ML20045G709

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Forwards Ssar Markup Resolving ISLOCA Issue 42 Re Intersys LOCA for Abwr,Replacing Text in Author 930430 Ltr
ML20045G709
Person / Time
Site: 05200001
Issue date: 07/09/1993
From: Fox J
GENERAL ELECTRIC CO.
To: Poslusny C
Office of Nuclear Reactor Regulation
References
NUDOCS 9307150079
Download: ML20045G709 (70)
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Text

L GENuclearEnergy Genera!Decmc Company 175 Cunnw Avenue, Sc hse. CA 95125 July 9,1993 Docket No. STN 52-001 ,

Chet Posiusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Schedule - ISLOCA (Issue #42)

Dear Chet:

Enclosed is a SSAR markup resolving ISLOCA issue #42. This replaces the text part of my April 30,1993 letter. However, the marked up P&lDs of my Aprilletter still apply and they are not repeated in this transmittal.

Please provide a copy of this transmittal to George Thomas.

Sincerely, h

J. k Fox Advanced Reactor Programs cc: Alan Beard (GE)

Norman Fletcher (DOE)

Bill Taft (GE) nn w eg J

930715o079 930709 mF PDR ADOCK 05200001 A PDR j

APPENDIX 3M l 1

RESOLUTION OF INTERSYSTEM LOSS OF COOLANT ACCIDENT. .

FOR ABWR l

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ABM 21A6100AE REV B Standard Plant 3.9.5.3.6 Stress, Deformation, and Fatigue 3.9.6 Testing of Pumps and Valves Limits for Safety Class and Other Reactor Internals (Except Core Support Structures) Inservice testing of safety-related pumps and

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valves will be performed in accordance with the For safety class reactor internals, the stress requirements of ASME/ ANSI OMa-1988 Addenda to deformation and fatigue criteria listed in Tables ASME/ ANSI OM-1987, Parts 1,6 and 10. Table 3.9-4 through 3.9-7 are based on the criteria 3.9-8 lists the inservice testing parameters and I established in applicable codes and standards for frequencies for the safety-related pumps and similar equipment, by manufacturers standards, or valves. The reason for each code defined by empirical methods based on field experience testing exception or justification for each code (minimum exemption request is noted in the description of and safetytesting.

factor) For the quantity appearing in those SF,;, tables, the the affected pump or valve. Valves having a following values are used: containment isolation ft, ; tion are also noted in the listing. Inservice inspection is discussed l Service Service 3p in Subsection 5.2.4 and 6.6.

Lml Condition rnin Details of the inservice testing program, l A Normal 2.25 including test schedules and frequencies will be B Upset 2.25 reported in the inservice inspection and testing l C Emergency 1.5 plan which will be provided by the applicant D Faulted 1.125 referencing the ABWR design. The plan will integrate the applicable test requirements for Components inside the reactor pressure vessel safety-related pumps and valves including those such as control rods which must move during listed in the technical specifications (Chapter accident condition have been examined to 16) and the containtnent isolation system, determine if adequate clearances exist during (Subsection 6.2.4). For example, the periedic emergency and faulted conditions. No mechanical leak testing of thgreactor coolant pressure clearance problems have been identified. The isolation valves in Table 3.9-9 will be forcing functions applicable to the reactor performed in accordance with Chapter 16 internals are discussed in Subsection 3.9.2.5. Surveillance Requirement SR 3.6.1.5.10. This plan will include baseline pre service testing The design criteria, loading conditions, and to support the periodic in-service testing of analyses that provide the basis for the design of the components. Depending on the test results, the safety class reactor internals other than the the plan will provide a commitment to core support structures meet the guidelines of disassemble and inspect the safety related pumps NG-3000 and are constructed so as not to and valves when limits of the OM Code are adversely affect the integrity of the core exceeded, as described in the following support structures (NG-1122). paragraphs. The primary elements of this plan, including the requirements of Generic Letttir The design requirements for equipment 8910 for motor operated valves, are delineated classified as non-safety (other) class internals in the subsections to follow. (See Subsection (e.g., steam dryers and shroud heads) are 3.9.7.3 for COL license inform ation specified with appropriate consideration of the requirements).

intended service of the equipment and expected plant and environmental conditions under which it 3.9.6.1 Testing of Safety Related Pumps will operate. Where Code design requirements are not applicable, accepted industry or engineering For each pump, the design basis and required practices are used, operating conditions (including tests) under which the pump will be required to function will be established. These designs (design basis and

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Page I s u,I introduction An 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 f subsyncms 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 1 and the NRC Staff recommended specific URS design characteristics by Reference 2. i

'3M,2 ABWR Regulatory Reauirements 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 l requiring that low-pressure piping systems that interface with the reactor  ;

coolant pressure boundary be designed to . withstand reactor pressure to the extent practicable. 1-lowever, the staff believes that for those systems that have not been designed to withstand full reactor pressure, evolutionary ALWRs should provide (l) the capability for leak testing the pressure isolation valves, (2) valve position indication that is available in the control room when isolation valve operators are deenergized and (3) high-pressure alarms to warn main control room operators when rising 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 necessary to provide a higher system ultimate pressure capability for the entire low-pressure connected system. The staff will

Page 2 q

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

GE provided a proposed implementation of the issue resolution for the ABWR in Reference 5 and again in Reference 6. The staff in the Civil Engineering and Geosciences Branch of the Division of Engineering ,

completed its evaluation of the Reference 5 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.

l 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 O.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. 1 The design is to be in accordance with the ASME Boiler and Pressure i Vessel Code, Section 111 Subarticle NC/ND-3600. Furthermore,' the staff l 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.

3n3 Boundary Limits of URS Guidance given by Reference 3 provides provision for applying practical 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 boundary limits of URS for the ABWR:

1. It is impractical to consider a disruptive open flow path from reactor pressure to a low pressure sink. A key assumption to >

understanding the establishment of the boundary limits from i this practicality basis is that only static pressure conditions are

Page 3 considered. Static conditions are assumed when the valve adjacent to a low pressure sink remains closed. Thus, the dynamic pressurization effects accompanied by 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. As a consequence, the furthest downstream valve in such a path is assumed closed so that essentially all of the static reactor pressure is contained by the URS upgraded . region.

2. It is impractical to design or construct large tank structures to the URS design pressure that are vented to atmosphere and have a low design pressure. Tanks included in this category are:

Condensate storage tank, SLC main tank, LCW receiving tank, HCW receiving tank, FPC skimmer surge tank, and FPC spent fuel storage pool and cask pit.

Condensate hotwell '

These are termed low pressure sinks for the purposes of this report. See Table i for approximate sizes of these tanks as an indication of the impracticality o.f increasing the design pressure.

The size of these tanks would result in an unnecessary dollar cost burden to increase their design pressure to the URS value.

The small tanks in Table 1 are greater than 3 meters in height and diameter. (For perspective, remember the "3 meter board" at the swimming pool is the high dive.) The large condensate storage tank, if constructed with its height equal to the diameter, is approximately as tall as a four story building. The FPC System's tank, pool, and pit (Table 1) have no top cover and are open to the large refueling floor (bay), so that their pressure can not be increased above the static head for which they are designed.

Page 4

3. It is impractical to design piping systems that are connected to low pressure sink features to the URS ' design pressure when the piping is always locked open to a low pressure sink by locked open valves. These piping sections are extensions of the low pressure sink and need no greater design pressure than the low pressure sink to which they are connected.

In summary, the following low pressure sinks are . protected by an adjacent closed valve and are impractical to design to the URS design pressure.

(1) Suppression Poql_- Provides a normal low pressure sink, approximate'y 0.05 arg (0.75 psig) above atmospheric for its interfacing.

systems and the first closed valve is at least 28.8 atg (410 psig) rated. The suppression pool is designed to Seismic Category 1.

(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  !

I interfacing systems. The first closed valve of each interfacing system with i URS upgrade is at least 28.8 atg (410 psig) rating.

(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 Category 1. i l

(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.

(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.

(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 floor.- The first closed valve is at least 28.8 atg (410 psig) rated.

The FPC skimmer surge tank is designed to Seismic Category 1.

-- - .-- -= ._ - .

Page 5  ;

i (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 floor. 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 1. ,

(8) Condensate llotwell - During reactor high pressure operation, the hotwell operates at a vacuum pressure. ,

3MA Evaluation Procedure The pressure of each system piping boundary on all of the ABWR P&lD'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 )

pressure values were increased to 28.8 atg which is equiva'ent to 410 psig.  !

(1 at = 1 kg/cm2; atg is gage) The low pressure piping boundaries were j upgraded to URS pressures and extend to the last closed valve connected to piping interfacing a low pressure sink, such as the suppression pool, I 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. I For some systems, with low pressure piping and normally open valves, the l 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 llCW receiving tank piping,
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.

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Page 6 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 piping, equipment and instruments.

'P 3 K.5 Systems Evaluated The following fourteen systems, interfacing directly or indirectly with the RCPB, were evaluated.

SSAR Figure No.

^

1. Residual Heat Removal (RHR) System 5.4-10
2. High Pressure Core Flooder (llPCF) System 6.3-7 ,
3. Reactor Core Isolation Cooling (RCIC) System 5.4-8
4. Control Rod Drive (CRD) System 4.6-8
5. Standby Liquid Control (SLC) System 9.3-1
6. Reactor Water Cleanup (CUW) System 5.4-12
7. Fuel Pool Cooling Cleanup (FPC) System 9.1-1 ,
8. Nuclear Boiler (NB) System 5.1-3
9. Reactor Recirculation (RRS) System 5.4-4
10. Makeup Water (Condensate) (MUWC) System, 9.2-4
11. Makeup Water (Purified) (MUWP) System. 9.2-5
12. Radwaste System i1.2-2 (LCW Receiving Tank, HCW Receiving Tank).
13. Condensate and Feedwater (CFS) System 10.4-6
14. Sampling (SAM) System -

Appendix A contains a system-by-system evaluation of potential reactor pressure application to piping and components, discussing the URS boundary and listing the upgraded components. For some systems, certain regions of piping and components not upgraded are also listed.

