,3B,As Was 14 atg  :

50A-HPCF-018 Pipe 28.8 atg, 100 C,3B,As -Was 14 atg f 50A-HPCF-F012B Valve 28.8 arg, 100 C,3B,As Was 14 atg l 50A-HPCF-F011B Valve 28.8 atg. 100 C,3B,As .W as 14 atg i 50A-HPCF-017 Pipe 28.8 atg. 100 C,3B.As' Was 14 atg l 50A-HPCF-F002B Check V. 28.8 arg, 100 C,3B,As Was 14 atg l 400A-HPCF-F001B MO. Valve 28.8 atg, 100 C,3B,As Was 14 atg l 400A-HPCF-005 SS Pipe 14 atg, 66 C,B(S1,S2) No change i 500A-HPCF-004 SS Pipe 14 atg, 66 C,B(S1,S2)' No change i 400A-HPCF-105 SS Pipe 14 atg, 66 C,B(S1,S2) No change 200A-HPCF-015 SS Pipe 14 atg, 66 C,B(S1,S2) No change 200A-HPCF-016 SS Pipe 14 atg, 66 C,B(S1,S2) No change l

  • Connects to lock open valves at condensate storage tank vented to atmosphere. t I

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Page A - (O

! 2.3 continued HPCF Subsystem B test and minimum flow piping to the suppression pool.

Reference Components Press./ Temp./DesignfSeismicClass Remarks Sheet 2 80A-HPCF-014 Pipe 3.16 atg, 104,C,3B.As No change 200A-HPCF-012 Pipe 3.16 atg, 104 C,3B As No change 50A-HPCF-024 Pipe 3.16 atg, 104,C,3B,As No change 250A-RHR- 109 Pipe 3.16 atg, 104 C,3B,As No change Suppression Pool HPCF Subsystem B keep fill line interface.

l Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 20A-MUWC-135 Pipe 14 atg, 66 C,4D,B No change 25A-HPCF-F013B Valve 110 arg, 100 C,3B.As No change 25A-HPCF-D006B R0 110 atg, 100 C,3B,As No change 50A-HPCF-019 Pipe 110 atg. 100 C,3B,As No change 50A-HPCF-020 Pipe 110 atg, 100 C,3B,As No change 50A-HPCF-F016B valve 110 atg, 100 C,3B,As No change HPCF Subsystem C suction piping from the suppression pool and condensate storage tank.

Reference Components Press./ Temp./DesignfSeismicClass Remarks Sheet 2 400A-HPCF-106 Pipe 28.8 atg, 100 C,3B.As Was 14 atg 20A-HPCF-712 Pipe 28.8 atg, 100 C,3B.As Was 14 atg 20A-HPCF-F701C Valve 28.8 atg, 100 C,3B.As Was 14 atg I 20A-HPCF-P004C Press. Pt.28.8 atg, 100 C,3B,As Was 14 atg 20A-HPCF-D001C Temp. Str.28.8 atg, 100 C,3B,As Was 14 atg 20A-HPCF-711 Pipe 28.8 atg, 100#C,3B,As Was 14 atg 20A-HPCF-F700C Valve 28.8 atg, 100 C,3B.As Was 14 atg 20A-HPCF-PI001C Press.Ind.28.8 atg, 100 C,3B As Was 14 atg 20A-HPCF-PT002C Press.Trn.28.8 atg, 100 C,3B,As Was 14 atg 20A-HPCF-PT003C Press.Trn.28.8 atg, 100 C,3B.As Was 14 atg 400A-HPCF-106 Pipe 28.8 atg, 100 C,3B,As Was 14 atg 50A-HPCF-118 Pipe 28.8 atg, 100 C,3B.As Was 14 atg 50A-HPCF-F012C Valve 28.8 atg, 100 C,3B,As Was 14 atg 50A-HPCF-F011C Valve 28.8 atg, 100 C,3B,As Was 14 atg 50A-HPCF-117 Pipe 28.8 atg, 100 C,3B,As Was 14 atg 50A-HPCF-F002C Check V. 28.8 atg, 100 C,3B,As Was 14 atg 400A-HPCF-F001C MO. Valve 28.8 atg, 100 C,3B,As Was 14 atg 400A-HPCF-110 Pipe 3.16atg, 104 C,3B As No change 25A-HPCF-123 Pipe 28.8 atg, 100 C,3B As Was 14 atg 25A-HPCF-F020C Relief V. 28.8 atg, 100 C,?.B.As Was 14 atg 400A-HPCF-F007C Check V. 28.8 arg, 100 C,3B As Was 14 atg 20A-HPCF-125 Pipe 28.8 arg, 100 C,3B.As Was 14 atg 20A-HPCF-F022C T. Valve & cap 28.8 atg, 100 C,3B.As Was 14 atg 400A-HPCF-F006B MO. Valve 28.8 atg, 104 C,3B,As Was 14 atg 400A-HPCF-109 Pipe 3.16atg, 104 C,3B.As No change 400A-HPCF-D003C Suction Str.3.16atg, 104 C,3B,As No change Suppression Pool l

Page A -}fi 2.3 continued HPCF Subsystem C test and minimum flow piping to the suppression pool.

Reference Components Press./ Temp./DesignfSeismicClass Remarks Sheet 2 80A-HPCF-114 Pipe 3.16 atg, 104 C,3B,As No change 200A-HPCF-112 Pipe 3.16 atg, 104 C,3B As No change 50A-HPCF-124 Pipe 3.16 atg, 104 C,3B,As No change 250A-RHR- 209 Pipe 3.16 arg, 104 C,3B,As No change Suppression Pool HPCF Subsystem C keep fill line interface.

l Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 1 20A-MUWC-138 Pipe 14 atg, 66 C,4D,B No change l Sheet 1 25A-HPCF-F013C Valve 110 atg, 100 C,3B. As No change

! 25A-HPCF-D006C R0 110 atg, 100 C,3B,As No change l 50A-HPCF-119 Pipe 110 arg, 100 C,3B,As No change 50A-HPCF-120 Pipe 110 arg, 100 C,3B,As No change

50A-HPCF-F016C Valve 110 atg, 100 C,3B,As No change i
  • Connects to locked open valves from condendate storage tank which is vented to atmosphere.

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Page A-16 1

3. Reactor Core Isolation Cooling System 3.1 Upgrade Description The RCIC System pump suction piping was low pressure and has been upgraded to the URS design pressure. The RCIC has two suction sources, the primary source being the condensate storage tank (CST) and the  ;

suppression pool as an alternate.

The URS boundary was terminated at the last RCIC valve in the pipeline to l the CST, E51-F001. Beyond this valve, the pipeline is open to the CST  ;

except for three locked open maintenance valves in parallel adjacent to the CST. The pipeline to the CST is a large pipe (20 inch) providing a common supply to the RCIC, HPCF, and SPCU System. Because of the open communication to the CST, and the CST is vented to atmosphere, this line cannot be pressurized. The CST is a large structure, impractical to upgrade to the URS design pressure.

The URS boundary was terminated at the last valve before the suppression pool, which is valve E51-F006 and is normally closed. The suppression pool is a large structure, impractical to upgrade to the URS design pressure.

The only portions of the RCIC System that are not upgraded to the URS design pressure is unobstructed piping to the suppression pool.

3.2 Downstream Interfaces Other systems are listed below that interface with RCIC and could possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

- Makeup Water (Condensate) System upstream of the injection valve for the purpose of providing the piping keep-fill water source and a filling and flushing water source. The MUWC System is discussed in section 10. ,

- High Conductivity Waste System for drainage is located down stream of CST suction check valve. HCW is discussed in section 12.

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Page A-F7

- Reactor Core Isolation Cooling System shares common CST suction.

The CST suction has open communication to the CST, and the CST is vented to atmosphere; this line cannot be pressurized and was not practical to

, upgrade to the URS design pressure.

- Suppression Pool Cleanup System shares common CST suction. The  ;

CST suction has open communication to the CST, and the CST is vented to  !

atmosphere; this line cannot be pressurized and was not practical to  :

upgrade to the URS design pressure.  !

a 1

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.-- -. - - - - - . - - - - - ~ .

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Page A - jh 3 3.3 Upgraded Components i

A detailed listing of the components upgraded for the RCIC System follows, f including identification of those interfacing system components not requiring . ,

upgrade.  !

REACTOR CORE IS01ATION COOLING SYST SSAR Figure 5.4-8 GE Drawing 103E1795 Rev. 2P, Sheets 1 & 3. (atg - Kg/cm )

{

RCIC pump suction piping I Reference Components Press./ Temp./ Design / Seismic Class Remarks  !

Sheet 1 200A-RCIC-001-W Pipe 28.8 atg, 77 C,3B,As Was 14 atg 20A-RCIC-703-W Pipe 28.8 atg, 77 C,3B.As Was 14 atg 20A-RCIC-F701 Valve 28.8 atg, 77 C,3B.As Was 14 atg 20A-RCIC-PX015 P. Test 28.8 atg, 77 C,3B.As Was 14 atg-200A-RCIC-D001 Strainer 28.8 atg, 77 C,3B,As Was 14 atg  !

