ML17255A673

Rev 1 to Procedure EWR 2606, Design Criteria Ginna Station: Post-Accident Sampling Sys Implementation.

ML17255A673
Person / Time
Site:	Ginna
Issue date:	07/20/1982
From:	Robert Davis, Mambretti C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17255A675	List: ML17255A673 ML17255A678 ML17255A679 ML17255A680 ML17309A324
References
RTR-NUREG-0737, RTR-NUREG-737 EWR-2606, NUDOCS 8402100252
Download: ML17255A673 (38)

Text

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HVORifATII Ply Design Criteria Ginna Station Post Accident Sampling System Implementation Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 EWR 2606 Revision 1 July 19, 1982 Prepared by: -lP" C DATE Nuclear gineer Reviewed by: TM DATE Quality Assurance Approved by:

-2o-8 Manager, Nucle Engzneexxng OATK Page i DC13J 8402100252 840206>>,),->>

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0 19 0 20 0 Design Criteria Revision 1

EWR 2606 Page ii l)etc 7/19/82

1.0 Summar Descri tion of the Desi n 1.1.1 As.a result of the inability at Three Mile Island to rapidly obtain reactor coolant samples to ascertain the extent of core damage, the NRC is requiring that all licensees evaluate and, if required, upgrade their plants to enable acquisition of appropriate expeditious samples after an accident. Ability to assess the conditions of the core early in an accident can result in taking remedial actions which could limit or even preclude core damage.

1.1.2 The sampling system at Ginna has been evaluated to be marginally adequate for post-accident conditions and consequently remedial modifications are planned.

1.1.3 '

new Post Accident Sampling System (PASS) will be installed which will enable the station to obtain and analyze reactor coolant, containment air, and containment sump samples within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of the decision to sample.

The PASS will also enable sampling of these streams during normal operation.

1.1.4 In-line chemical instrumentation will be provided in a new Liquid and Gas Sample Panel (LGSP) which will remotely determine important chemical parameters of reactor coolant, containment air, and containment sump.

1.1.5 The LGSP will enable acquisition of diluted and undiluted grab samples of both xeactor coolant and containment air for isotopic analysis in the existing counting lab.

1.1.6 The LGSP will be controlled from a new Electric Control Panel (ECP) and Instrument Panel (IP) to be located in the Hot Shop. Remotely operated valves and instruments external to the LGSP will also be controlled from the ECP. The LGSP will be located on the 253'-6" elevation of the controlled portion of the Intermediate Building.

j 1.1.7 The PASS is designed to meet the requirements of NUREG 0578 and NUREG 0737 (Section II.B.3). Furthermore, the PASS installation at Ginna is to have adequate 'provisions to allow compliance with the containment sump sampling, pH and oxygen analysis requirements now invoked by Regulatory Guide 1.97 (Rev. 2) dated December 1980.

1.1.8 Sample lines associated with the PASS will be installed in such a manner that the post accident vital dose criteria will be met for sampling and access to areas.

Design Criteria Revision 0 Page 1 EWR 2606 Date 11/23/81

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1.1.9 The necessary modifications are shown schematically on the attached Figure 1. The general arrangement of equipment is shown on Figure 2.

1. 1.'10 Steam generator blowdown sample lines from containment penetrations 206 and 207 to the existing sample room are to be rerouted (for ALARA considerations) using the same design criteria discussed herein.: These two lines are being rerouted to reduce operator exposure for routine sampling and are not required as a part of NUREG-0737 or Reg. Guide 1.97 (Rev. 2).

H 1.2 Functions 1.2.1 The new PASS functional requirements are given in the attached Tab3.e 1. The PASS sample source design para-meters are given in the attached Table 2. The PASS major component design parameters are given in Table 3.

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1.2.2 The new PASS shall provide for disposition of the sample waste to a new waste collection system during post-accident operation. The new Waste Tank and Waste Transfer Pump wil3. collect sample waste for return to the containment sump during post accident conditions.

1.2.3 During normal operation, valving is provided to direct the sampling waste to the volume control tank or to 1.2.4 tQ!. I f: i r y, plant liquid radwaste system.

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The basic functions of the PASS can be performed while

~,t r l >4 ~ '> rr the operator is in a shielded, remote location from the LGSP. The LGSP.is designed with integral lead shot shielding which will minimize the dose rate to adjacent areas of the intermediate, auxiliary, and service

$ r buildings.

r 1.2.5 Liquid and Gas Sample Pane3. (LGSP) 'I 1

1.2.5.1 The LGSP wi3.1 provide the functions given in the attached Table l.

1.2.5.2 The specific analytical parameters measured by the LGSP instrumentation are given in the attached Table 3 (Item

1) ~ I' rC 1.2.5.3 All PASS analytical and sample components which contain

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post accident liquids and gases are mounted in the LGSP behind a shield structure.