Page 7 3 M4 Pining Design Pressure for URS Compliance Guidelines for URS compliance were established by Reference 2, which

. concluded 't hat for the ABWR that:

1. The design pressure for the low-pressure piping systems that {

interface with the RCPB pressure boundary should be equal to  ;

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

410 psig), and  ;

2. The minimum wall thickness of the low-pressure piping should be 1

no less than that of a standard weight pipe.  !

"5 M .7 Anolicability of URS Non-nininn Comnonents Reference 2 also provided the NRC Staffs 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 operating reactor pressure (i.e., 410 psig). This is accomplished in the SSAR by the revised boundary symbols of the P&lDs to the 28.8 atg design pressure, which includes all the piping and components associated with the boundary symbols. A stated parameter (e.g., design pressure) of a boundary symbol on the P&lD applies to all the piping and components on the P&lD that extend away from the boundary symbol, including along any branch line, until another boundary symbol occurs on the P&lD.  !

The components include heat exchangers, flanges, and pump seals, etc. as shown on the P&lD.

2. A Class 300 valve is adequate for ensuring the pressure of the  !

low-pressure piping system under full reactor pressure. The rated working pressure for Class 300 valves varies widely depending on material and temperature ( ASME/ ANSI B16.34).

However, as a lower limit bounding condition, within the material group that includes the stainless steels, the lowest working pressure is 29.2 kg/cm2 g (415 psig) at 204 C (400 F),

which exceeds the URS of 28.8 kg/cm2 g (410 psig). For lower

Page 8 temperatures the working pressure increases. The material group that includes the carbon steels has working pressures above this value. More typical working pressure values at 93 C (200 "F) range between 42 to 49 kg/cm2 g (600 to 700 psig).

3 M.B Results The results of this work are shown by the markups of. the enclosed P&lDs,.

which are SSAR figures. The affected sheets are listed below.

System SSAR Affected Sheet-Figure No. Nos.

1. Residual lieat Removal (RIIR) 5.4-10 1,2,3,4,6,7 System
2. 1ligh Pressure Core Flooder 6.3-7 1, 2 (IIPCF) System
3. Reactor Core Isolation Cooling 5.4-8 1, 3 (RCIC) System 4 Control Rod Drive (CRD) 4.6-8 1, 3 System
5. Standby Liquid Control (SLC) 9.3-1 1 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
9. Reactor Recirculation (RRS) 5.4 4 1 System

Page 9 System SSAR Affected Sheet Figure No. Nos.

I

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) .)
13. Condensate and Feedwater 10.4-6 (CSF) System
14. Sampling (SAM) System utbchm ed Also, see -Appemh A for more detail.

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 3 M 9 yiilve Misalignment Due To Operator Error An important result to observe is that because of the widespread application of the URS boundary for the ABWR design as compared to previously constructed BWRs, misalignment of valves due to operator error is not a contributor to ISLOCA. The ISLOCA issue that has been dealt with for existing BWRs, where valve misalignment due to operator error was a significant contributor to ISLOCA considerations, had to use the design pressures used for plant construction that were accepted before ISLOCA issues were considered. As a result, operator error of valve misalignment could possibly result in situations where high pressure might occur in piping regions with design pressures below the current accepted URS

Page 10 design pressure (28.8 kg/cm2g). However, the ABWR design with the ISLOCA URS applied for the boundary described by this report, has '

extended the increased design pressure (URS) over the full extent of regions that could potentially experience reactor pressure, so that operator misaligned valves will not expose piping to reactor pressure not designed to the URS pressure.

3 M.to Additional Operational Considerations t

The periodic surveillance testing of the ECCS injection valves that interface with the reactor coolant system might lead to ISLOCA conditions if their associated testable check valve was stuck open. To avoid this occurrence, 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).

1 3M.tt 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 atg (1025 psig) by applying the guidance recommended by Reference 2. This design pressure was i applied to the low pressure piping at their boundary symbols on the P&lDs, 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

Page 11 l

P&lD requiring pipe to have a minimum wall thickness equal to standard  ;

grade. Upgrading revisions ivere made to 13 systems.

3 M.t2 R e fere nces

1. Dino Scaletti, NRC, to Patrick Marriott, GE, " Identification of New issues for the General Electric Company Advanced Boiling Water Reactor Review," September 6,1991
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 2, 1992, Docket No.52-001 1

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," J an. 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
6. Jack Fox, GE, to Chet Posiusny, NRC, " Resolution of Intersystem Loss of Coolant Accident for ABWR," April 30,1993.

Page 12.

Table 1 Low Pressure Sink Component Sizes Tank Name Volume Diameter lleight Length Width Design Note rn 3 m m m m pressure kg/cm2g I

Condensate storage tank 2110 13.9 13.9 14 (1)

SLC main tank 32 3.44 3.44 SWil (1)

LCW receiving tank 430 8.18 8. I 8 10 (1) p to 45 3.85 3.85 10 (1) P llCW receiving tank FPC skimmer surge tank 30 2.3 7 . '2 SWil h FPC spent fuel storage pool 2960 11.8 17.9 14.0 SWil FPC cask pit 121 11.8 3.2 3.2 SWil Condensate hotwell 7800 20- 30 13

)

N'otes:

(1) Diameter and height calculated from volume based on diameter = height.

SWil = Static water head

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1 Page A- l ATTACnMcwT A System Evaluation General Comments About the Anpendix t

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, "Downstre.am 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 .l are shown as "No change." The listings are grouped in sections that  !

describe a particular pressure travel path. This grouping may include I 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 valve at the URS boundary. ,

1

1. }Lesidual Heat Removal System l

u 1.1 Upgrade Description The RHR System pump suction piping was low pressure and has been upgraded to the URS design pressure. The RHR has two suction sources, j 1

l

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 Ell-F001. The suppression pool is a large structure, j 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 ]

1 Other systems are listed below that interface with RilR 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 MUWC upgrades 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. There is no source to pressurize the MUWC line because of closed valves in the RilR System's URS region.

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

i Page A- 3; .

- 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 ,

without upgrade.

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

- 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.  ;

I l

- The Fire Protection System and the fire truck connection provide l water for the Alternating Current (AC) Independent Water Addition piping  !

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 ]

b!ced valves, RHR-F101 and RHR-F102, and a drain pipe between these 1 1

valves vented to the HCW sump in the Reactor Building. This design very l effectively prevents reactor pressure from reaching the Fire Protection System. No upgrade to URS is practical or appropriate for the extensive piping of the Fire Protection System since the system function is not related to ISLOCA nor is its interconnection a normal plant operational pathway.

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

T

  1. 8' A ~ 4 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, RESIDUALHEATREMOVALSYSTEM, Sheets 1 through 7. (atg - Kg/cm ssp): Figure 5.4-10,GEDrawing103E1797Rev.

RHR Subsystem A suction piping from the suppression pool.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 RHR Pump C001A 35 atg, 182 No change 450A-RHR-002 Pipe 28.8 atg. 182,C,3B As C,3B,As Was 14 atg 20A-RRR-701 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-F701A Velve 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 450A-RHR-D002A Temp.Str. 28.6 atg. 182 C,3B,As Was 14 atg 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-PIO01A Press.I 28.8 atg, 182 C,3B As Was 14 atg 50A-RHR-018 Pipe 28.8 arg, 182 C,3B.As Was 14 atg 50A-RHR-F026A Valve 28.8 atg, 182 C,3B,As Was 14 atg j 450A-RHR F001A MO Valve 28.8 atg. 182 C,3B,As Was 14 atg  ;

Sheet 2 450A-RHR-001 Pipe 3.16atg, 104 C,3B,As No change l 450A-RHR-D001A Suct.Str. 3.16atg, 104 C,3B,As No change l I

RHR Subsystem A suction piping from the reactor presssure vessel Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 350A-RHR-011 Pipe 28.8 atg, 182 C,3B,As Was 14 atg j 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 arg 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 50A RHR-F712A Valve 28.8 atg, 182 C,3B.As Was 14 atg 20A-RHR-PT009A Press.T 28.8 atg, 182 C,3B,As Was 14 atg Sheet 2 350A-RHR 011 Pipe 28.8 atg, 182 C,3B.As Was 14 atg

  • 20A-RHR F508A Valve 28.8 arg, 182 C,3B,As Was 14 atg 25A-RHR-030 Pipe 28.8 arg, 182 C,3B.As Was 14 atg
    • 100A-RHR F041A Check V. 28.8 atg, 182 C,3B As Was 14 atg
    • 100A-RHR F040A Valve. 28.8 atg, 182 C,38,As Was 14 atg
    • To HUW(Concensate) Sytem interface.

Page A . g 1.3 continued RHR Subsystem A discharge fill pump suction piping from the suppression pool.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 40A RHR-C002A Pump 28.8 atg, 182 C,3B,As Was 14 atg 40A-RHR-015 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 40A-RHR-F022A Valve 28.8 atg, 182 C,3B,As Was 14 atg 40A-RHR-D008A Temp.Str. 28.8 arg, 182 C,3B,As Was 14 atg 20A RHR-708 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 20A-RER-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 25A-RHR-017 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 25A-RHR-F025A Valve 28.8 arg, 182 C,3B,As Was 14 atg 25A-RHR-D009A RO 28.8 atg, 182 C,3B,As Was 14 atg RHR Subsystem A discharge from relief valves and test line valve directly to the suppression pool without restriction.