20A-RCIC-700-W Pipe 28.8 atg, 77 C,3B,As Was 14 atg [

20A-RCIC-F700 Valve 28.8 arg, 77 C,3B,As Was 14 atg i 20A-RCIC-FT001 P.Trans 28.8 atg, 77 C,3B,As Was 14 atg j 20A-RCIC-701-W Pipe 28.8 atg, 77 C,3B As Was 14 atg '

20A-RCIC-702-W Pipe 28.8 atg, 77 C,3B,As Was 14 atg ,

20A-RCIC-PIOO3 P.Ind. 28.8 atg, 77 C,3B,As Was 14 atg i 20A-RCIC-PT002 P.Trans 28.8 atg. 77 C,3B,As Was 14 atg i

50A-RCIC-018-W Pipe 28.8 atg, 77 C,3B,As Was 14 atg ,

50A-RCIC-F017 R. Valve 28.8 atg 104 C,3B,As Was 14 atg l

200A-RCIC-F002 T. Check .28.8 atg, 77 C,3B,As Was 14 atg

  • HPCF Interface Piping 200A-HPCF-015-S, 14 atg, 66 C,B (S1,S2), As (open pathway to Condensate Storage Tank with ID valves).  !
    • Suction Piping from Suppression Pool Interface 200A-RCIC-004-W, 3.16 atg, i 104 C, 3B, As.  !

RCIC discharge from relief valves and test line valve direct to the suppression.

pool without restriction.  !

Reference Components Press./ Temp./ Design / Seismic Class Remarks  ;

Sheet 1 50A-RCIC-009-W Pipe 3.16 atg, 104 C,3B,As No change '

50A-RCIC-019-W Pipe 3.16 arg, 104 C,3B,As No change l 100A-RCIC-007-W Pipe 3.16 atg, 104 C,3B,As No change 250A-RHR- 008 Pipe 3.16 atg, 104 C,3B,As No change Sheet 1 Suppression' Pool I

e

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

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

Page A - l$

3.3 continued ABWR High Pressure Core Flooder System SSAR Figure 6.3-7 CE Drawing 107E6008 Rev. 1P. componets interfacing with RCIC System are not upgraded because this is the open pathway to the condensate storage tank vented to the atmosphere. ]

Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 1 200A-HPCF-015-U Pipe 14 atg, 66 C,B (S1,S2), As No change l 400A-HPCF-105-W Pipe 14 atg, 66 C.B (S1,S2), As No change 500A-HPCF-004-U Pipe 14 atg, 66 C,B (S1,S2), As No change 300A-HPCF-001-W Pipe 14 atg, 66 C,B (S1.S2), As No change  ;

300A-HPCF-002-U Pipe 14 atg, 66 C,B (S1,S2), As No change l 300A-HPCF-003-W Pipe 14 atg, 66 C,B (S1,S2), As No change  :

I i ABWR Makeup Water System (Condensate) SSAR Figure 9.2-4 CE Drawing 107E6014 f Rev. IP. components interfacing with HPCF System are not upgraded due to the  !

open pathway to the condensate storage tank vented to the atmosphere.  ;

Reference Components Press./ Temp./ Design / Seismic CIass Remarks .

Sheet 1 300A-MUWC-F100 Valve 14 atg, 66 C,B (S1,S2), As No change 300A-MUWC-F101 Valve 14 arg, 66 C,B (S1,S2), As No change l l 300A-MUUC-F102 Valve 14 atg, 66 C,B (S1,S2), As No change  !

300A-MUWC-100 Pipe Static Hd, 66 C B (S1,S2), As No change .

300A-MUWC-101 Pipe Static Hd, 66 C B (S1,S2), As- No change i 300A-MUWC-102 Pipe Static Hd, 66 C,B (S1,S2), As No change  ;

l Condensate Storage Tank, 66 C,4D, Non-seismic No change i RCIC turbine condensate piping to the suppression pool i' Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 250A-RCIC-037-S Pipe 28.8 atg, 184 C,3B.As Was 10 atg i 20A-RCIC-720-S Pipe 28.8 atg 184 C,3B,As Was 10 atg  !

l 20A-RCIC-F722 Valve 28.8 atg 184"C,3B,As Was 10 atg 1 20A-RCIC-PIO12 P.Ind. 28.8 atg, 184 C,3B,As Was 10 atg j 350A-RCIC-Cond. Chamber 28.8 atg 184 C,3B As Was 10 atg  !

. 350A-RCIC-038-S Pipe 28.8 atg, 184 C,3B,As Was 10 atg "

l

20A-RCIC F723 Valve 28.8 atg, 184 C,3B.As Was 10 atg i 20A-RCIC-722-S Pipe 28.8 atg 184 C,3B,As Was 10 atg  ;

20A-RCIC-PT013A P.Trans 28.8 atg. 77 C,3B,As Was 14 atg  !

! 20A-RCIC-PT013B P.Trans 28.8 atg, 77 C,3B,As Was 14 atg {

  • Vent via Rupture Disks.  !
    • RCIC Turbine Condensate Piping to the Barometric Condenser. l I

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Page A - 20 j 3.3 continued RCIC turbine condensate piping to the suppression pool (continued)

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 350A-RCIC-F038 Check 28.8 atg, 77 C,3B.As Was 14 atg l 20A-RCIC-053-S Pipe 28.8 arg, 184 C,3B,As Was 10 atg i 20A-RCIC-F053 T. Valve 28.8 arg, 184 C,3B,As Was 10 atg l 350A-RCIC-F039 Valve 28.8 atg, 184 C,3B,As Was 10 atg .

350A-RCIC-039-S Pipe 10 arg, 184 C,3B,As No change j Sheet 1 Suppression Pool  !

l RCIC vacuum tank condensate piping to the suppression pool. l Reference Components Press./ Temp./ Design / Seismic Class Remarks [

Sheet 3 50A-RCIC-Vacuum Pump 28.8 atg, 121 C,4D As Was 7.7 atg l 50A-RCIC-044-S Pipe 28.8 arg, 88 C,4D,As Was 3.16atg )

l 50A-RCIC-067-S Pipe 28.8 atg, 88 C,4D,As Was 3.16atg SOA-RCIC-PCV Valve 28.8 atg, 121 C,4D,As Was 7.7 atg Sheet 3 20A-RCIC-068-S Pipe 28.8 atg, 121 C,4D As Was 10 atg l Sheet 1 50A-RCIC-F046 Check V. 28.8 atg, 104 C,3B.As Was 3.16atg i 20A-RCIC-057-S Pipe 28.8 atg, 104 C,3B,As Was 3.16atg j 20A-RCIC-F059 T. valve 28.8 atg, 104 C,3B.As Was 3.16atg  !

50A-RCIC-F047 MO valve 28.8 atg, 104 C,3B,As Was 3.16atg 50A-RCIC-045-S Pipe 10 atg, 104 C,3B.As No change  ;

Sheet 1 Suppression Pool ,

i RCIC steam drains from trip and throttle valve piping and turbine to condensate chamber. l

\

Reference Components Press./ Temp./ Design / Seismic Class Remarks  !

Sheet 3

Condensate Chamber 28.8 atg, 184 C,3B.As Was 10 atg

  • RCIC Trip and Throttle Valve leakoffs are piped to Condensing Chamber.  ;
    • RCIC Turbine Condensate Drain connects to the Condensing Chamber l l

RCIC turbine valve leakoffs are piped to the barometric condenser Reference Components Press./ Temp./ Design / Seismic Class Remarks ]

Sheet 3

    • 25A-RCIC-059-S Pipe 28.8 atg, 184 C,4D As Was 10 ats l Barometric Condenser 28.8 atg, 184 C,4D, As Was 7.7 atg

)

25A-RCIC-Relief Valve 28.8 arg, 121 C,4D As Was 7.7 atg 25A-RCIC-066-S Pipe 0 atg, 121 C,4D,As No change

  • RCIC Trip and Throttle Valve Stem leakoff is piped to the Barometric j
    • RCIC Turbine Covernor Valve Stem is piped to the to Barometric Condenser. l
      • Barometric Condenser pressure relief and piping.