>" C 1.2.5.4. The rear of the LGSP is enclosed and,has provisions for exhausting to ithe station HVAC system'o-prevent airborne contamination in the event of component leakage.

Design Criteria Revision.

Page 2 EWR'i 2606 Date 7/19/82

1.2.5.5 'he LGSP has an integral internal spray system for washdown and decontamination prior to maintenance.

1.2.5.6 The LGSP contains a means to strip reactor coolant of dissolved gases for subsequent analysis.

1.2.5.7 The LGSP contains a means to dilute reactor coolant, containment air, and containment sump samples by a factor of approximately 1000. The diluted samples can be withdrawn by a shielded syringe via port connections located on the front of the LGSP. The LGSP contains a means to obtain an undiluted reactor coolant gas and liquid grab sample during normal operation.

A means is'rovided to obtain a undiluted containment air sample.

1.2.5.8 The motive force for reactor coolant samples to the LGSP is provided by primary coolant pressure.

1.2.5.9 The motive force for obtaining the containment sump sample is from a new containment sump sampling pump located in Containment Sump 'A'.

1.2.5.10 The motive force for obtaining the containment air sample is from a vacuum pump contained within the LGSP.

1.2.6 PASS Coolers 1.2.6.1 A PASS cooler will be provided for each reactor coolant and containment sump sample, refer to Table l. A separate cooler for each liquid sample line will ensure sample representativeness, and minimize the liklihood of sample cross-contamination.

1.2.6.2 The coolers (4 required) will be shell and tube type.

Sample fluid will circulate through the tube side.

1.2.6.3 The coolers will be mounted on a rack which will be located directly behind the LGSP. The LGSP integral shielding will thus shield the coolers from adjacent areas.

1.2.6.4 The cooler rack can be isolated for maintenance.

1.2.6.5 The cooler design parameters are given in the attached Table 3 (Item 2).

1.2.7 PASS Waste Tank 1.2.7.1 A PASS Waste Tank is provided to collect sample waste from purge, flush, and analysis operations.

Design Criteria Revision Page 3 EWR 2606 Date 7/19/82

1.2.7.2 The PASS Waste Tank is sized to contain the fluid generated while purging any sample inlet line for a minimum of three line volumes during a single sample opexation.

1.2.7.3 The PASS Waste Tank is provided with two means to transfex fluid contents in the event of Waste Tank transfer pump failure". The primary method is a transfer pump; the backup method is by nitrogen displacement 1

1.2.7.4 The PASS Waste Tank is provided with an evacuating compressor to remove gases which will evolve from reactox coolant samples to vent the tank duxing sampling back to containment.

1.2.7.5 The tank is protected fxom over pressurization by a rupture disc. A rupture disc is selected for leak tightness and to assure adequate response to rapid pressure excuxsions as would occur with a hydxogen detonation. During operation the rupture disc discharge in routed to the Intermediate Building HVAC System.

t 1.2.7.6 The PASS Waste Tank is to be located within the pad which suppoxts the LGSP. The tank will be situated below the drain connection on the LGSP to assure gravity drainage when necessary.. The 'pad and LGSP will thus pxovide shielding of the tank contents.

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1. 2.7.7 The design parametexs for the PASS Waste Tank are given 7 h in the attached Table 3 (Item 3).

ht 1.2.8 PASS Waste Transfer Pump 1.2.8.1 A new PASS Waste Transfer Pump will pxovide the motive force to empty the PASS Waste Tank of its contents during typical operation. For post accident operation the Waste Transfer Pump will dischaxge to the Containment

'A'ump. This will be accomplished by pumping in the

'reverse-to-normal flow direction through the Containment

'A'ump Pump discharge line (Penetxation No. 107).

1.2.8.2 The PASS Waste Transfer Pump will also have the capability to discharge to the plant liquid radwaste system when used during noxmal opexation.

1.2.8.3 The design parameters fox the PASS Waste Txansfer Pump are given in the attached Table 3 (Item 4).

l. 2.9 PASS Waste Tank Evacuating Compressor 1.2.9.1 A new PASS Waste Tank Evacuating Compressor.is=pxovided to maintain the PASS Waste Tank a'"atmospheric pressure to ensure adequate gravity draina'ge from the LGSP. 1 Design Criteria Revision Page 4 EWR 2606 Date 7/1'9'2

P 1.2.9.2 The evacuating compressor will discharge to the con-tainment during post accident operation since the process stream could contain post accident gases which evolve from the reactor coolant.