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 100A-RHR-014 Pipe 3.16 ats, 104 C,3B,As No change-50A-RHR-037 Pipe 3.16 seg, 104 C,3B,As No change 50A RHR-033 Pipe 3.16 atg, 104 C,3B,As No change 50A-RER-021 Pipe 3.16 atg, 104 C,3B As No change Sheet 2 250A-RHR-008 Pipe 3.16 arg, 104 C,3B,As No change Suppression Pool RHR Subsystem A flushing line interface at branch discharging to feedvater.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 100A MUWC-134 Pipe 14 atg, 66 C,4D,B No change Sheet 3 100A RHR -F032A Valve 35 atg, 182 C,3B,As No change 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 RHR Subsystem A flushing line interface at suction shutdown branch from RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 100A-HWC-133 Pipe 14 arg, 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 aeg, 182 C,3B.As Was 14 atg

Page A - 6 I 1.3 continued RHR Subsystem B suction piping from the suppression pool. I Reference Components Press./ Temp./ Design / Seismic Class Remarks  !

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 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 Vas 14 atg 450A-RHR-D002B Temp.Str. 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-730 Pipe 28.8 atg. 182 C,3B,As Was 14 atg 20A-RHR F700B Valve 28.8 atg, 182 C,3B,As Was 14 atg 20A RHR-PI001B Press.I 28.8 atg, 182 C,3B.As Vas 14 atg 50A-RHR-124 Pipe 28.8 arg, 182,C,3B.As Was 14 atg 50A-RHR-F026B Valve 28.8 atg, 182,C,3B,As Was 14 atg 450A-RHR-F001B MO Valve 28.8 atg, 182 C,3B,As Vas 14 atg Sheet 2 450A-RHR-101 Pipe 3.16atg, 104 C,3B,As No change 450A-RHR-D001B Suet.Str. 3.16arg, 104 C,3B,As No change RER 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 atg, 182 C,3B,As Was 14 atg 350A-RHR-F012B MO Valve 28.8 atg. 182 C,3B,As Vas 14 atg  :

25A-RHR-139 Pipe 28.8 arg, 182 C,3B,As Was 14 atg 25A-RHR-F042B Rel. Valve 28.8 arg, 182 C,3B,As Vas 14 atg 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 Vas 14 atg 20A-RHR-F712B Valve 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-PT009B Press.T 28.8 atg. 182 C,3B,As Was 14 atg Sheet 2 350A-RHR-111 Pipe 28.8 atg, 182 C,3B,As Vas 14 atg

      • 100A-RHR 138 Pipe 28.8 atg, 182 C,3B,As Vas 14 atg
      • 100A RHR-F041B Check V. 28.8 atg. 182 C,38,As Vas 14 atg
      • To MUV(Concensate) Sytem interface.

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q Page A - 7 l 1.3 continued ,

i RHR Subsystem B discharge fill pump suction piping from the suppression pool, l

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 4 40A-RHR-C002B Pipe 28.8 arg, 182 C,3B.As Was 14 atg 40A-RHR-121 Pipe 28.8 atg, 182 C,3B.As Was 14 atg 40A-RER F022B Valve 28.8 atg, 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 atg 20A-RHR-F713B Valve 28.8 arg, 182 C,3B.As Was 14 atg 20A-RHR-PX010BPress.Pt. 28.8 atg, 182 C,3B,As Was 14 atg 25A-RHR-123 Pipe 28.8 atg, 182 C,3B.As Was 14 atg 25A-RHR-F025B valve 28.8 atg, 182 C,3B.As Was 14 atg 25A-RHR-D009B R0 28.8 atg, 182 C,3B,As Was 14 atg RHR Subsystem B flushing line interface at branch discharging to RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 100A-MUWC-137 Pipe 14 atg, 66 C,4D,B No change Sheet 5 100A-RHR -F032B Valve 35 atg, 182 C,3B,As No change 100A-RER -132 Pipe 35 atg. 182 C,3B,As No change i 100A-RHR -F033B Check V. 35 arg, 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-MUWC-136 Pipe 14 atg, 66 C,4D,B No change Sheet 2 100A-RER -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 suction piping from the suppression pool.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 6 RHR Pump C001C 35 atg, 1S2 C,3B,As No change 450A-RER-202 Pipe 28.8 ats, 182 C,3B,As Was 14 atg 20A-RER-761 Pipe 28.8 atg, 182 C,3B,As Was 14 atg 20A-RHR-F701C Valve 28.8 atg, 182 C,3B.As Was 14 atg 20A-RHR-PX002C Press.Pt. 28.8 atg, 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 l 20A-RHR-F700C Valve 28.8 atg, 182,C,3B As Was 14 atg 20A-RHR-PI001C Press.I 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 atg. 182 C,3B,As Was 14 atg 450A-RHR-F001C H0 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-RER-D001C Suct.Str. 3.16atg. 104 C,3B,As No change 1

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Page A - 8 1.3 continued RER 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 atg. 104 C,3B,As No change 100A-RHR-131 Pipe 3.16 atg, 104 C,3B.As No change 100A-RHR-120 Pipe 3.16 atg, 104 C,3B.As No change 50A-RHR-145 Pipe 3.16 atg, 104 C,3B,As No change 50A-RHR-140 Pipe 3.16 atg, 104 C,3B.As No change 50A-RHR-127 Pipe 3.16 arg, 104 C,3B.As No change Sheet 2 250A-RHR-109 Pipe 3.16 atg, 104 C,3B,As No change Suppression Pool RRR Subsytem B interface with Radvaste System.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 4 150A RHR-129 Pipe 35 arg, 182 C,3B.As No change 150A-LCV-F006 Valve 28.8 atg, 66 C,4D,B Was 10 atg 150A-LCV-CS Pipe 10 atg, 66 ':,4D, B No change 200A LCV-CS Pipe 10 atg, 66 C,4D,b No change 200A-LCW-CS Valve LO 10 atg, 66 C,4D,B No change 200A-LCV-CS A0 Valve 10 atg, 66 C,4D,B No change

  • LCW 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 200A-LCV-CS A0 Valve 10 atg, 66 C,4D,B No change
  • LCV Collector Tank B 0 atg, 66 C,4D,B No change
  • Each LCV 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 atg, 182 C,3B As Was 14 atg 350A RRR-F012C M0 Valve 28.8 atg, 182 C,3B As Was 14 atg 25A-RHR 240 Pipe 28.8 arg, 182 C,3B As Was 14 atg 25A-RHR F042C Rel. Valve 28.8 atg, 182 C,3B,As Was 14 atg 50A-RHR-241 Pipe 28,8 atg, 182 C,3B.As Was 14 atg 20A-RHR 767 Pipe 28.8 atg, 182 C,3B.As Vas 14 atg 50A-RHR-F712C Valve 28.8 atg, 182 C,3B,As Was 14 atg 20A RHR-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

    • 300A RHR-215 Pipe 28.8 atg, 182 C,3B.As Was 14 atg
  • To LOW funnel drain to LCW Sump. ** To FPC System interface.
      • To MUW(Concensate) Sytem interface.

l Page A - i 1.3 continued l l

RHR Subsystem C discharge fill pump suction piping from the suppression pool.

Reference Components Press / Temp./ Design / Seismic Class Remarks Sheet 6 40A-RHR-C002C Pump 8 8 atg. 182 C,3B,As Was 14 atg 40A-RHR-222 Pip 182 C,3B.As Was 14 atg 40A-RRR-F022C Valve 2. g, 82 C,3B,As o

Was 14 atg 40A-RRR-D00BC Temp.Str. 28 8 atg. y,, 13 ,gg 20A-RHR-768 Pipe .

, ,, 4 ,gg 20A-RRR-F713C Valve -

8 82 C,3B,As Was 14 atg 20A-RHR-PX010C Press.Pt. 28.8 atg, 182oC 3B As Was 14 atg 25A-RHR.224 Pipe ' ,, ,g 25A-RRR-F025C valve 28.8 atg, C.3B,As Was 14 atg 25A-RHR-D009C RO 28.8 atg, . p RHR Subsystem C discharge from relief valves and test line valve direct to the suppression pool without restriction.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 250A-RHR-209 Pipe 3.16 arg, 104 C,3B,As No change 100A-RHR-232 Pipe 3.16 atg, 104 C,3B,As No change.

100A-RRR-221 Pipe 3.16 atg, 104 C,3B.As No change' 50A-RHR-246 Pipe 3.16 atg. 104 C,3B.As No change 50A-RHR-241 Pipe 3.16 aeg, 104 C,3B,As No change 50A-RHR-228 Pipe 3.16 atg. 104 C,3B,As No change Sheet 2 250A RRR-209 Pipe 3.16 atg, 104 C,3B,As No change Suppression Pool RER Subsystem C flushing line interface at branch discharge to RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 100A-MUWC-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 arg, 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 100A MWC-140 Pipe 14 atg. 66 C,4D,B No change 100A-RHR -F040C Valve 28.8 atg, 182 C,3B.As Vas 14 atg 100A-RHR -239 Pipe 28.8 arg, 182 C,3B,As Was 14 atg 100A-RHR -F041C Check V. 28.8 atg, 182 C,3B,As Was 14 atg

Page A . go 1.3 continued RRR Subsystem C outdoor fire truck connection in RHR pump discharge pipe to RPV.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 7 100A-RHR -F103 Valve 28.8 atg, 66 C,7E,C Vas 16 arg 100A-RHR -F104 Check V. 28.8 atg, 66,C,7E,C Vas 16 atg 100A-RHR -249 Pipe 28.8 atg, 66,C,7E,C Vas 16 atg 100A-RHR -247 Pipe 28.8 atg, 66,C,7E,C Vas 16 atg 100A-RNR F100 Check V. 28.8 atg, 66 C,7F,C Vas 16 atg 100A-RHR -F101 Key Lock V.35 atg, 182 C,3B.As No change 100A-RHR -248 Pipe 35 atg. 182 C,3B As No change 20A-RHR -769 Pipe 35 atg, 182 C,3B,As No change 20A-RHR -F790 Globe V. 35 atg, 182 C,3B,As No change 20A-RHR -PI-099 Press 1 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.LO 35 atg, 182 C,3B As No change 20A-RER -571 Pipe 35 aeg, 182 C,3B As No change
    • 20A-RHR -F591 Globe 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
  • Funnel drain to LCW sump in Reactor Building.
    • Test valve.
      • Injection pipe to RPV at outboard isolation valve MO F-005C.  :

No other low pressure components of the RER 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. High Pressure Core Flooder System 2.1 Upgrade Description The llPCF System pump suction piping was low pressure and has been upgraded to the URS design pressure. The HPCF 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 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 llPCF, 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.