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t Page A - 2.1 I 3.3 continued j RCIC pump cooling water piping for pump and turbine lube oil coolers j i

Reference Components Press./ Temp./ Design / Seismic Class Remarks i Sheet 3 50A-RCIC-011-W Pipe. 28.8 atg, 77 C,3B,As Was 8.8 atg l 50A-RCIC-028-V Pipe 28.8 arg, 77 C,38,As Was 8.8 atg l 50A-RCIC-F030 Relief V.28.8 atg, 77 C,3B.As Was 8.8 atg j 50A-RCIC-029-W Pipe 28.8 atg. 77 C,3B.As Was 8.8 atg l 20A-RCIC-713-W Pipe 28.8 atg, 77 C,3B.As Was 8.8 atg l 20A-RCIC-PX018 Press 28.8 atg, 77 C,3B As Was 8.8 atg j SOA-RCIC-Turb.LO Cooler 28.8 atg, 77 C,3B.As- Was 8.8 atg )

SOA-RCIC-Pump LO Cooler 28.8 atg. 77 C,3B As Was 8.8 atg l 15A-RCIC-TX019 Temp.Pt. 28.8 atg, 77 C,3B,As Was 8.8 atg l 20A-RCIC-714-W Pipe 28.8 atg, 77,C,3B,As .Was 8.8 atg j 20A-RCIC-F714 Valve 28.8 atg, 77 C,3B As Was 8.8 atg 20A-RCIC-PX020 Press.Pt.28.8 atg, 77 C,3B,As Was 8.8 atg l 15A-RCIC-012-W Pipe 28.8 atg, 77 C,3B.As Was 8.8 atg  :

15A-RCIC-013-W Pipe 28.8 atg, 77 C,3B,As Was 8.8 atg  ;

15A-RCIC-014-U Pipe 28.8 atg, 77 C,3B,As Was 8.8 atg i 15A-RCIC-015-W Pipe 28.8 atg, 77 C,38,As Was 8.8 atg .f Sheet 3 Barometric Condenser 28.8 arg, 121 C,4D.As Was 7.7 atg  !

RCIC vacuum tank and condensate pump piped to RCIC pump suction pipe. l i Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 3 RCIC Vacuum Tank 28.8 arg, 77 C,4D,As Was 7.7 atg j RCIC Press. Switch H 28.8 arg, 121 C,4D.As Was 7.7 atg j RCIC Level Switch H 28.8 atg. 121 C,4D,As Was 7.7 atg i RCIC Level Switch L 28.8 atg. 121 C,4D,As Was 7.7 atg l RCIC Cond. Pump 28.8 atg, 88 C,4D,As. . Was 14 atg  !

50A-RCIC-F014- Check 28.8 atg,- 88 C,4D.As Was 14 atg  ;

50A-RCIC-016-W Pipe 28.8 atg, 88 C,4D,As. Was 14 atg l 20A-RCIC-715-W Pipe 28.8 atg, 88 C,4D,As Was 14 atg  ;

20A-RCIC-F715 Valve 28.8 atg,- 88 C,4D.As 'Was 14 atg j

20A-RCIC-PX021 Press.Pt.28.8 atg, 88 C,4D,As . Was 14 atg 50A-RCIC-F015 Valve 28.8 atg, 88 C,3B.As Was 14 atg 50A-RCIC-017-V Pipe 28.8 atg, 88 C,3B.As Was 14 atg 50A-RCIC-030-W Pipe 28.8 atg, 88 C,3B,As Was 14 atg 50A-RCIC-F031 MO Valve 28.8 atg, 88 C,3B,As -Vas 14 atg 50A-RCIC-F032 A0 Valve 28.8 arg, 88 C,3B.As Was 14 atg 20A-RCIC-032-W Pipe 28.8 atg, 88 C,3B.As . Was 14 atg 20A-RCIC-F034 T. Valve 28.8 atg, 88 C,3B,As Was 14'atg

!

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, . . _ . , _ , _ , _ , , , _ . _ . _ . _ . . _ , . . , _ _ . , _ . _ . _ ... .._ , _ .-__ _ _. .,l

Page A - 2 Z, 3.3 continued Sheet 2: Valve gland leak off piping ,

Branch piping from RCIC steam supply isolation valves FO-035,inside primary containment and F0_036 outsids primary containment to VGL Radwaste Treatment System.

Reference Components PressureoRa ting Remarks Sh 2,I-11 25A-RCIC-506-S Pipe 87.9 arg, 302 C,1A,As Reactor Pressure I-7 25A-RCIC-507-S Pipe 87.9 atg, 302 0,1A,As Reactor Pressure Sheet 2: Instrument piping from RCIC steam supply piping to PT-009, PI-010 and level switch LS-011.

Reference Components PressureoRating Remarks ,

Sh 2,H-6 20A-RCIC-716-S Pipe 87.9 arg, 302 C,1A,As Reactor Pressure  !

H-7 20A-RCIC-717-S Pipe 87.9 atg, 302 C,lA,As Reactor Pressure G-5 20A-RCIC-718-S Pipe 87.9 atg, 302 C,lA,As Reactor Pressure i F-5 20A-RCIC-719-S Pipe 87.9 atg, 302 C,lA,As Reactor Pressure No other low pressure components of the RCIC System were identified

, for upgrading to the higher design pressure as shown on the marked P &

ID's. Interface with the LCW Reactor Building sump which is vented to atmosphere, is through open funnel drains with low pressure piping to the sump.

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Page A- 2. 3 l

4 Control Rod Drive System 4.1 Upgrade Description The CRD System interfaces with the reactor in a manner that makes low  ;

pressure piping over pressurization very unlikely. The minimum failure path from the reactor to the low pressure piping has three check valves in series and the second check valve is one half inch in size. This path is from i

the purge flow channels of the CRD, out through the first check valve in the CRD housing, through the purge supply line that has the second half inch  !

check valve, and to the pump discharge check valve. An alternate path  !

through the accumulator charging line has additionally the normally closed scram valve, and this path is less likely for failure, therefore not considered. The path from the pump discharge, back through the pump to its suction, and back through the suction lines to the condensate storage ,

tank or the condensate feedwater source is an open path. The open pump i suction pipeline is a minimum 100 mm (4 inch) diameter except for a 150  !

I mm (6 inch) diameter attachment to the Condensate Storage Tank. The CRD pumps run continuously while the reactor is at operating pressure, '

which prevents reactor pressure from reaching the low pressure piping unless for the very unlikely case when both CRD pumps have failed.

Therefore, an ISLOCA condition from a 0.5 inch diameter source could only occur when three check valves in series fail open at the same time both CRD pumps have failed. The ISLOCA guidelines do not provide credit for

  • this rare condition, so the low pressure piping has been upgraded to the URS design criteria over the entire low pressure piping region of the  :

Control Rod Drive System. The suction path through the Makeup Water '

System (Condensate) to the Condensate Storage Tank from the CRD interface is an open path whose design pressure was not upgraded to URS design criteria. The piping design of the primary suction path through the l

Condensate, Feedwater and Condensate Air Extraction System has not be-en established, but if a check valve is in that path, the design pressure up to and including the check valve will be the URS design pressure.

The normal key assumption to this evaluation, as stated in the Boundary Limits of URS section above, that the valve adjacent to a low pressure sink

Page A- 2A- 1 l

remains closed, means that the pump discharge check valve remains closed ]

as a given. However, this valve is in the high pressure piping, which is unique for the CRD System. According to this accepted line of reasoning, the low pressure piping would not have to be upgraded because it would not experience the high reactor pressure. However, the low pressure piping has been upgraded in response to reference l's guidance that states )

"for all interfacing systems and components which do not meet the full RCS URS criteria, justification is required......, which must include engineering feasibility; not solely a risk benefit analysis." Upgrading the low pressure piping is feasible and was done.

4.2 Downstream Interfaces t

Other systems are listed below that' interface with the CRD System and could possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given, j I

- Reactor Water Cleanup System at the output of the filter units. The RWCU design pressure exceeds the URS design pressure without upgrade.

- Reactor Recirculation System purge water supplied by the CRD System, has a 190 atg design pressure, which exceeds the URS design pressure and needs no upgrade.

- Makeup Water (Condensate) System provides pump suction from ,

and system return to the CST. The MUWC System is discussed in Section 10, where it is explained how certain MUWC upgrades were made that j provide an open path to the CST. This line cannot be pressurized because  !

l of the open communication to the CST, and the CST is vented to atmosphere. There is no source to pressurize the MUWC line because of closed pump discharge check valves in the CRD System's URS region that I limit any flow to a small leak.

- Condensate, Feedwater and Air Extraction System provides pump suction from the turbine building condensate supply. This system is not l part of the SSAR design scope, but it is expected to be an open path to a i

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Page A  ;

i large water source similar to the MUWC System. Because of the open path .

the CFAE System was not upgraded.

- Sampling System at the output of the filter units. The Sampling System's design pressure exceeds the URS design pressure without upgrade.  !

i

- Nuclear Boiler System at a branch off of the CRD purge line provides ,

the water for conducting RPV hydro tests and the 100 atg design pressure  !

exceeds the URS design pressure and needs no upgrade.

4 P

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4 4

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b 4.3 Upgraded Components  :

i A detailed listing of the components upgraded for the CRD System follows, [

including identification of those interfacing system components not requiring "

upgrade.

CONTROLRODDRIVESYSTEM,SSAg)

Sheets 1, 2 & 3. (atg - Kg/cm : Figure 4.6-8,CEDrawing103E1789Rev.IP.

l CRD pump suction piping Condensate. Feedwater and Condensate Air Extraction  !

System or Condensate Storage Tank of the Makeup Water System (Condensate).  !