1.2.9.3 During normal, non-post accident operation, the tank is vented to the Intermediate Building HVAC system via the LGSP plenum.

1.3 Performance Re uirements 1.3.1 The new PASS shall be capable of extracting and analyzing the samples indicated in the attached Table 1. The samples must, be obtained and analyzed within three hours of the decision to sample.

1.3.2 The analytical parameters and ranges of the instru-mentation for in-line measurement are given in Table 3 (Item 1) . ~

1.3.3 The PASS shall be capable of obtaining diluted (Approx.

1000:1) post accident reactor coolant, containment sump, and containment air samples for isotopic analysis or off-site shipment.

1.3.4 During normal operation the PASS can be used to obtain undiluted reactor coolant dissolved gas grab samples from a gas sample bomb.

1.3.5 The PASS shall have the ability to extract the sample in Table 1 while minimizing operator exposure. This shall be accomplished by a combination of shielding, remote/automatic operation, and by minimizing the time necessary to perform the sampling procedure.

The total dose that a single operator can receive while obtaining and analyzing a single sample is 5 Rem whole body and 75 Rem to the extremities.

1.3.7 The dose to the operator must include:

1. High radiation levels from sample lines

2. High radiation levels from other equipment which may be post accident sources including containment shine.

3. Exposure while entering and exiting the sample area 1.3.8 The PA~S shall be capable of operating during normal and post accident conditions (pressure, temperature, Design Criteria Revision Page 5 EWR 2606 Date 7/19/82

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.3.9 and radiation) in the reactor coolant system and the containment. atmosphere.

V The LGSP will contain pxovisions for connection to a portable chloride analyzer in the event a post accident chloride analysis is requixed. These connections will also be used to obtain undiluted liquid samples during normal operation.

1.4 Contxol 1.4.1 Control and readout for the PASS shall be from a new Electric Control Panel (ECP) and Instrument Panel (IP) located in the Hot Shop.

1.4.2 The PASS does not xequire tie-in to the stations safety buses. A reliable souxce of normal AC power can be utilized.

1.4.3 The PASS ECP will contain controls for the remote operation of the LGSP.

1.4.4 The PASS IP will contain the readout devices for the in-line instrumentation located in the LGSP.

1.4. 5 Calibration solutions and gases for the in-line instxu-mentation in the I

LGSP will be-controlled from the IP.

P l 1.4.6 Components of PASS which are external to the LGSP will also be controlled. from the ECP. This includes the Waste Tank and Transfer Pump controls, the Evacuating Compressor controls, tie-in. valve controls.

gl 4y"ap 1.4.7 Controls for the existing sample line conta'inment isolation valv'es associated with the PASS operation will be from existing control stations, e.g., the main control room, or the primary sample room panel.

Modes of Operation 1.5 1.5.1 lj The operation of the PASS is remote, manual.

'II The system will be designed to obtain and analyze a sample within three hours of the decision to obtain a sample.

ll 1.5.2 The PASS may also be used by plant chemistry personnel during normal operation to perform routine chemical analysis of reactor coolant and containment.'atmosphere samples.

1.5.3 Interlocks will be pxovided to prevent. post accident sample solutions from being routed to the station liquid radwaste system ox volume control tank.

Design Criteria Revision Page 6 EWR 2606 Date: 7/19/82'

1' 2.0 Refexenced Documents The following documents are referenced herein. Their applicability ox xequirements fox design are as specified in this critexia document.

2.1 USNRC Regulatory Guide 2.1.1 No. 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant. Accident for Pressurized Watex Reactors, Rev. 2, 1974.

2.1.2 No. 1.21, Measuring, Evaluating and Reporting Radio-activity in. Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Watex-Cooled Nuclear Power Plants, Rev. 1, 1974.

2.1.3 No. 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Rev. 3, 1976.

2.1.4 No. l. 97, Instrumentation fox Light-Watex-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident, Rev. 2, Decembex 1980.

2.1.5 NUREG-0578, TMI-2 Lessons Learned Task Force Status Report and Shoxt Term Commendations, 1979.

2.1.6 NUREG-0737, Clarification of TMI Action Plan Requirements, November, 1980.

2.1.7 No. 1.29, "Seismic Design Classification," Rev. 3, September 1978.

2.1.8 No. 1.48, '"Design Limits and Loading Combinations fox Seismic Category I Fluid System Components," May 1973.

2.1.9 No. 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plans, " Rev. 1, December 1973.

2.1.10 No. 1.61, "Damping Values for Seismic Design of Nucleax Power Plants," October 1973.

2.1.11 No. 1.92, "Combining Modal Responses and Spatial Components in Seismic'esponse Analysis, "Rev. 1, Februaxy, 1976.

2.1.12 No. 1.100, "Seismic Qualification of Electric Equipment fox Nuclear Power Plants, Rev. 1, August 1977.

American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code 1980 Edition with Addenda through Winter 1980.