- 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.

Page A- 12.

i There is no source to pressurize the MUWC line because of closed valves in the liPCF System's URS region.

- liigh 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 - 13' 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.

I HICHPRESSURECOREF140DERSYSTEg),SSARFigure6.3-7,GEDrawing107E6008Rev.

IP, Sheets 1 and 2. (atg - Kg/cm :

HPCF Subsystem B suction piping from the suppression pool.

Reference Components Press./ Temp./DesignfSeismicClass Remarks Sheet 2 400A-HPCF-006 Pipe 28.8 atg. 100 C,3B.As Was 14 atg 20A-HPCF-701 Pipe 28.8 atg, 100 C,3B.As Was 14 atg 20A-HPCF-F701B Valve 28.8 atg, 100 C,3B As Was 14 atg 20A-HPCF-PX004B Press. Pt.28.8 arg, 100 C,3B,As Was 14 atg 20A-HPCF-D001B Temp. Str.28.8 atg, 100 C.3B.As Was 14 atg 400A-HPCF-010 Pipe 28.8 atg, 104 C,3B.As- Was 14 stg 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 arg 20A-HPCF PI001B Press.Ind.28.8 arg, 100 C,3B.As Was 14 atg 20A-HPCF-PT002B Press.Trn.28.8 atg, 100 C,3B,As Was 14 atg 20A-HPCF-PT003B Press.Trn.28.8 atS, 100 C,3B,As Was 14 atg 25A-HPCF-023 Pipe 28.8 atg. 100 C,3B.As Was 14 atg 25A-HPCF-F020B Relief V. 28.8 atg, 100 C,3B,As Was 14 _atg 400A HPCF-F007B Check V. 28.8 atg, 100 C,3B As Was 14 atg 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 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,3B As No change Suppression Pool HPCF Subsystem B suction piping from the Condensats Storage Tank.

Reference Components Press./ Temp./DesignfSeismicClass Remarks 400A-HP,CF-006 Pipe 28.8 arg, 100 C,3B As Was 14 atg 50A-HPCF-018 Pipe 28.8 atg, 100 C,3B.As Was 14 atg  !

50A-HPCF-F012B Valve 28.8 atg, 100 C,3B,As Was 14 atg l' 50A-HPCF-F011B valve 28.8 atg. 100 C,3B,As Vas 14 atg 50A-HPCF 017 Pipe 28.8 atg. 100 C,3B,As Was 14 atg 50A-HPCF-F002B Check V. 28.8 aeg, 100 C,3B,As Was 14 atg i 400A-HPCF-F001B MO. Valve 28.8 atg, 100 C,3B,As Was 14 atg 400A-HPCF 005 SS Pipe 14 atg, 66 C,B(S1,S2) No change 500A-HPCF-004 SS Pipe 14 arg, 66 C,B(S1,S2) No change 400A-HPCF-105 SS Pipe 14 aeg, 66 C,B(S1,52) No change 200A-HPCF-015 SS Pipe la atg, 66 C,B(S1,S2) No change 200A-HPCF-016 SS Pipe 14 atg, 66,C.B(S1,S2) No change

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

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Page A - (4 2.3 continued HPCF Subsystam 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 arg, 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.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 20A-MWC- 135 Pipe 14 atg, 66 C,4D,B No change 25A-HPCF-F013B Valve 110 atg, 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 aeg, 100 C,3B,As No change HFCF 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 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 arg, 100 C,3B,As Was 14 atg 50A-HPCF-F012C Valve 28.8 atg, 100 C,3B,As Was 14 arg 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 aeg, 100 C,3B,As Was 14 atg 400A HPCF-110 Pipe 3 16atg, 104 C,3B,As No change 25A-HPCF-173 ripe 28.3 atg, 100 C,3B As Was 14 atg 25A-HPCF-F020C Relief V. 28.8 atg, 100 C,3B,.4 Was 14 atg 400A-HPCP-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 j Suppression Pool 1 l

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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 aeg, 104 No change 200A-HPCF-112 Pipe 3.16 atg, 104,C,3B,As C,3B,As No change 50A-HPCF-124 Pipe 3.16 arg, 104 C.3B.As No change 250A-RHR 209 Pipe 3.16 aeg, 104 C,3B.As. No change Suppression Pool HPCF Subsystem C keep fill line interface.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 1 20A-MWC - 138 tipe 14 atg, 66 C,4D,B No change Sheet 1 25A-HPCF-F013C Valve 110 arg, 100 C,3B,As No change 110 atg, 100 C,3B.As No change 25A-HPCF-D006C R0 50A-HPCF-119 Pipe 110 atg, 100 C,3B.As No change 50A-HPCF-120 Pipe 110 atg, 100 C,3B.As No change 50A-HPCF-F016C Valve 110 arg, 100 C,3B.As No change

  • Connects to locked open valves from condendate storage tank which is vented to atmosphere.

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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 the CST, E51-F001. Beyond this valve, the pipeline is open n 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 e 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.

l 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.  !

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

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

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

Page A- 17 f

- Reactor Core Isolation Cooling System shares common CST suction. j 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.

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- 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.

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Page A - l8 3.3 Upgraded Components A detailed listing of the compor.ents upgraded for the RCIC System follows, including identification of those interfacing system components-not requiring upgrade.

SSAR Figure 5.4-8 GE Drawing 103E1795 REACTORCOREISOLATIONCOOLINGSYSTp):,

Rev. 2P, Sheets 1 & 3. (atg - Kg/cm RCIC pump suction piping Re fe rence 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 arg, 77 C,38,As Was 14 arg 20A-RCIC-F700 Valve 28.8 atg, 77 C,3B,t.s Was 14 atg 20A-RCIC-PT001 P.Trans 28.8 atg, 77 C,3B As Was 14 atg 20A-RCIC-701-W Pipe 28.8 atg, 77 C,3B,As Was 14 atg 20A RCIC-702-W Pipe 28.8 arg, 77 C,3B,As Was 14 atg I 20A RCIC-PIOO3 P.Ind. 28.8 atg, 77"C,3B.As Was 14 atg 20A-RCIC-PT002 P.Trans 28.8 atg, 77 C,3B,As Was 14 atg 50A RCIC-018-W Pipe 28.8 atg, 77 C,3B.As Was 14 atS 50A-RCIC-F017 R. Valve 28.8 atg, 104 C,3B As Was 14 atg 200A-RCIC-r002 T. Check 28.8 ats, 77 C,3B.As Was 14 atg

  • 200A-RCIC F001 MC Valve 28.8 atg. 77 C,3B,As Was 14 atg ,
    • 200A-RCIC F007 Check 28.8 atg, 77 C,3B,As Was 14 atg j
  • HPCF Interface Piping 200A-HPCF-015-S, 14 atg, 66 C.B (51,S2)., As (open pathway to Condensate Storage Tank with LO valves).
    • Suction Piping from Suppression Pool Interface 200A-RCIC 004-U, 3.16 atg, l 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 50A RCIC-009-W Pipe 104 C,3B,As No change; sheet 1 3.16 atg.

50A-RCIC 019-U Pipe 3.16 atg. 104 C,3B,As No change 100A-RCIC-007-W Pipe 3.16 atg, 104 C,3B,As No change Pipe 3.16 atg, 104 C,3B Am No change 250A RHR- 008 Sheet 1 Suppression Pool 1

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Page A - l$

3.3 continued ABVR High Pressure r: ore Flooder System SSAR Figure 6.3-7 GE Drawing 107E6008 Rev. 1P. componets int'frfacing 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 Sheet 1 200A-HPCF-015 W Pipe 14 atg, 66 C B (S1,S2), As No change 400A-HPCF-105-W Pipe 14 atg, 66 C B (51,S2), As No change 500A-HPCF-004-W Pipe 14 arg, 66 C,B (51,S2), As No change 300A-HPCF-001-W Pipe 14 atg, 66 C,B (S1,52), As No change 300A-HPCF-002 W Pipe 14 arg, 66 C,B (S1,S2), As No change 300A-HPCF-003-W Pipe 14 atg, 66 C.B (S1,52), As No change ABWR Makeup Water System (Condensate) SSAR Figure 9.2-4 CE Drawing 107E6014 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 Class Remarks Sheet 1 300A-MUWC-F100 Valve 14 atg, 66 C,B (51,S2), As No change 300A-MUWC-F101 Valve 14 atg, 66'C,B (S1,52), As No change 300A-MUWC 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 (S1,52), As No change 300A-MUUC-102 Pipe Static Hd, 66 C.B (51,52), As No change Condensate Storage Tank, 66 C,4D, Non-seismic No change RCIC turbine condensate piping to the suppression pool Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 250A-RCIC 037-S Pipe 28.8 aeg, 184 C,3B,As Was 10 atg 20A-RCIC-720-S Pipe 28.8 atg, 184 C,3B,As Was 10 atg 20A-RCIC-F722 Valve 28.8 atg, 184 C,3B,As Was 10 atg 20A RCIC-PIO12 P.Ind. 28.8 atg, 184 C,3B,As Was 10 atg 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

  • 250A-RCIC D015 Rup. Disk 28.8 atg, 184 C,3B,As Was 10 atg 20A RCIC-721-S Pipe 28.8 atg, 184 C,3B,As Was 10 arg 20A RCIC F723 Valve 28.8 atg, 184 C,3B,As Was 10 atg 20A RCIC-722-S Pipe 28.8 arg, 184 C,3B,As Was 10 arg ,

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

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

    • 25A-RCIC 051-S Pipe 28.8 atg, 184 C,3B,As Was 10 atg
    • 25A RCIC-F051 Valve 28.8 arg, 184 C,3B,As Was 10 arg
    • 25A RCIC D012 Strainer 28.8 atg, 184 C,3B,As Was 10 atg
    • 25A RCIC-D013 S. Trap 28.8 atg, 184 C,3B.As Was 10 arg
    • 25A RCIC-F052 Valve 28.8 atg, 184 C,3B.As Was 10 atg i Sheet 3 ** 25A RCIC-052-S Pipe 28.8 atg, 184 C,4D.As Was 10 atg
  • Vent via Rupture Disks.
    • RCIC Turbine Condensate Piping to the Barometric Condenser.