Reference Components Press./ Temp./ Design / Seismic Class Remarks i See Note 1 100A-CFDWAO-Fxxx Valve 42 atg, 66 C.B,(S1,S2),As No change i Sheet 1 100A-CRD-001-S Pipe 28.8'atg, 20 C,4D B Was 14 atg  !

150A-MUWC-F103 Valve LO 14 atg, 66 C,B,(S1,S2),As No change  !

150A-CRD-002-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg i Sheet 1 Condensate Storage Tank, 66 C,4D, Non-seismic No change  !

50A-MUWC-F103 Valve 14 atg, 66 C,4D B Lock Open 50A-MUWC-103 Pipe Static Hd, 66 C,4D,B No change  !

50A-CRD-033-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg- l 50A-CRD-032-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-500-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg ,

20A-CRD-501-S Pipe '28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-502-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg ,

20A-CRD-503-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg l 25A-CRD-504-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg l i 50A-CRD-505-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg ,

l 50A-CRD-033-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg  !

50A-CRD-F019 Globe V 28.8 arg, 20 C,4D,B Was 14 atg 50A-CRD-032-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg CRD-B001 Elec'Htr 28.8 atg, 20 C,4D,B Was 14 atg  ;

l 25A-CRD-518-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg- l j 25A-CRD-F018 Safe.RV 28.8 atg, 20 C,4D,B Was 14 atg '

l 50A-CRD-F107 Valve 190 atg, 66 C,4C,B No change 100A-CRD-F001A Cate V 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-003-S Pipe- 28.8 atg, 20 C,4D,B Was 14 atg CRD-D001A . Filter 28.8 atg, 20 C,4D,B Was 14 atg l 20A-CRD-500-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg l 20A-CRD-F500A Valve NC 28.8 atg, 20 C,4D.B Was 14 atg i 20A-CRD-501-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 1

20A-CRD-F501A Clobe V 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-004-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-F002A Cate V 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-F001B Gate V 28.8 atg, 20 C,4D B Was 14 atg 100A-CRD-005-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg CRD-D001B Filter ~ 28.8 arg, 20"C,4D,B Was 14 atg 20A-CRD-502-S Pipe 28.8 atg,.20 C,4D.B Was 14 atg <

20A-CRD-F500B. Clobe V 28.8 atg 20 C,4D,B Was 14 atg l 20A-CRD-503-S- Pipe 28.8 atg, 20 C,4D,B Was 14 atg i 20A-CRD-F501B Globe V 28.8 atg, 20 C,4D,B Was 14 atg i 100A-CRD-006-S Pipe 28 8 atg, 20 C,4D,B Was 14'atg I

Page A - 2 J 4.3 continued CRD pump suction piping (continued)

Reference Components Pressure / Temperature / Design / Seismic Class 100A-CRD-F002B Cate V 28.8 atg, 20 C,6D,B Was 14 atg 100A-CRD-007-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-700-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg 20A-CRD-F700 Globe V 28.8 atg, 20 C,4D,B Was 14 atg CRD-DPT001 Diff P T 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-F701 Globe V 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-701-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-F003A Gate V 28.8 arg, 20 C,4D,B Was 14 atg

-100A-CRD-008-S Pipe 28.8 atg, 20 C,4D,B Was.14 atg 25A-CRD-504-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 25A-CRD F004A Safe.RV 28.8 arg, 20 C,4D,B

~

Was 14 atg 20A-CRD-702-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-F702A Globe V 28.8 atg, 20 C,4D,B Was 14 atg CRD-PIO02A Press I 28.8 arg, 20 C,4D,B Was 14 atg.

CRD-PT003A Press T 28.8 atg, 20 C,4D,B Was 14 atg CRD-C001A Pump 35 atg, 66 C,4C,B No change

  • CRD-F502A Globe V 28.8 atg, 20 C,4D,B Vas 14 atg
  • A-CRD-505-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg
  • - CRD-F503A Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F504A Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • A-CRD-506-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg
  • A-CRD-307-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F505A Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F506A Globe V 28.8 atg, 20 C,4D,B Was 14 atg.

100A-CRD-F003B Cate V 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-010-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 25A-CRD-508-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg 25A-CRD-F004B Relief V.28.8 atg, 20 C,4D,B Was 14 arg 20A-CRD-703-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-F702B Globe V 28.8 atg, 20 C,4D,8 Was 14 atg CRD-PIOO2B Press I 28.8 atg, 20 C,4D B Was 14 atg CRD-PT003B Press T 28.8 atg, 20 C,4D,B Was 14 atg CRD-C001B Pump 35 atg, 66 C,4C,B No change

  • A-CRD-509-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F502B Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F5038 Globe V 28.8 atg, 20 C,4D,B Was 14 atg l
  • A-CRD-510-S Pipe 28.8.atg, 20 C,4D,B Was 14 atg
  • CRD-F504B Globe V 28'.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F505B Globe V 28.8 atg 20 C,4D,B Was 14 atg
  • A-CRD-Sil-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg
  • CRD-F506B Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • Size dependent on pump requirements.

Page A - 2 8 4.3 continued CRD interface from pump discharge to the NWC System condensate storage tank Reference Components Press./ Temp./ Design / Seismic Class Remarks 50A-CRD-034-S Pipe 190 atg, 66 C,4C,B No change 50A-CRD-F022 Cate V 190 atg, 66 C,4C,B No change 50A-CRD-035-S Pipe 190 atg, 66 C,4C,B No change 50A-CRD-F023 Gate V 190 atg, 66 C,4C,B No change SOA-MWC-xxx-S Pipe 14 atg, 66 C,4C,B No change 50A-MWC- Fxxx Gate V 14 atg, 66 C,4C,B No change Condensate Storage Tank 66 C,Non-seismic No change CRD interface from pump discharge to the RRS System Reference Components Press./ Temp./ Design / Seismic Class Remarks 20A-CRD-036-S Pipe 190 atg, 66 C,4C,B No change 20A-CRD-F024 Cate V 190 atg, 66 C,4C,B No change 20A-CRD-F025 Cate V 190 atg, 66 C,4C,B No change CRD interface from pump discharge to the CW System Reference Components Press./ Temp./ Design / Seismic Class Remarks 20A-CRD-037-S Pipe 190 atg, 66 C,4C B No change 20A-CRD-F026 Gate V 190 atg, 66 C,4C,B No change 20A-CRD-F027 Cate V 190 arg, 66 C,4C,B No change No other low pressure components of the Control Rod Drive System were identified for upgrading to the higher design pressure as shown on the marked P & ID's. Interface with the LCW Reactor Building sump which is vented to atmosphere, is through open funnel drains with low pressure piping to the sump.

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Page A - 2 9 5.0 Standby Liould control System 5.1 Upgrade Description i The SLC System interfaces with the reactor through the HPCF injection piping inside the drywell. The leakage path includes three 40mm diameter check valves in series with normally closed motor operated valves in addition to the -

positive displacement pumps piped in parallel. A 40mm dimeter test pipe from the pump discharge piping to the test tank has two normally closed valves in series. All of these valves have leakage test features. Short monthly pump ,

operating tests produce demineralized water flow through the test tank.

The 100 mm diameter pump suction piping between the pumps, the storage tank outlet valve, the test tank and the MUWP System interface is upgraded to URS design criteria. The SLC storage tank is vented to atmosphere and serves as the pressure release sink connecting to the outermost pump suction piping valves.

All low pressure instrumentation, pressure relief, drain piping and valving are upgraded to URS design criteria to reduce the level of pressure challenge to these components.  ;

l 5.2 Downstream interfaces.

Other systems are listed below that interface with the SLC System and could possibly be exposed to reactor pressure. A dese.ription of the interface location and a statement of its applicability to ISLOCA is given.

MUUP System 80 mm diameter piping interface occurs at the SLC check valve

  • connected to a branch off the test loop suction pipe. This SLC branch piping consists of a normally closed flushing valve and a normally open 20 mm diameter suction piping pressurizing valve to prevent borated solution migrating to the SLC injection pump suction piping. Refer to Section 11 for upgrade information on the MUUP System.

MUWP System also provides the makeup water to the SLC System storage tank  ;

through block and bleed valves and a piping drain to a portable container to prevent leakage of additional makeup into the SLC storage tank which could dilute the borate solution in the tank.

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5.3 Upgraded Components A detailed listing of the components upgraded for the SLC System follows,-

including identification of those interfacing system components not requiring upgrade.

IP STANDBYLIQUIDCONTR0p)

Sheet 1. (atg - Kg/cm : SYSTEM,SSARFigure9.3-1CEDrawing107E6016Rev.

SLC Injection Pump A suction piping from the SLC storage tank.

Reference Components Press./ Temp./ Design / Seismic Class Remarks SLC-COOlA Pump 110 atg, 66 C,2B,A No Change SLC-F003A Relief V.110 atg, 66 C,2B.A No Change 50A-SLC-F003A Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-F002A Valve LO 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-F001A Valve MO 28.8 atg, 66 C,2B,A Was 14 atg l

  • SLC-A001 Storage Tk, STH atg, 66 C,2B,A No Change SLC Injection Pump B suction piping from the SLC storage tank.