Design Cxitexia Revision 1 Page 7 EWR 2606 Date 7/19/82

Section III Nuclear Power Plant ComponentsSection V Nondestructive Testing Section VXII Pressure Vessels, Division 1 6 2 Section XX Nelding and Brazing Qualifications 2.3 American National Standards Institute (ANSI)

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2.3.1 ANSX N45.2.1 1973, "Cleaning of Fluid Systems and Associated Components During Construction Phase of Nucleax'ower Plants".

2.3.2 ANSI N45.2.2 1972, "Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants".

2.3.3. ANSI N45.2.3 1973, "Housekeeping During the Construction Phase of Nuclear Power Plants".

2.3.4 ANSI N45.2.8 1975, "Supplemental Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants".

2.3.5 ANSX N13. 1 2.3.6 ANSI 18. 2 f

2.3.7 B16.5 Steel Pipe Flanges and Flanged Fittings, 1980.

2.3.8 B31.1 Power Piping, 1980.

2.4 Institute of'lectrical and Electronic Engineers (IEEE) 2.4.1 IEEE-323-1974, "Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations".

2.4.2 IEEE-344, Recommended Practice for Seismic Qualifi-cation of Class 1E Equipment for Nuclear Power Operating Stations, 1975.

2.4.3 ZEEE-383, Standard for Type Test of Class lE Electrical Cables, Field Splices and Connections fox Nuclear Power Opexating Stations, 1974.

2.4.4 IEEE-384, Standard Criteria for Independence of Class 1E Equipment and Circuits, 1977.

2.5 American Institute of Steel Construction (AISC)

"Specification-for the Design, Fabrication and Erection of Structural Steel for Buildings," November 1, 1978.

Design Criteria Revision P'age 87 ENR 2606 Date 7/19/82

2.6 American Concrete Institute (ACI)

ACI Standard 318-77, Building Code Requirements for Reinforced Concrete, 1977 Edition.

2'. 7 Tubular Exchange Manufacturer's Association (TEMA) >

TEMA Standards, 1978 Edition.

2.8 Rochester Gas 6 Electric Fire Protection Evaluation, Gilbert Associates, Inc. Report 1936, March 1977.

2.9 American Welding Society (AWS) Dl.l, Structural Welding Code, 1981.

2.10 National Electric Code, 1978.

2.11 Final Safety Analysis Report for the Ginna Station 2.12 Design Review of Plant Shielding and Environmental Qualification'of Equipment for Spaces/Systems which may be used in Post Accident Operations Outside Containment at R.E. Ginna Nuclear Power Plant, December, 1979.

2.13 NRC Fire Protection Safety Evaluation Report for Ginna Station and supplements, February 14, 1979, Docket 5 0-244.

3.0 Seismic Cate or 3.1 The new PASS is classified non-seismic except for the component, cooling water and V.C.T. purge line tie-ins which are seismic Category I. The isolation relays to obtain the position'ndication for existing reactor coolant sample line containment isolation valves will be housed in seismic Category I supported electrical

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enclosure.'.2 All equipment. supports for the PASS will be analyzed for seismic loadings to preclude gross failure which could damage nearby safety related components. The Electric Control Panel (ECP) and Instrument Panel (IP) will no't be analyzed the for seismic loadings since they are to be located in Hot Shop.

3.3 The existing primary sample system is defined as non-seismic in the Ginna FSAR (

Reference:

FSAR Section 9.4) at all points of tie-in to the PASS, except for the existing component cooling water system, existing sample coolers shell side, and liquid/gas sample lines up to the containment isolation valves. The tie-in to the V.C.T. for sample purge is also seismic.

Design Criteria Revision 0 Page 9 EWR 2606 Date 11/23/81

4.0 Qualit Grou I ll 4.1 Consistent with Regulatory Guide 1.26 the new PASS system components are assigned Quality Group D except for the component cooling water tie-in up to and including the tie-in automatic isolation valves which are Quality Group C, and the tie-in valve to the V.C.T.

for purging which is Quality Group B.

5.0 Code Class 5.1 The new PASS components are non-ASME IXX code except for the component cooling water tie-in up to and including the remote operated automatic isolation valves on the supply and return headers, and the tie-in to the V.C.T. for purging. The component cooling water isolation valves will be ASME III, Class 3. The V.C.T.

line tie-in valve will be Class 2.