Page A - 20 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 20A-RCIC-053-S Pipe 28.8 atg, 184 Was 10 atg 20A-RCIC-F053 T. Valve 28.8 aeg, 184,C,3B,As C,3B,As Was 10 atg 350A-RCIC-F039 Valve 28.8 atg, 184 C,3B.As Was 10 atg 350A-RCIC-039-S Pipe 10 atg, 184 C,3B,As No change Sheet 1 Suppression Pool RCIC vacuum tank condensate piping to the suppression pool.

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 50A-RCIC-044-S Pipe 28.8 atg, 88 C,4D,As Was 3.16atg 50A-RCIC-067-S Pipe 28.8 atg, 88 C,4D As Was 3.16atg 50A-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 Sheet 1 50A-RCIC-F046 Check V. 28.8 atg, 104'C,3B,As Was 3.16atg 20A-RCIC-057-S Pipe 28.8 atg, 104 C,3B,As Was 3.16atg

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

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3

  • 20A-RCIC 063 S Pipe 28.8 atg, 184 C,3B,As Was 10 atg
    • 20A-RCIC 064-S Pipe 28.8 atg. 184 C,3B,As Was 10 atg Condensate Chamber 28.8 atg, 184 C,3B,As Was 10 atg w
  • RCIC Trip and Throttle Valve leakoffs are piped to Condensing Chamber.
    • RCIC Turbine Condensate Drain connects to the Condensing Chamber 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 arg, 184 C,4D.As Was 10 aeg Barometric Condenser 28.8 atg, 184 C,4D,As Was 7.7 atg
  • RCIC Trip and Throttle Valve Stem leakoff is piped to the Barometric
    • RCIC Turbine Governor Valve Stem is piped to the to Barometric Condenser.
      • Barometric Condenser pressure relief and piping.

Page A - 2 l 3.3 continued RCIC pump cooling water piping for pump and turbine lube oil coolers Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 50A RCIC Oll U Pipe 28.8 atg, 77 C,3B,As Was 8.8 atg 50A-RCIC-028-U Pipe 28.8 arg, 77 C,3B,As Was 8.8 atg 50A-RCIC-F030 Relief V.28.8 atg, 77 C,3B.As Was 8.8 atg 50A-RCIC-029-W Pipe 28.8 atg, 77 C,3B,As Was 8.8 atg 20A-RCIC-713-W Pipe 28.8 arg, 77 C,3B,As Was 8.8 atg 20A-RCIC-PX018 Press 28.8 atg, 77 C,3B,As Was 8.8 atg 50A-RCIC-Turb.LO Cooler 28.8 atg,- 77 C,3B,As Was 8.8 atg 50A-RCIC-Pump LO Cooler 28.8 atg, 77 C,3B,As Was 8.8 atg 15A RCIC-TX019 Temp.Pt. 28.8 atg. 77 C,3B.As Was 8.8 atg 20A-RCIC-714-W Pipe 28.8 atg, 77 C,3B.As Was 8.8 atg 20A-RCIC-F714 Valve 28.8 arg, 77,C,3B,As Was 8.8 atg 20A-RCIC-PX020 Press.Pt.28.8 atg, 77 C,3B,As Was 8.8 atg 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 W Pipe 28.8 atg, 77 C,3B.As Was 8.8 atg 15A-RCIC-015-W Pipe 28.8 arg, 77 C,3B,As Was 8.8 atg Sheet 3 Barometric Condenser 28.8 atg, 121 C,4D.As Was 7.7 atg RCIC vacuum tank and condensate pump piped to RCIC pump suction pipe.

Reference Components Press./ Temp./ Design / Seismic Class Remarks Sheet 3 RCIC Vacuum Tank 28.8 atg, 77 C,4D,As Was 7.7 atg RCIC Press. Switch H 28.8 atg. 121 C,4D,As Was 7.7 atg RCIC Level Switch H 28.8 atg. 121 C,4D,As Was 7.7 atg RCIC Level Switch L 28.8 atg, 121 C,4D.As Was 7.7 atg 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 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 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-U Pipe 28.8 atg, 88 C,3B,As Was 14 atg 50A-RCIC-030-U Pipe 28.8 arg, 88 C,3B,As Was 14 atg 50A-RCIC-F031 MO Valve 28.8 atg, 88 C,3B,As Was 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 1 20A-RCIC F034 T. Valve 28.8 aeg, 88 C,3B.As Was 14 atg

  • 50A-RCIC-017 Pipe connects with RCIC pump suction 200A RCIC-001 U Pipe on sheet 1 upgraded to 28.8 atg.

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Page A - l l 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 outside primary containment to VGL Radwaste Treatment System.

Reference Components PressureoRating Remarks Sh 2,1-11 25A RCIC-506-S Pipe 87.9 atg, 302 C,lA,As Reactor Pressure I-7 25A RCIC 507 S Pipe 87.9 atg, 302 C,lA,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 atg, 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 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 LCV Reactor Building sump which is vented to atmosphere, is through open funnel drains with low pressure piping to l the sump.

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Page A- 2 3

4. Control Rod Drive System j l

J 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 suction pipeline is a minimum 100 mm (4 inch) diameter except for a 150 mm 4 6 inch) diameter attachment to the Condensate Storage Tank. The CRD pumps run continuously while the reactor is at operating pressure, whier 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 Wate 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 Condensate, Feedwater and Condensate Air Extraction System has not been 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 remains closed, means that the pump discharge check valve remains closed as a given. Ilowever, 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. Ilowever, 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 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.

- 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.

- hiakeup Water (Condensate) System provides pump suction from and system return to the CST. The N1UWC System is discussed in Section 10, where it is explained how certain N1UWC upgrades were made that provide an open path to the CST. This line cannot be pressurized because of the open communication to the CST, and the CST is vented to atmosphere. There is no source to pressurize the N1UWC line because of closed pump discharge check valves in the CRD System's URS region.

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

Page A- 2.5 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.

- 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.

i Page A - 2 6 4.3 Upgraded Components A detailed listing of the components upgraded for the CRD System follows, including identification of those interfacing system components not requiring upgrade.

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CONTROLRODDRIVESYSTEM,SSAg)

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

CRD pump suction piping Condensate, Feedwater and Condensate Air Extraction System or Condensate Storage Tank of the Makeup Vater System (Condensate).

Reference Components Press./ Temp./ Design / Seismic Class Remarks See Note 1 100A-CFDWAO-Fxxx Valve 42 atg, 66 C.B,(S1,52),As No change 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,(S1,52),As No change 150A-CRD-002-S Pipe 28.8 atg, 20 C,4D,B Was 14 arg 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 No change 50A CRD-033-S Pipe 28.8 atg, 20,C,4D,B C,4D,B Was 14 atg 50A CRD 032 5 Pipe 28.8 atg. 20 C,4D,B Was 14 atg  !

20A-CRD-500-S Pipe 28.8 acg, 20 C,40,B Was 14 atg 20A-CRD-501-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-502-5 Pipe 28.8 atg, 20 C,4D,B Was 14 atg i 20A-CRD 503-S Pipe 28.8 atg, 20 C,4D,B Was 14 aeg l 25A-CRD-504-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg l 50A CRD-505-S Pipe 28.8 atg, 20 C,4D,B Was 14 at; )

50A-CRD-033-5 Pipe 28.8 atg, 20 C,4D,B Was 14 atg l 50A-CRD F019 Globe V 28.8 atg, 20 C,4D,B Was 14 atg j 50A-CRD-032 S Pipe 28.8 atg, 20 C,4D,B Was 14 aeg  ;

CRD-B001 Elec Her 28.8 arg, 20 C,4D,B Was 14 atg 25A-CRD-518-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 25A-CRD-F018 Safe.RV 28.8 atg, 20 C,4D,B Was 14 atg 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 20A-CRD 500-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-F500A Valve NC 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-501-S Pipe 28.8 arg, 20 C,4D,B Was 14 atg 20A-CRD-F501A Globe 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 Gate V 28.8 acg, 20 C,wD 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,40,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 aeg, 20 C,4D,B Was 14 atg 20A-CRD 503 S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A CRD-F501B Globe V 28.8 arg, 20 C,4D,B Was 14 atg 100A-CRD-006-S Pipe 28.8 aeg, 20 C,4D,B Was 14 atg

l Page A 2 ;

4.3 continued CRD pump suction piping (continued)