Reference Components Press./ Temp./ Design / Seismic Class Remarks SLC-C001B Pump 110 atg, 66 C,2B,A No Change SLC-F003B Relief V.110 arg, 66 C,2B,A No Change SOA-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-F002B Valve ID 28.8 atg, 66 C,2B.A Was 14 atg 100A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 20A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 20A-SLC-F500 Valve 28.8 atg, 66"C,2B,A Was 14 atg 100A-SLC-F001B Valve MO 28.8 atg, 66 C,2B,A Was 14 atg

  • SLC-A001 Storage TK. STH atg, 66 C,2B,A No Change
  • SLC Storage Tank is vented to atmosphere (STH is static head).

SLC test tank piping.

Reference Components Press./ Temp./ Design / Seismic Class Remarks

    • 40A-SLC-F011 Valve LC 110 atg, 66 C,2B,A Was ATP atg 40A-SLC-SS Pipe 110 atg, 66 C,2B.A Was 14 atg SLC-A002 Test Tank 28.8 atg, 66 C,2B,A Was STH atg 100A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-F012 Valve LC 28.8 atg, 66 C,2B,A Was 14 atg 25A-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg SLC-F026 Relief V. 28.8 atg, 66 C,2B,A Was 14 atg 20A-SLC-SS Pipe 28.8 arg, 66 C,2B.A Was 14 atg 100A-SLC-SS Pipe 28.8 atg, 66*C,2B,A Was 14 atg
    • ATP is atmospheric pressure. ,

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Page A - 31 1 5.3 continued j l

SLC interface with MUWP for makeup and pressurization of suction piping from  ;

tank. (Pressure higher than static head of SLC storage tank.) I Reference Components Press./ Temp./ Design / Seismic Class Remarks 80A-MUWP-F163 Valve LO 14 atg, 66 C,4D.C No change  :

80A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Was 14 atg j SLC-F013 Check V. 28.8 atg, 66 C,2B,C Was 14 atg l 80A-SLC-SS Pipe. 28.8 atg, 66 C,2B.C Was 14 atg l 80A-SLC-F014 Valve LC 28.8 atg, 66 C.2B,A Was 14 atg  ;

80A-SLC-SS Pipe 28.8 atg, 66 C,2B.C Was 14 atg .;

20A-SLC-SS Pipe 28.8 atg, 66 C,2B C Was 14 atg '

20A-SLC-F020 Valve LO 28.8 atg, 66 C,2B,A Was 14 atg  ;

20A-SLC-D002 RO 28.8 atg, 66 C,2B.A Was 14 atg l 20A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Was 14 atg j l

SLC storage tank interface with MUWP for purified makeup water. l I

Reference Components Press./ Temp./ Design / Seismic Class Remarks j 80A-MUWP-F163 Valve LO 14 atg, 66 C,4D.C No change j 80A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Was 14 atg }

SLC-F013 Check V. 28.8 atg, 66 C,2B,C Was 14 atg j 80A-SLC-SS ~ Pipe 28.8 atg, 66,C 2B,C Was 14 atS .!

25A-SLC-SS Pipe 28.8 atg, 66,C,2B,C Was 14 atg ,

25A-SLC-F015 Valve LC 28.8 atg, 66 C 2B,A Was 14 atg  !

20A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Was 14 atg  !

'20A-SLC-F505 Valve NO 28.8 atg, 66 C,2B.A Was 14 atg  !

25A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Was 14 atg {

25A-SLC-F023 Valve LC 28.8 atg, 66 C,2B,A Was 14 atg f 25A-SLC-SS Pipe 8.8 atg, 66 C.2B,C No change  !

  • SLC-A001 Storage.TK. STH atg, 66 C,2B,A No change f i
  • SLC Storage Tank is vented to atmosphere (STH is static head). i P

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- . _. _ . _ ._._ - _ . . ~ _ _

Page A- 3 2-

6. Reactor Water Cleanup System 6.1 Upgrade Description The Reactor Water Cleanup System (CUW) is a high pressure system that is almost totally designed above the URS design pressure. One pipe connecting to radwaste was upgraded. It is the pipe downstream of valve G31-F023 shown at zone E-14 of Figure 5.4-12 , sheet 3. The interface symbol is labeled "LCW Collector Tank."

6.2 Downstream Interfaces A system is listed below that interfaces with CUW and could possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given .

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- Low Conductivity Waste, (Radwaste) connects to a branch of the CUW filter /demineralizer discharge, as described in 6.1 above. There is not a practical reason to upgrade this interface in CUW as discussed in the Radwaste System, Section 12.  ;

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I l 6.3 Upgraded Components A detailed listing of the components upgraded for the CW System follows, including identification of those interfacing system components not requiring upgrade.

REACTORWATERCLEANUPSYSTEM,gSARFigure5.4-12CEDrawing107E5051Rev.2P Sheets 1,2 and 3. (atg - Kg/cm ).

CW System interface with Radwaste System Reference Components Press./ Temp / Design / Seismic Class Remarks 150A-CW- F023 Valve MO 104 atg, 66 C,4C,B No change 150A-CW-31-CS Pipe 28.8 atg, 66 C,4D,C Was 10 atg I

200A-LCW-CS Pipe 10 atg, 66 C,4D,B No change 200A-LCW-CS Valve LO 10 atg, 66 C,4D,B No change 200A-LCW-CS AO Valve 10 atg, 66 C,4D,B No change

  • LCU Collector Tank A 0 atg, 66 C,4D,B No change 200A-LCW-CS Valve LO 10 atg, 66 C,4D,B No change 200A-LCW-CS A0 Valve 10 atg, 66 C,4D,B No change
  • LCW Collector Tank B 0 atg, 66 C,4D,B No change l

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Page A- 34

7. Fuel Pool Cooling Cleanun System 7.1 Upgrade Description The Fuel Pool Cooling Cleanup System interfaces with the RHR System at two locations that could possibly expose the FPC System to reactor pressure. One location is the discharge from the FPC to RHR in the line downstream from the skimmer surge tank; the other location is the RHR return to the FPC in the line to the reactor well. See Figure 9.1-la, upper right and left hand corners respectively.

Upgrading of components and new pipeline with a testable check valve and gate valve were added to the first interface of the discharge from the FPC to RHR. This new line has the gate valve locked open with the check valve's flow direction into the skimmer surge tank and provides an open path into the skimmer surge tank from valve FPC-F031. Valve FPC-F029 has and open path to the skimmer surge tank. This new line and its two i new valves have the FPC normal design pressure of 16 atg because the line  !

is an open path to the skimmer surge tank. All the piping between the FPC valves, FPC-F029 and FPC-F031, and the RHR valves, RHR-F016B and RHR-F016C, was upgraded to the URS design pressure of 28.8 atg.

The second interface, the RHR return to the FPC in the line to the reactor well, was not upgraded because of the continuous open path to the spent fuel storage pool and cask pit. Valves FPC-F093 and FPC-F017 are always l locked open and provide an open path from the RHR valves, RHR-F015B and RHR-F015C, to the spent fuel storage pool and cask pit.

7.2 Downstream Interfaces The Fuel Pool Cooling Cleanup System has nn further downstream system interfaces that could allow reactor pressure from RHR to proceed further than the FPC System.

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Page A - 3 3 7.3 Upgraded Components A detailed listing of the components upgraded for the FPC System follows, including identification of those interfacing system components not requiring upgrade.

FUELPOOLCOOLINGANDCLEANUPSYSTEM,gSARFigure9.1-15,CEDrawing107E6042 Rev.lP., Sheets 1,2 and 3. (atg - Kg/cm ).

FPC System interface with makeup from RHR System or SPCU System.

Reference Components Press./ Temp./ Design / Seismic Class Remarks 250A-RHR-F015C Valve MO 35 atg, 66 C,3B.A(S2)D No change 250A-FPC-SS Pipe 16 atg. 66 C,3B,A(S2)D No change 250A-RHR-F015B Valve MO 35 atg, 66 C,3B,A(S2)D No change 250A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-F094 Check Valve 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change '

20A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 20A-FPC-F506B valve 16 atg, 66 C,3B.A(S2)D No change 250A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 250A-RHR-F022 Valve LO 16 atg, 66 C,3B A(S2)D No change 250A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-F023 Check valve 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-SS Pipe 16 atg 66 C,3B.A(S2)D No change REACTOR WELL No change 250A-FPC-SS Pipe 16 atg, 66 C,3B A(S2)D No change ,

250A-FPC-F093 Valve LO 16 atg, 66 C,3B,A(S2)D No change 80A-SPCU F014 Valve MO 35 atg, 66 C,3B.A(S2)D No change 80A-FPC-SS Pipe 16 atg, 66 C,3B, A(S2)D No change 80A-FPC-F091 Check Valve 16 atg, 66 C,3B,A(S2)D No change 80A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 80A-FPC-D011 R0 16 atg, 66 C,3B,A(S2)D No change 80A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-SS Pipe 16 atg, 66 C,3B A(S2)D No change 250A-FPC-F016 Check Valve 16 atg, 66 C,3B.A(S2)D No change 250A-FPC-F017 Valve ID 16 atg, 66 C,3B,A(S2)D No change 250A-FPC-F018 Check Valve 16 atg, 66 C,3B,A(S2)D No change SPENT FUEL STORACE POOL l l

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Page A - 3lo 7.3 continued FPC System interface with suction of RHR System for cooling.  ?