Reference Components Pressure / Temperature /Lesign/ Seismic Class-100A-CRD F002B Cate V 28.8 atg, 20 C,4D.B Was 14 atg 100A-CRD 007 S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 20A CRD-700-5 Pipe 28.8 arg, 20 C,4D,B Was 14 atg 20A-CRD-F700 Globe V 28.8 ats, 20 C,4D,B Was la arg i CRD-DPT001 Diff P T 28.8 atg, 20 C,4D,B Was 14 .stg '

20A CRD F701 Globe V 28.8 atg, 20 C,40,B Was 14 aeg 20A-CRD-701-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg 100A-CRD-F003A Gate V 28.8 atg 20 C,40,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 arg, 20 C,4D,B Was 14 atg l 25A-CRD F004A Safe.RV 28.8 atg, 20 C,4D,B Was 14 atg 20A-CRD-702-5 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 arg CRD-PI002A Press I 28.8 atg, 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 Was 14 atg i
  • 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 aeg. l
  • CRD F504A Globe V 28.8 arg, 20 C,4D,B Was 14 atg i
  • A CRD-506-S Pipe 28.8 atg, 20 C,4D,B Was 14 atg  ;
  • A-CRD-507 S Pipe 28.8 ats, 20 C,4D.B Was 14 atg i
  • CRD F505A Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD-F506A Globe V 28.8 arg, 20 C,4D,B- Was 14 atg 100A-CRD-F003B Gate V 28.8 atg, 20 C,40,8 Was 14 atg 100A CRD-010 S Pipe 28.8 atg, 20 C,4D,B Was 14 atg l 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 atg 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,B Was 14 atg CRD-PIOO2B Press I 28.8 atg,-20 C,4D,B Was 14 atg CRD-PT003B Press T 28.8 aeg 20 C,4D,B Was 14 atg '

CRD-C001B Pump 35 arg, 66*C,4C,B No change

  • A-CRD 509-S Pipe 28.8 atg, 20 C,40,B Was 14 atg I
  • CRD-F502B Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • CRD F503B Globe V 28.8 atg, 20 C,4D,B Was 14 atg
  • 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-511-S Pipe 28.8 atg, 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.

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Page A - 2. 8 4.3 continued CRD interface from pump discharge to the MWC System condensate storage tank Re fe rence Components Press./ Temp,/ Design / Seismic Class Re:urks 50A CRD 034 S Pipe 190 atg, 66 C,4C B No change 50A CRD-F022 Cate V 190 aeg, 66,C,4C,B No change 50A CRD-035 S Pipe 190 atg, 66 C,4C,B No change 50A CRD F023 Cate V 190 atg, 66 C,4C.B No change SOA MWC-xxx S Pipe 14 C,4C,B No change 50 A-MWC - Fxxx Cate V 14 atg, 66,C,4C B No change Condensate Storage Tank atg, 66,C 66 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 arg, 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 interf ace from pump discharge to the CW System Reference Components Press./ Temp./ Design / Seismic Class Remarks 20A-CRD 037-5 Pipe 190 atg, 66 C,4C,B No change 20A-CRD F026 Cate V 190 atg, 66 C,4C,B No change 20A CRD F027 Cate V 190 atg, 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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1 Page A 2.9 5.0 Standby Liauid Control System  ;

5.1 Upgrade Description 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 MUUP System interface is upgraded to URS design writeria. 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.

5.2 Downstream interfaces, i I

Other systems are listed below that interface with the SLC 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, MUWP 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.

MUVP 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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Page A 30  !

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 STANDBY LIQUID Sheet 1. (atg CONTR0g)

- Kg/cm  :

SYSTEM, SSAR Figure 9.3-1 GE Drawing 107E6016 Rev.

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

Reference Components Press./ Temp./ Design / Seismic Class Remarks SLC-CO0lA 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

  • 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 arg, . 66 C,2B.A No Change SLC-F003B Relief V.110 atg, 66 C,2B,A No Change SOA-SLC-SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-F002B Valve LO 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-SS Pipe 28.8 arg, 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 M0 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./ Tamp./ 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 aeg, 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 aeg SLC F026 Relief V. 28.8 aeg, 66 C,2B.A Was 14 atg 20A SLC SS Pipe 28.8 atg, 66 C,2B,A Was 14 atg 100A-SLC-SS Pipe 28.8 arg, 66 C,2B,A Was 14 atg
    • ATP is atmospheric pressure.

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5.3 continued SLC interface with NUVP for makeup and pressurization of suction piping from l tank. (Pressure higher than static head of SLC storage tank.)

Reference Components Press./ Temp./ Design / Seismic Class Remarks 80A-MUVP F163 Valve LO 14 atg, 66 No change 80A SLC SS Pipe 28.8 arg, 66,C,4D,C C,2B,C Vas 14 atg SLC F013 Check V. 28.8 aeg, 66 C,2B.C Vas 14 atg 80A-SLC SS Pipe 28.8 atg, 66 C 2B,C .Vas 14 aeg.

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 Vas 14 atg 20A-SLC SS Pipe 28.8 aeg, 66 C.2B,C Vas 14 atg 20A-SLC F020 Valve LO 28.8 aeg, 66 C,2B,A Vas 14 atg 20A-SLC-D002 RO 28.8 atg, 66 C,2B,A Vas 14 atg 20A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Vas 14 atg SLC storage tank interface with NUVF for purified makeup water.

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

SLC-F013 Check V. 28.8 atg, 66 C 2B,C Vas 14 ats l 80A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Vas 14 atg 25A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Vas 14 ats ,

25A-SLC-F015 Valve LC 28.8 atg, 66 C,2B,A Vas 14 atg  ;

20A-SLC-SS Pipe 28.8 atg, 66 C,2B,C Vas 14 atg i 20A SLC F505 Valve No 28.8 atg, 66 C.2B A Vas 14 atg l 25A SLC-SS Pipe 28.8 atg, 66 C,2B,C Vas 14 atg 25A-SLC F023 Valve LC 28.8 atg, 66 C,2B A Vas 14 atg 25A-SLC-SS Pipe 8.8 atg, 66 C,2B,C No change

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

l Page A- 3 2. '

6. Reactor Water Cleanun Svstern 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 .

- 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. .

7t e---*e- ** -<w--- -~-+-~ r' '-v *-si-- +' -' -- ---- + ~ - - --~--n -- - --- -- -- -

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1 Page A 33 6.3 Upgraded Components A detailed listing of the components upgraded for the CCW System follows, including identification of those interfacing system components not requiring l upgrade, )

REACTOR WATER CLEANUP SYSTEM, GSAR Figure 5.4-12 GE Drawing 107E5051 Rev.2P Sheets 1,2 and 3. ' 'tg - Kg/cm'). ,

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CUW System interface with Radvaste System Reference Components Press./ Temp./ Design / Seismic Class Remarks '

150A CUW F023 Valve MO 104 atg, 66 C,4C,B No change 150A-CUV-31 CS Pipe 28.8 atg, 66 C,4D C Was 10 atg 200A-LCV CS Pipe 10 atg, 66 C,4D,B No change 200A-LCW.CS Valve LO 10 atg, 66 C,4D,B No change No change 200A LCW-CS A0 Valve 10 atg. 66 C,4D,B

  • LCW 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- 3 4

7. Fuel Pool Cooling Cleanup- System 7.1 Upgrade Description The Fuel Pool Cooling Cleanup System interfaces with the RilR System at two locations that could possibly expose the FPC System to reactor pressure. One location is the discharge from the FPC to RilR in the line downstream from the skimmer surge tank; the other location is the RiiR 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 RilR. This new line has the gate valve locked open with the check ,

I 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  !

new valves have the FPC normal design pressure of 16 atg because the line j is an open path to the skimmer surge tank. All the piping between the FPC I valves, FPC-F029 and FPC-F031, and the RHR valves, RilR-F016B and RHR-F016C, was upgraded to the URS design pressure of 28.8 atg.

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

7.2 Downstream Interfaces The Fuel Pool Cooling Cleanup System has no further downstream system interfaces that could allow reactor pressure from RilR to proceed further than the FPC System. )

Page A 3 S~  ;

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. 1 FUELPOOLC00LINCANDCLEANUPSYSTEM,}SARFigure9.1-15,GEDrawing107E6042 Rev.1P, Sheets 1,2 and 3. (atg - Kg/cm ).

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

Reference Componeats Press./ Temp./Desien/

d Seismic Class Remarks 250A-RAR-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,33,A(S2)D No change ,

250A-FPC SS Pipe 16 aeg, 66 C,3B,A(S2)D No change i 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 ]

24 ,o JPC-SS Pipe 16 atg, 66 C,3B,A(52)D No change l cidA-FPC-F023 Check Valve 16 aeg, 66 C,3B,A(S2)D No change i 25CA-FN SS Pipe 16 atg, 66 C,3B,A(S2)D No change l REE TOR VELL No change 250A-FPC-SS Pipe 16 atg, 66 C,3B A(52)D No change 250A-FPC-F093 Valve LO 16 arg, 66 C,3B,A(52)D No change ,

80A SPCU F014 Valve MO 35 atg, 66 C,3B,A(S2)D No change l 80A-FPC SS Pipe 16 atg, 66 C,35,A(S2)D No change I 80A FPC-F091 Check Valve 16 atg, 66 #C,3B.A(S2)D No change SOA-FPC-SS Pipe 16 arg, 66 C,3B,A(S2)D No change 80A-FPC D011 RO 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 LO 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 I

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

Reference Components Press./ Temp./ Design / Seismic Class Remarks 300A-RHR-F016C Valve MO 28.8 atg, 182 C,3B As Was 14 aeg 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 atg 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 STORACE POOL 250A FPC SS Pipe 28.8 atg, 66 C,3B A(S2)D Was 14 atg
    • FILTER DEMINERALIZER No change 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 New Branch 250A FPC Fxxx Check Valve 16 atg, 66 C,3B,A(S2)D NewValve 1 50A FPC-SS Pipe 16 atg, 66 C,3B.A(S2)D New Branch 250A FPC-Fxxx Valve LO 16 atg, 66 C,3B,A(S2)D New Valve 250A-FPC-SS Pipe SWH atg, 66 C,3B.A(S2)D New Branch
      • SKIMMER SURCE TANK No change
  • FPC Valve F029 is open only for fuel pool cooling mode B (maximum heat 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.