Re ference Components Press./Terp./Desigg/ Seismic Class Remarks ,

300A-RHR-F016C Valve MO 28.8 atg, 182 C,3B.As Was 14 atg l 300A-FPC-SS Pipe 28.8 atg, 66 C,3B.A(S2)D Was 14 atg '

300A-RHR-F016B valve MO 28.8 atg, 182 C,3B As Was 14 arg l 300A-FPC-SS Pipe 28.8 atg, 66 C,3B,A(S2)D Was 14 atg 300A-FPC-F029 Valve NC 28.8 atg, 66 C,3B,A(S2)D Was 14 atg 300A-FPC-SS Pipe SWH atg, 66 C,3B,A(S2)D No change

  • SPENT FUEL STORAGE POOL 250A-FPC-SS Pipe 28.8 arg, 66 C,3B.A(S2)D Was 14 atg 250A-FPC-F031 Valve NC 28.8 atg, 66 C,3B.A(S2)D Was 14 atg 250A-FPC-SS Pipe 16 atg, 66 C,3B,A(S2)D No change
      • SKlMMER SURCE TANK No change
  • FPC Valve F029 is open only for fuel pool cooling mode B (maximum heat j load operation with RHR System B or C operating in paralell with FPC System).
    • FPC Valve F031 is open only for fuel pool cooling mode B (refueling when Dryer / Separator Pool is drained and pumped to Radwaste LCW collector tank by RHR System B or C).
      • FPC Valve F031 leakage is directed to skimmer surge tank through a lock ,

open valve and a check valve into skimmer surge tank. ,

SWH is static water head. i i

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l Page A - 3'7 J 8.0 Nuclear Boiler System 8.1 Upgrade Description l

The NBS piping and instrumentation are designed for reactor pressure. One low pressure level transmitter and level indicator with the associated piping and ,

two normally closed globe valves are upgraded to URS design criteria. This level instrumentation is used to measure the level in the reactor well during refueling and is selected for the required sensitivity. A relief valve ,

downstream of the two normally closed globe valves discharges to a LCW funnel drain to the Reactor Building LCW sump.

8.2 Downstream Interfales ,

i Other systems are listed below that interface with the NBS and could possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

CRD, RCIC, RPV, RHR, HPCF, CUW, MS, are high pressure interfaces of the I NBS and RW(LCW, HCW, VG) are low pressure interfaces of the NBS. Interfacing '

systems at high pressure have low pressure interfaces addressed in their specific system listings.

8.3 Upgraded Components A detailed listing of the components upgraded for the NBS System follows. [

NUClIARBOILERSYgTEM,SSARFigure5.1-3GEDrawing103E1791Rev.2P. Sheets 1

& 5. (atg - Kg/cm ):

Refueling level transmitter piping Reference Components Press./ Temp./ Design / Seismic Class Remarks 20A-NBS-F708 Relief V 28.8 atg, 20 C,lA As Was 7 atg ,

  • LT-004 must be low pressure rated for level sensitivity during refueling.

Other fluid piping components of the NBS System are rated for reactor pressure, except the main steam drain header interface with the Condensate, Fgedwater and Air Extraction System piping to be designed for at least 28.8 Kg/cm and other l drains including valve gland leakage, LCW and HCW funnel drains to the drywell equipment drain sump.

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Page A - 3 6  !

9.0 Reactor Recirculation System 9.1 Upgrade Description i

Ten Reactor Internal Recirculation Pumps (RIP) are installed around the perimeter of the reactor vessel and operate at reactor pressure.

9.2 Downstream Interfaces Other systems are listed below that interface with the RRS System and could r possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given. .

t MUWP System interfaces with each reactor recirculation pump to provide RIP casing makeup water. Another MUWP System interface exists during refueling or maintenance shutdown to provide water for the RIP shaft inflatable seal subsystem. Pressure upgrades are required for the interfacing components of the

  • MUWP System.

RCW System interfaces with each RRS RIP motor cooling subsystem through a heat exchanger designed for 87.9 atg.and utilizes RCW water for cooling the RIP motors. No upgrade is needed for the RCW System connecting piping designed to j 14 atg.

l CRD System piping connects to ten RIP motor purge subsystems. Control t Rod Drive System SSAR Figure 4.6-8, sheet 1 at C-2, the 20A-CRD-036 pipe and .

20A-CRD-F025 valve interface with the 20A-RRS-003A pipe connecting to the ten R.IP motors. No upgrade is required because the design pressure for both the  ;

CRD and RRS is 190 atg.  !

t RUS Open funnel drain piping connects to the LCW and HCW sumps in the drywell.

MUWP Makeup Water System (Purified) SSAR Figure 9.2-5 GE Drawing 107E5111 Rev. 2P. shows other components interfacing with RRS System. These are not upgraded because they are part of the open pathway to the Condensate Storage Tank which is vented to the atmosphere. Another MUWP System interface is connected to a portable inflatable shaft seal pump and tank only during l refueling or when the reactor is shut down for maintenance.

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Page A - 3 9 9.3 Upgraded Components j A detailed listing of the components upgraded for the RRS System follows, l' including identification of those interfacing system components not requiring upgrade.

REACTOR Sheets 1 & 2.RECIRCULATION (atg - Kg/cm SYSTp):SSAR Figure 5.4-4, GE Drawing 107E5194 Rev. IP, RRS interface with MUWP System for Reactor Internal Pump (RIP) casing makeup  ;

water.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 15A-RRS-502A-K Pipes . 87.9atg,302 C, 4A,As- No change 15A-RRS-F504A-K Valves NC 87.9atg,302 C, 4A,As No change '!

15A-MUWP-189-198 Pipes 28.8atg, 66 C, 4D C Was 14 atg }

50A-MUWP-185 Pipe 28.8atg, 66 C, 4D,C . Was 14 atg i 50A-MUWP-F142 Check Valve 28.8atg,171 C, 3B, As Was 14 atg l 50A MUWP-184 Pipe 28.8atg,171 C, 3B.As Was 14 atg l 50A-MUWP-F141 Valves NC 28.8atg,171 C, 3B.As Was 14 atg 50A-MUWP-183 Pipe 14 atg, 66 C, 4D,C No change l

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80A-MUWP-181 Pipe 14 atg, 66 C, 4D.C No change 80A-MUUP-F140 Valve LO 14 atg, 66 C, 4D,C No change j

125A-MUUP-101 Pipe 14 atg, 66 C, 4D C No change'  !

l 125A-MUUP-F101 Valve LO 14 arg, 66 C, 4D,C No change i l 20A-MUMP-602 Pipe 14 atg, 66 C, 4D C No change l 20A-MUWP-F602 Valve NC 14 atg. 66 C, 4D,C No change j 20A-MUMP-601 Pipe 14 atg, 66 C, 4D.C  ; No change i 20A-MUWP-F601 Valve NC 14 atg, 66 C, 4D,C No change l 20A-MUWP-FQ102 Flow Integr.14 atg, 66 C, 4D,C No change  !

20A-MU'JP- 801 Pipe 14 atg, 66 C, 4D,C' No change 20A-MUWP-F801 Valve NC 14 atg, 66 C, 4D,C No change l 20A-MUWP-800 Pipe 14 atg, 66 C, 4D,C No change .j 20A-MUWP-F800 Valve NC 14 atg, 66 C, 4D,C No change j l 20A-MUMP-PX101 Press. Pt. 14 atg, 66 C, 4D,C No change ]

20A-MUWP-600 Pipe 14 atg, 66 C. 4D,C No change. l 20A MUWP-F600 Valve NC 14 arg, 66 C, 4D,C No change 20A-MUWP-F100 Valve LO 14 atg, 66 C, 4D C No change 125A-MUWP-102 Pipe 14 atg 66 C, 4D,C ' No change 125A-MUWP-F102 Valve NC 14 atg 66 C, 4D,C No change 150A-MUWP-xxx Pipe 14 atg, 66 C, 4D,C No change ISOA-MUWP-xxx Pipe 14 atg, 66 C, 4D.C No change

!. SOA-RRS-Fxxx Check Valve 14 arg, 66 C, 4D,C - No change i Condensate Storage Tank, 66 C, 4D,Non-seismic No change l

i r ~ < v , --r, , - . , . --.+,.,,.n..,-- ,,, . , , - .e, , , , . -..-.--..-,.n.--.,-n - , . . -

t Page A - $hO 10.0 Makeup Water System Condensate 10.1 Upgrade Description The MUWC System has extensive system interfaces throughout the plant for makeup water to fill systems and serve flushing connections. The extent of the piping and the size of the Condensate Storage Tank of the MUWC System makes it l impractical to upgrade. Instead valves are changed to lock open type to create i a clear path from the URS boudary to the Condensate Storage Tank which is l vented to atmosphere.

l 10.2 Downstream Interfaces l HPCF System is a downstream interface of the MUWC System at three outlets of the Condensate Storage Tank. The CRD piping is not upgraded to the URS l design pressure because the maximum static head is 1.62 atg. The first closed

valve of the HPCF System suction piping is upgraded to URS design pressure based on data provided in Section 2.

CRD System 150A suction piping interfaces with Condensate Storage Tank.

Other interfaces include the HPCF System fill line, RHR flushing lines, j CRD makeup and discharge, and MUWP System are not upgraded due to the impractical nature of upgrades for such an extensive piping system with lock open type valves and open piping paths to the vented condesate storage tank.

All MUWC valves between the interfacing system connections and the Condensate Storage Tank are lock open type _ to provide an open pathway to relieve pressure to this tank which is vented to the atmosphere.

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Page A - 4l 10.3 Upgraded Corponents A detailed listing of the components upgraded for the MWC System follows, including identification of those interfacing system components not requiring upgrade.

MAKEUPWATERSYSTEM(CgNDENSATE)SSARFigure9.2-4CEDrawing107E6014Rev. 1P.

Sheets 1. (atg - Kg/cm ):

HPCF Subsystem B keep fill line interface.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1

Reference Components Press./ Temp./Desggn/SeismicClassRemarks Sheet 1

MWC System interface with HPCF System Reference Components Press./ Temp./ Design / Seismic Class Remarks 300A-HPCF-001 SS Pipe 14 atg, 66 C,B(S1,S2) No change 300A-HPCF-002 SS Pipe 14 atg, 66 C,B(S1,S2) No change 300A-HPCF-003 SS Pipe 14 atg, 66 C,B(S1,S2) No change Sheet 1 300A-MWC-F100 Valve LO 14 atg, 66 C,4D,B No change 300A-MWC-F101 Valve LO 14 atg, 66 C,4D,B No change 300A-MWC-F102 Valve LO 14 atg, 66 C,aD,B No change 300A-MWC-100 Pipe Static Hd. 66 C,4D,B No change 300A-MWC- 101 Pipe Static Hd. 66 C,4D B No change 300A-MWC- 102 Pipe Static Hd. 66 C,4D,3 No change RHR Subsystem A flushing line interface at branch discharging to feedwater.

Reference Components Press./ Temp./ Design / Seismic Class Remarks l Sheet 1

  • 100A-MWC- 134 Pipe 14 atg, 66 C,4D,B No change Sheet 3 100A-RHR -F032A Valve 35 atg, 182 C,3B,As No change l 100A-RHR -026 Pipe 35 atg, 182 C,3B,As No change l 100A-RHR -F033A Check V. 35 atg, 182 C,3B,As No change l

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Page A - Q 10.3 continued RHR Subsystem A flushing line interface at suction shutdown branch from RPV.

Reference Coaponents Press./ Temp./ Design / Seismic Class Remarks Sheet 1

  • 100A-MWC- 133 Pipe 14 atg, 66 C,4D,B No change Sheet 3 100A-RHR -F040A Valve 28.8 atg, 182 C,3B,As Was 14 atg 100A-RHR -031 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 100A-RHR -F041A Check V. 28.8 arg, 182 C,3B,As Was 14 atg RHR Subsystem B flushing line interface at branch discharging to feedvater.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1

  • 100A-MWC-137 Pipe 14 atg, 66 C,4D,B No change Sheet 3 100A-RHR -F032B valve 35 atg. 182 C,3B.As No change 100A-RHR -132 Pipe 35 atg, 182 C,3B,As No change 100A-RHR -F033B Check V. 35 atg, 182 C,3B.As No change RHR Subsystem B flushing line interface at suction of shutdown branch from RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1

  • 100A-MWC- 136 Pipe 14 atg, 66 C,4D,B No change 100A-RHR -F040B Valve 28.8 atg, 182 C,3B.As Was 14 atg 100A-RHR -138 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 100A-RHR -F041B Check V. 28.8 atg, 182 C,3B,As Was 14 atg RHR Subsystem C flushing line interface at branch discharge to feedwater.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1

  • 100A-MWC- 140 Pipe 14 atg, 66 C,4D,B No change 100A-RHR -F032C Valve 35 atg, 182 C,3B,As No change 100A-RHR -233 Pipe 35 atg, 182 C,3B As No change 100A-RHR -F033C Check V. 35 atg, 182 C,3B,As No change RHR Subsystem C flushing line interface at suction of shutdown branch from RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1

  • Makeup Water System (Condensate) piping designed with open pathway to Condensate Storage Tank.

Page A . 4 3 l 10.3 continued MUWC System changes and upgrades.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 150A-MWC-F131 Valve LO 14 arg, 66 C,4D,B No change 250A-MWC-F111 Valve LO 14 atg, 66 C,4D,B No change 250A-MWC-F110 Valve LO 14 atg, 66 C,4D,B No change

> ** 250A-MWC- 110 Pipe 14 atg, 66 C,4D,B No change

    • Interface with new MWC System pump minimum flow bypass pipe with check valve and to service valves connecting to Condensate Storage Tank.

MWC System interface with MWP Re ference Components Press./ Temp./ Design / Seismic Class Remarks 150A-WMP-101 SS Pipe 14 atg, 66 C,4D C No change 150A-WMP-Fxxx SS Valve LO 14 atg, 66 C,4D,C No change

! 150A-WMP-Fxxx SS Check V.14 atg, 66 C,4D,C No change l Candensate Storage Tank MWC interface with the CR0 System pump suction piping.

l Reference Components Press./ Temp./ Design / Seismic Class Remarks l 150A-CRD-002-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg Sheet 1 150A-MWC-Fxxx LO Valve 14 atg, 66 C,4D,B Lock Open 150A-MWC-xxx Pipe 14 atg, 66 C,4D,B No change l

150A-MUWC-Fxxx LO Valve 14 atg, 66 C,4D,B Lock Open 150A-MWC-xxx Pipe 14 atg, 66 C,4D B No change i 150A-MUWC-Fxxx LO Valve 14 atg, 66 C,4D,B Lock Open

150A-MWC-xxx Pipe Static Hd, 66 C,4D B No change Condensate Storage Tank, 66 C,4D, Non-seismic No change MWC interface with the CRD System pump discharge piping.

Reference Components Press./ Temp./ Design / Seismic Class Remarks 50A-CRD-034-S Pipe 190 atg, 20 C,4C,B No change 50A-CRD-F021 Valve MO 190 atg, 20 C,4C,B No change 50A-CRD-F022 Valve 190 atg, 20 C,4C,B No change 50A-CRD-035-S Pipe 190 atg, 20 C,4C,B No change i

50A-CRD-F023 Valve 190 atg, 20 C,4C,B No change Sheet 1 50A-MWC- F103 Valve 14 atg. 66 C,4D,B Lock Open SOA-MWC-xxx Pipe Static Hd, 66 C,4D,B No change Condensate Storage Tank, 66 C,4D, Non-seismic No change i

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Page A Zhdb 11.0 Makeup Vater System Purifed 11.1 Upgrade Description The MUWP System is not upgraded due to the extensive nature of the piping distribution, but instead all valves between the interface and the Condensate i Storage Tank are changed to the lock open type. This provides a cicar path for the release of pressure to the Condensate Storage Tank which is vented to atmosphere. The extensive small piping of the MUWP System serving so many plant systems was determined to be impractical to upgrade to URS design I criteria. ,

11.2 Downstream Interfaces t

l other systems are listed below that interface with the MUWP System and could possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

l SLC System makeup seal, the RRS ten RIP casing makeup water connections and shaft inflatable seal capped connections are interfaces of the MUWP System.

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11.3 Upgraded Conponents di i

A detailed listing of the components upgraded for the MUWP System follows, including identification of those interfacing system components not requiring upgrade.

S MAKEUP Sheets 1,2WATER SYSTEM and 3. (atg (PURIFIED)2)SAR Figure 9.2-5 GE Drawing 107E5111 Rev. 2

- Kg/cm .

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i MUWP interface with the SLC System makeup seal and storage tank fill line.

t Reference Components Press./ Temp./ Design / Seismic Class Remarks l 80A-SLC -F013 Check Valve 28.8 atg. 66 C, 4D.C No change i 80A-MUWP-F019 Valve LO 14 atg 66 C, 4D,C No change  !

80A-MUWF-F163 Valve LO 14 atg, 66 C, 4D.C No change  !

80A-MT0P-2 U Pipe 14 atg, 66 C, 4D.C No change  !