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

i refueling and is selected for the required sensitivity. A relief valve  !

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

S.2 Downstream Interfaces 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 NBS and.RW(LCW, HCV, 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.

2P. Sheets 1 NUCLEARBOILERSYgTEM,SSARFigure5.1-3CEDrawing103E1791Rev.

& 5. (atg - Kg/cm ):

Refueling level transmitter piping I

Reference Components Press./ Temp./ Design / Seismic Class Remarks 1 20A-NBS-F708 Relief V 28.8 atg, 20 C,lA As Vas 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 drains including valve gland leakage, LCV and HCW funnel drains to the drywell equipment drain sump, i

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Page A 36 9.0 Reactor Recirculation System 9.1 Upgrade Description 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 possibly be exposed to reactor pressure. A description of the interface location and a statement of its applicability to ISLOCA is given.

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 arg.and utilizes RCW water for cooling the RIP motors. No upgrade is needed for the RCW System connecting piping designed to 14 aeg.

CRD System piping connects to ten RIP motor purge subsystems. Control Rod Drive System SSAR Figure 4.6-8, sheet 1 at C 2, the 20A-CRD 036 pipe and i 20A-CRD-F025 valve interface with the 20A-RRS-003A pipe connecting to the ten RIP motors. No upgrade is required because the design pressure for both the CRD and RRS is 190 aeg.  ;

RWS 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 1 Tank which is vented to the atmosphere. Another MUWP System interface is connected to a portable inflatable shaft seal pump and tank only during refueling or when the reactor is shut down for maintenance.

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

REACTOR RECIRCULATION SYSTFM j SSAR Figure 5.4-4, GE Drawing 107E5194 Rev. 1P, Sheets 1 & 2. (atg - Kg/cm );

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,3029C, 4A,As No change 15A-MWP-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 50A-MWP-F142 Check Valve 28.8atg,171 C, 3B As Was 14 atg L 50A- MWP - 184 Pipe 28.8atg,171 C,-3B,As Was 14 atg 50A- MWP- F141 Valves NC 28.8atg,171 C, 3B As Was 14 atg 50A MUWP-183 Pipe 14 atg, 66 C, 4D,C No change 80A-MUWP 181 Pipe 14 atg. 66 C, 4D,C No change 80A- MWP- F140 Valve LO 14 atg, 66 C, 4D.C No change 12 5 A -MWP- 101 Pipe 14 atg, 66 C, 4D,C No change 125 A-MWP - F101 Valve LO 14 atg, 66 C, 4D,C No change 20A-MWP - 602 Pipe 14 atg, 66,C, 4D,C No change 20A-MUWP F602 Valve NC 14 atg, 66 C, 4D,C No change 20A MWP 601 Pipe 14 atg, 66 C, 4D,C No change 20A-MUWP F601 Valve NC 14 atg, 66 C, 4D,C No change 20A-MWP- FQ102 Flow Integr.14 atg, 66,C, 4D,C No change 20A-MUWP-801 Pipe 14 arg, 66 C, 4D C No change 20A -MWP - F801 Valve NC 14 atg, 66 C, 4D C No change 20A-MWP - 800 Pipe 14 atg, 66 C, 4D,C No change 20A-MWP F800 Valve NC 14 arg, 66 C, 4D,C No change 20A- M P PX101 Press Pt. 14 atg, 66 C, 4D C No change 20A-MWP - 600 Pipe 14 atg, 66 C, 4D,C No change 20A-MWP- 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 MWP F102 Valve NC 14 atg, 66 C, 4D,C No change 150A-MWP - xxx Pipe 14 atg, 66 C, 4D,C No change I SOA-MWP -xxx Pipe 14 atg, 66 C, 4D.C No change SOA RRS Fxxx Check Valve 14 atg, 66 C, 4D,C No change Condensate Storage Tank, 66 C, 4D,Non-seismic No change

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Page A shO 10.0 Makeue Water System condensate 10,1 Upgrade Description The MU'.'C 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 site of the Condensate Storage Tank of the MUWC System makes it impractical to upgrade. Instead valves are changed to_ lock open type to create a clear path from the URS boudary to the Condensate Storage Tank which is vented to atmosphere.

10.2 Downstream Interfaces 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 design pressure because the maximum static head is 1.62 aeg. 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, CRD makeup and discharge, and KUWP System are not upgraded due to the j 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. ,

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All MUUC 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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10.3 Upgraded Components i A detailed listing of the components upgraded for the MWC System follows, including identification of those interfacing system components not requiring upgrade.

MAKEUP WATER SYSTEM (CQNDENSATE) SSAR Figure 9.2-4 CE Drawing 107E6014 Rev. 1P.

Sheets 1. (atg - Kg/cm'):

HPCF Subsystem B keep fill line interface.

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

omponents Sheet 1

50A-HPCF-F015B Check V.110 arg, 100 C,3B.As No change i 50A-HPCF-020 Pipe 110 atg, 100 C,3B As No change l HPCF Subsystem C keep fill line interface.

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

  • 50 A - MWC- 13 8 Pipe 14 arg, 66 C,4D,B No change 25A-HPCF-F013C Valve LO 14 aeg, 100 C,3B,As No change 25A-HPCF-D006C R0 14 arg, 100 C,3B.As No change ,

25A-HPCF 119 Pipe 14 atg, 100 C,3B,As No change i 50A-HPCF-F016C Valve la arg, 100 C,.3B,As No change l' 50A-HPCF F014C Check V.110 atg, 100 C,3B.As No change 50A-HPCF F015C Check V.110 atg, 100 C,3B.As No change j 50A HPCF 120 Pipe 110 arg, 100 C,3B.As No change l

MUVC System interface with HPCF System i Reference Components Press./ Temp./ Design / Seismic Class Remarks 300A HPCF-001 SS Pipe l' arg, 66 C,B(S1,S2) No change I 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 i Sheet 1 300A-MWC-F100 Valve LO 14 arg, 66 C,4D,B No change 300A-MWC-F101 Valve LO 14 atg, 66 C,4D,B No change 300A-MUVC-F102 Valve LO la atg, 66 C,4D,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,B No change RRR Subsystem A flushing line interface at branch discharging to feedwater.

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

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

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

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

Sheet 1

  • 100A -E"JC- 13 3 Pipe 14 arg, 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-ENC- 13 7 Pipe 14 atg, 66 C,4D,B No change Sheet 3 100A-RER F032B Valve 35 atg, 182 C,3B,As No change 100A-RHR -132 Pipe 35 atg, 182 C,3B,As No change 100A-RER F033B Check V. 35 atg, 182 C,3B,As No change RHR Subsystem B flushing line ine =.fsce at suction of shutdown branch from RPV.

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

  • 100A-E'WC - 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, i82 C,3B,As Was 14 atg RHR Subsystem C flushing line interface at branch discharge to feedvater.

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

  • louA-MirJC-140 Pipe 14 arg, 66 C,4D,B No change 100A-RHR -F032C Valve 35 atg. 182 C,3B,As No change 100A RER -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, i

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Page A - 4 3  !

10.3 continued MWC System changes and upgrades.

Reference Components Press,/ Temp./ Design / Seismic Class Remarks Sheet 1 150A-MUWC-F131 valve LO 14 atg, 66 C,4D.B No change 2 50A-MWC- F111 Valve LO 14 atg, 66 C,4D,B No change 2 50A-MWC-F110 Valve LO 14 atg, 66 C,4D B No change

    • 2 50 A - MWC - 110 Pipe 14 atg, 66 C,4D,B No change
    • Interf ace with new MWC System pump minimum flow bypass pipe with check valve and to service valves connecting to Condensate Storage Tank.

MUWC System interface with MWP Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-WUMP-101 SS Pipe 14 atg, 66 C,4D.C No change 150A-WUMP-Fxxx SS Valve LO 14 atg, 66 C,4D,C No change 150A-WUMP-Fxxx SS Check V. 14 atg, 66 C,4D,C No change Condensate Storage Tank MUWC interface with the CRD System pump suction piping.

Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A CRD-002-S Pipe 28.8 atg, 20 C,4D,B Was 14 at; ,

Sheet 1 150A- S C-Fxxx LO Valve 14 atg, 66 C,4D,B Lock Open 150A-MWC- xxx Pipe 14 atg, 66 C,4D,B No change 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 15r'A-MWC Fxxx LO Valve 14 atg, 66 C,4D,B Lock Open 150A-MUWC-xxx Pipe Static Hd, 66 C,4D,B No change Condensate Storage Tank, 66 C,4D, Non seismic No change MUWC 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 50A-CRD-F023 Valve 190 atg, 20 C,4C,B No change 66 C,4D,B Lock Open Sheet 1 50A MWC-F103 Valve 14 atg, Pipe Static Hd, 66 C,4D,B No change 50A-MWC xxx Condensate Storage Tank, 66 C,4D, Non-seismic No change

i Page A 4fdb 11.0 Makeup Water System Purifed 1

11.1 Upgrade Description The KUWP System is not upgraded due to the extensive nature of the piping distribution, but instead all valves between the interface and the Condensate Storage Tank are changed to the lock open type. This provides a clear 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 criteria.