803-trJWP-l'.4 Pipe 14 atg, 66 C, 4D,C No change 80A-hdWP-I (62 Valve LO 14 atg, 66 C, 4D.C No change 100A-MUWP-180 Pipe 14 atg, 66 C, 4D.C No change 125A-MUWP-101 Pipe 14 atg, 66 C, 4D C No change 125A-MUWP-F101 Valve LO 14 atg, 66 C, 4D C No change 20A-MUWP-602 Pipe 14 atg, 66 C, 4D,C No change 20A-MUUP-F602 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-601 Pipe 14 atg, 66 C, 4D,C No change 20A-MUWP-F601 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-FQ102 Flow Integr.14 atg, 66 C, 4D.C No change  :

20A-MUWP-801 Pipe 14 atg, 66 C, 4D.C No change 20A-MUWP-F801 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-800 Pipe 14 atg, 66 C, 4D.C No change 20A-MUWP-F800 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-PX101 Press. Pt. 14 atg, 66 C, 4D,C No change 20A-MUWP-600 Pipe 14 atg, 66 C, 4D.C No change 20A-MUWP-F600 Valve NC 14 atg. 66 C, 4D C No change '

125A-MUWP-F100 Valve ID 14 atg, 66 C, 4D,C No change 125A-MUWP-102 Pipe 14 atg 66 C, 4D.C No change 125A-MUWP-F102 Valve NC 14 atg, 66 C, 4D,C No change i 150A-MUWP-xxx Pipe 14 atg, 66 C, 4D,C No change 1 150A-MUWP-Fxxx Check Valve 14 atg, 66 C, 6D C No change l

150A-MUWP-xxx Pipe Static Head, 66 C, 4D.C No change  :

Condensate Storage Tank, 66 C, 4D,Non-seismic No change l

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Page A - 46 11.3 continued MUWP System interface with RRS for Reactor Internal Pump (RIP) casing makeup water.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 15A-RRS-502A-K Pipes 87.9atg,302 C, 4A,As No change 15A-RRS-F504A-K Valves NC 87.9atg,302 C, 4A,As No change 15A-MUWP-189-198 Pipes 28.8atg, 66 C, 4D,C Was 14 atg 50A-MUWP-185 Pipe 28.8atg, 66 C, 4D C Was 14 atg }

28.8atg,171 C, 3B,As Was 14 atg 50A-MUWP-F142 Check Valve 50A MUWP-184 Pipe 28.8atg,171 C, 3B As Was 14 atg 50A-MUWP-F141 Valves NC 28.8atg,171 C, 3B As Was 14 atg i 50A-MUUP-183 Pipe 14 atg, 66 C, 4D.C No change 80A-MUWP-181 Pipe 14 atg, 66 C, 4D C No change 80A-MUWP-F140 Valve LO 14 atg, 66 C, 4D,C No change 125A-MUWP-101 Pipe 14 atg, 66 C, 4D.C No change 125A-MUWP-F101 Valve LO 14 atg, 66 C, 4D C No change 20A-MUWP-602 Pipe 14 atg, 66 C, 4D,C No change 20A-MUWP-F602 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-601 Pipe 14 atg, 66 C, 4D.C No change 20A-MUWP-F601 Valve NC 14 atg, 66 C, 4D.C No change 20A-MUWP-FQ102 Flow Integr.14 arg, 66 C, 4D.C No change 20A-MUWP-801 Pipe 14 atg, 66 C, 4D,C No change 20A-MUWP-F801 Valve NC 14 atg, 66 C, 4D,C No change 20A-MUWP-800 Pipe 14 atg, 66 C, 4D.C No change

! 20A-MUWP-F800 Valve NC 14 atg, 66 C, 4D C No change l 20A-MUWP-PX101 Press. Pt. 14 atg, 66 C, 4D,C No change 20A-MUUP-600 Pipe 14 atg, 66 C, 4D,C No change 20A-MUUP-F600 Valve NC 14 atg, 66 C, 4D,C No change 20A-MUWP-F100 Valve LO 14 atg, 66 C, 4D,C No change 125A-MUWP-102 Pipe 14 atg, 66 C, 4D.C No change 125A-MUWP-F102 Valve NC 14 atg, 66 C, 4D C No change  !

150A-MUWP-xxx Pipe 14 atg, 66 C, 4D,C No change  !

150A-MUWP-xxx Pipe 14 atg, 66 C, 4D.C No change i 150A-RRS-Fxxx Check Valve 14 atg, 66 C, 4D.C No change

! 150A-MUWP-xxx Pipe Static Head, 66 C, 4D.C No change l

Condensate Storage Tank, 66 C, 4D,Non-seismic No change

j Page A Zh'7 12.0 Radwaste System 12.1 Upgrade Description The Radwaste System LCW and HCW inlet piping header connects to each interfacing system at a valve. The header is not upgraded because it is an open pathway to the collector tanks. The dual LCW tanks rotate the fill mode one at a time through a level controlled AO valve at the inlet of each tank. The maintenance valve is a lock open type. The dual HCW tanks operate similarly to the LCW tanks.

12.2 Downstream Interfaces other systems are listed below that interface with the RW System and could  !

possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

There are no downstream interfaces because the LCW and HCW collector tanks and associated piping are all at atmospheric pressure since the HVAC System tank exhaust vents each tank.

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Page A - 4 8 12.3 Upgraded Components A detailed listing of the components upgraded for the RW System follows, l

including identification of those interfacing system components not requiring upgrade.

RADVASTE SYSTEM SSAR Figure 11.2-2 GE Drawing 103E1634 Rev. IP, Sheets 1, 3 and

7. (atg - Kg/cm 2).

RW LCW Subsystem interface with the RHR System Reference Components Press./ Temp./ Design / Seismic Class Remarks l 150A-RHR 129 Pipe 35 arg, 66 C,3B As No change 150A-LCW-F006 Valve 28.8 atg, 66 C,4D,B Was 10 atg 150A-LCW-CS Pipe 10 atg, 66 C,4D,B No change 200A-LCW-CS Pipe 10 atg, 66 C,4D,B No change i 200A-LCV-CS Valve LO 10 arg, 66 C,4D,B No change

! 200A-LCW-CS AO Valve 10 atg, 66 C,4D,B No change l

  • LCU Collector Tank A 0 atg, 66 C,4D,B No change l 200A-LCW-CS Valve LO 10 atg, 66 C,4D,B No change i

200A-LCW-CS A0 Valve 10 atg, 66 C,4D,B No change

  • LCW Collector Tank B 0 arg, 66 C,4D,B No change
  • Each LCW collector rank has HVAC tank vent system exhausting tank air through filter to RW Stack.

RW HCW Subsystem A interface with the RHR System Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 018 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 150A-RHR-F026A Valve 28.8 atg, 182 C,3B,As Was 14 atg 150A-HCV-SS Valve 28.8 atg, 182 C,3B,As Was 10 atg 150A-HCW-SS Pipe 10 arg, 66 C,4D,B No change 150A-HCW-SS Valve LO 10 atg, 66 C,4D,B No change 150A-HCW-F003A Valve AO 10 atg, 66 C,4D,B No change

  • HCW Collector Tank A 0 atg, 66 C,4D,B No change 150A-HCW-SS Valve LO 10 arg, 66 C,4D,B No change 150A-HCW-F003B Valve 10 atg, 66 C,4D,B No change
  • HCW Collector Tank B 0 atg, 66 C,4D,B No change
  • Each HCW collector tank has HVAC tank vent system exhausting tank air through I filter to RW Stack.

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PageA-4-9 12.3 continued RW HCW Subsystem B interface with the RHR System Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 124 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 150A-RHR-F026B Valve 28.8 atg 182 C,3B.As Was 14 atg 150A-HCW-SS Valve 28.8 atg, 182 C,3B.As Was 10 atg l 150A-HCW-SS Pipe 10 atg. 66 C,4D,B No change ,

150A-HCW-SS Valve ID 10 atg, 66 C,4D B No change l 150A-HCW-F003A Valve AO 10 atg, 66 C,4D,B No change

  • HCW Collector Tank A 0 atg, 66 C,4D,B No change 150A-HCW-SS Valve LO 10 atg, 66 C,4D,B No change 150A-HCW-F003B Valve 10 atg, 66 C,4D,B No change
  • HCW Collector Tank B 0 atg, 66 C,4D,B No change
  • Each HCW collector tank has HVAC tank vent system exhausting tank air through filter to RW Stack.

RW HCW Subsystem C interface with the RHR System Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 225 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 150A-RHR-F026C Valve 28.8 atg, 182 C,3B,As Was 14 atg 150A-HCW-SS Valve 28.8 atg 182 C,3B,As Was 10 atg 150A-HCW-SS Pipe 10 atg, 66 C,4D,B No change 150A-HCW-SS Valve LO 10 atg, 66 C,4D,B No change 150A-HCW-F003A Valve AD 10 atg, 66 C,4D,B No change

  • HCW Collector Tank A 0 atg, 66 C,4D,B No change 150A-HCW-SS Valve ID 10 atg, 66 C,4D,B No change 150A-HCW-F003B Valve 10 atg, 66 C,4D,B No change
  • HCW Collector Tank B 0 atg, 66 C,4D,B No change
  • Each HCW collector tank has HVAC tank vent system exhausting tank air through filter to RW Stack.

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