11.2 Downstream Interfaces other systems are listed below that interface with the MUWP System and could l possibly be exposed to reactor pressure. A description of the interface-  !

location and a statement of its applicability to ISLOCA is given.

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

S 2P, MAKEUP Sheets 1,2 VATER and 3- SYSTEM (PURIFIED)2)SAR (atg - Kg/cm . Figure 9.2-5 CE Drawing 107E5111 Rev.

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

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

80A-SLC -F013 Check Valve 28.8 atg 66 C, 4D,C No change 80A-MUWP-F019 Valve LO 14 atg, 66 C, 4D.C No change 80A-MUUP F163 Valve LO la atg, 66 C, 4D C No change 80A- M P-217 Pipe 14 atg, 66 C, 4D.C. No change 80A-MUWP-214 Pipe 14 atg, 66 C, 4D C No change 80A-MUWP F162 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-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 atg, 66 C, 4D.C No change 20A-MUUP-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-MUUP-F800 Valve NC 14 atg, 66 C, 4D C No chanSe 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 LO 14 atg, 66 C, 4D.C No change 125A-MUWP-102 Pipe 14 atg, 66 C, 4D.C No change 125A-MWP 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-Fxxx Check Valve 14 atg, 66 C, 4D C No change 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 - 4 /o 11.3 continued MUVP System interface with RRS for Reactor Internal Pump (RIP) casing makeup water.

Reference ~omponents Press../ Temp./ Design / Seismic Class Remarks Sheet 1 15A-RRS-202A-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-MWP-189 198 Pipes 28.8atg, 66,C, 4D,C Vas 14 atg 50A-MWP 185 Pipe 28.8atg, 66,C, 4D C Was 14 atg 50A-MWP-F142 Check Valve 28.8atg,171,C, 3B,As Was 14 atg 50A-MWP - 184 Pipe 28.8atg,171,C, 3B,As Was 14 atg 50A-MWP - F141 Valves NC 28.8atg,171,C, 3B,As Was 14 atg 50A-MWP - 183 Pipe 14 atg, 66 C, 4D,C No change 80A-MWP - 181 Pipe 14 atg, 66 C, 4D,C No change-80A-MWP- F140 Valve LO 14 atg, 66 C, 4D.C No change 125A-MWP- 101 Pipe 14 atg. 66 C, 4D,C No change 125A-MWP- F101 Valve LO 14 atg, 66 C, 4D,C No change 2 0A-ML"='P- 6 02 Pipe 14 atg, 66 C, 4D C No change 20A-MWP- F602 Valve NC 14 atg, 66 C, 4D,C No change 20A-MWP- 601 Pipe 14 atg, 66 C, 4D,C No change 20A-MWP F601 Valve NC 14 atg. 66 C, 4D C No change 20A-MW?-FQ102 Flow Integr.14 atg, 66 C, 4D,C No change 20A-MWP- 801 Pipe 14 atg, 66 C, 4D.C No change 20A-M'JVP- F801 Valve NC 14 atg, 66 C, 4D C No change 20A-MWP - 800 Pipe 14 atg, 66 C, 4D,C No change 20A-MWP- F800 Valve NC 14 atg, 66 C, 4D,C No change 20A-MWP- PX101 Press. Pt. 14 atg, 66 C, 4D,C No change 20A-MWP- 600 Pipe 14 atg, 66 C, 4D,C No change 20A-MWP- F600 Valve NC 14 arg, 66 C, 4D,C No change 20 A-MWP- F100 Valve LO 14 atg, 66 C, 4D,C No change 125A- M P-102 Pipe 14 atg, 66 C, 4D C No change 12 5A-MWP-F102 Valve NC 14 atg, 66 C, 4D,C No change 150A-MWP- xxx Pipe 14 -atg, 66 C, 4D,C No change 150A-MWP-xxx Pipe 14 atg, 66 C, 4D,C No change 150A-RRS-Fxxx Check V nve 14 atg, 66 C, 4D,C No change 150A-MWP xxx Pipe Static Head, 66 C, 4D C No change Condensate Storage Tank, 66 C, 4D,Non-seismic No change

Page A dh7 12.0 Radweste System 12.1 Upgrade Description The Radwaste System LCW and HCW inlet piping header inects to each interf acing system' at a valve. The header is not upgr. ded 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 A0 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 l 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 HCU collector tanks and associated piping are all at atmospheric pressure since the HVAC System tank exhaust vents each rank.

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Page A 48 12.3 Upgraded Components detailed listing of the components upgraded for the RW System follows,

_ucluding identification of those interfacing system components not requiring upgrade.

i RADVASTE SYSTEM SSAR Figure 11.2-2 CE Drawing 103E1634 Rev. 1P, Sheets 1, 3 and 2

7. (atg - Kg/cm ).

RV LCV Subsystem interface with the RRR System Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 129 Pipe 35 atg, 66 C,3B As No change 150A-LCW-F006 Valve 28.8 atg, 66 C,4D,B Was 10 aeg 150A-LCW-CS Pipe 10 atg, 66 C,4D B No change 200A-LCW-CS Pipe 10 atg, 66 C,4D,B No change 200A-LCV-CS Valve LO 10 atg, 66 C,4D.B No change 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 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
  • Each LCW collector tank has HVAC tank vent system exhausting tank air through filter to RW Stack.

RW HCV Subsystem A interface with the RER System Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 018 Pipe 28.8 aeg, 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 atg, 66 C,4D B No change 150A-HCW-SS Valve LO 10 atg, 66 C,4D.B No chant.

150A-HCW-F003A Valve A0 10 atg, 66 C,4D,B No change

  • HCW Collector Tank A 0 arg, 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.

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Page A - 4 9 12.3 continued RW HCW Subsystem B interface with the RER 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 150A-HCW-SS Pipe 10 atg, 66 C,4D,3 No change 150A-HCW-SS Valve LO 10 atg, 66 C,4D.B No change 150A-HCV-F003A Valve A0 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 arg, 66,C,4D,B No change
  • HCW Collector Tank B 0 atg, 66 C,4D,B No change
  • Each HCW collector t.ank has HVAC tank vent system exhausting tank air through filter to RW Stack.

RW HCV Subsystem C interface with the RHR Syscem -

Reference Components Press./ Temp./ Design / Seismic Class Remarks 150A-RHR 225 Pipe 28.8 arg, 182 C,3B,As Was 14 atg 150A-RHR F026C Valve 28.8 atg, 182 C,3B.As Was 14 atg 150A-HCV SS- Valve 28.8 aeg, 182 C,3B,As Was 10 atg 150A-HCV-SS Pipe 10 atg, 66 C,4D,B No change 150A-HCV-SS Valve LO 10 atg, 66 C,4D,B No change 150A-HCV-F003A Valve A0 10 atg, 66 C,4D,B No change

  • HCW Collector Tank A 0 atg, 66 C,4D,B No change 150A-HCV-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.

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13. Condensate' and Feedwater (CFS) System l 13.1 Upgrade Description The CFS System provides high pressure feedwater to the reactor, and all of ,

the system is designed for high pressure except the condensate pumps suction. The high pressure design includes the condensate polishing .

1 (hollow fiber filters and demineralizers) units. The transition to low pressure occurs from the condensate suction into the LP condenser shell '

(hotwell). The hotwell is a low pressure sink. The last closed valve in the path from the reactor is the condensate pumps discharge check valve. The piping to the condensate pumps suction can remain below the URS design pressure because it connects to the low pressure sink hotwell. The maintenance block valves in the condensate pump suction lines were upgraded to a LOCK OPEN status.

13.2 Downstream Interfaces l

None 13.3 Upgraded Components The maintenance block valves in the condensate pump suction lines were l upgraded to a LOCK OPEN status.

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Page A- 51

14. Sampling (S AM) System 14.1 Upgrade Description The Sampling System receives water from several of the above systems, and an analysis, as presented below, resulted in not requiring any pressure upgrades. The following interfaces include all of the potential links of SAM to the reactor pressure, and since none of the individual portions need upgrading, SAM as a whole was not upgraded.
1. RilR Interface: Samples can be taken downstream of the RHR heat exchanger, which is from a pipeline with a design pressure of 35 aig. The SAM System is designed for pressures at least as great as the point in the interfacing system where the sample is obtained. Therefore, the URS design pressure of 28 arg is exceeded and no upgrade required for this portion of SAM.
2. SLC Interface: Samples can be taken from the SLC main tank, which is one of the low pressure sinks. Therefore, no upgrade is required for this portion of SAM.
3. CUW Interface: Samples can be taken from the inlet and outlet of the filter demineralizer units, which are designed for full reactor pressure. The SAM System is designed for pressures at least as great as the point in the interfacing system where the sample is obtained. Therefore, the URS design pressure of 28 atg is exceeded and no upgrade required for this portion of SAM.

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4. FPC Interface: Samples can be taken from the inlet to the filter demineralizer units and from the heat exchangers outlet. The l pipeline sample points have a design pressure of 16 alg; I however, this region of the FPC System did not need upgrading l to the URS design pressure. Therefore, no upgrade is required for this portion of SAM.
5. NIIS Interface: Samples can be taken from the points within the NBS which are designed for full reactor pressure. The SAM System is designed for pressures at least as great as the point in the interfacing system where the sample is obtained. Therefore, the URS design pressure of 28 arg is exceeded and no upgrade required for this portion of SAM.

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6. h1UWP Interface: Samples can be taken from a point within the  !

A1UWP System located in the turbine building that did not need i upgrading to the URS design pressure. Therefore, no upgrade is l required for this portion of SAN 1. I

7. Rad Waste Interface: Samples can be taken from the LCW and-IICW collector tanks, which are low pressure' sinks. Therefore, ' no upgrade is required for this portion of SAh!.

14.2 Downstream Interfaces None 14.3 Upgraded Components None

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