5.2 The new PASS Waste Tank is designed in accordance with ASME VXXX, Division 1.

6.0 Codes, Standards, and Re ulator Re uirements The following requirements shall apply to the design

. and installation of the PASS.

The design, materials, fabrication, installation, examination and testing of the Quality Group B and C portion of the system shall be in accordance with the appropriate subsections of ASME Section XII. The first seismic support beyond the safety related systems interfaced shall be included under this criteria.

Field fabrication does not require stamping or third party inspectibn.

6.2 All seismic supports will be analyzed to Section NF of ASME III. Non seismic supports shall be designed in accordance with AISC. Field fabrication does not require stamping or third party inspection.

6.3 The materials, fabrication, installation, examination and 'testing of Quality Group D portions shall be in accordance with the appropriate sections of ANSX-B31.1, Power Piping Code, 1980.

6.4 Design activities of non-code items will be in accordance with ANSX-N45.2.11, 1974.

Base plate and expansion anchor bolt analysis will be performed using the criteria of NRC I.E. Bulletin 79-02, "Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts, dated March 8, 1979, in order to account for plate flexibility and bolt sizing loads.

Design Criteria Revision 1 Page 10 EWR 2606 Date 7/19/82

6.6 Modifications and additions to concrete structure shall be designed and installed in accordance with the requirements of ACI 318-77.

6.7 Cleanliness of the PASS shall meet. the requirements of ANSI N45.2.1 Class C to the extent practicable.

6.8 Housekeeping during construction shall be in accordance with the requirements of ANSI N45.2.3.

6.9 Installation of the PASS shall be in accoxdance with Sections 4 and 5 of ANSI N45.2.8.

6.10 Tubing within the LGSP is designed in accordance with ANSI B31.1.0.

I 7.0 Desi n Parameter 7.1 The PASS design parameters are given in Tables 1 and 2.'.2 The PASS components design parametexs are given in Table 3.

7.3 The PASS is shown in Figures 1 and 2.

Load'onditions The following requirements shall apply to the design of the PASS.

8.1 The new PASS supports shall be designed to sustain loads due to seismic,'ccelerations and displacements, weight, pressure,I and thermal expansion, as applicable.

8.2 Mechanical component. supports shall be designed to retain stxuctuxal integrity following the SSE.

8.3 All non-safety related piping/tubing will be designed to maintain pressure retaining integrity during a SSE.

Stress will be limited to the material yield strength.

Normal loading conditions will be limited to the allowable in ANSI B31.1.

8.4 Seismic analyses shall be based on the damping values required by USNRC Reg. Guide 1.61.

8.5 The seismic analysis critexia of NUREG 75/087 Standard Review Plan Section 3.7.2 "Seismic System Analysis" dated November 24, 1975 shall be followed; Both dynamic and equivalent static load methods will be used Criteria Revision 0 Design EWR 2606 Page ll Date ll/23/81

depending on the situation. When performing dynamic analysis the response spectxum method will be applied.

8.6 Fox piping systems equal to a greater than 2 inch diameter, support stiffnesses should be incorpoxated in

-the dynamic analysis modeling. When the equivalent static load method is used, supports shall be designed rigid to. prevent response amplification. A component, equipment or support is'considered to be rigid when the weight of the support and equipment can be accelerated in all three directions with an acceleration of 1 g.

and have a frequency equal to or greater than 33 hertz.

8.7 The LGSP will be analyzed to insure the panel stxucture does not fail during a safe shutdown earthquake (SSE).

If the fundamental vibration frequency is greater than 33 Hz., a static analysis will be performed using the maximum SSE accelerations of the floor at the attachment locations (zero period accelexations from, the response spectra). If the fundamental vibration frequency is less than 33 Hz., a dynamic analysis will be perfoxmed using a nodal xesponse spectra analysis. The instrument and control panels will not be analyzed since they will be located in a non-seismic area, the Hot Shop. Tubing within the LGSP is not seismically supported.

h 9.0 Envixonmental Conditions I

9.1 The design conditions inside of the containment axe as follows:

Pressure: Atm to 60 psig Temperatuxe: 286 Relative Hudmi ity: F'-1 00%

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.'adiation:

2 x 10 Rads, Integrated Dose These are maximum design conditions which occur at approximately 1 minute after a loss of coolant accident.

9.2 The design conditions in areas outside of containment are as follows:

Pressuxe: Atmospheric Temperature: 50-104 F Relative Humidity: 0-100%

9.3 Components outside containment handling radioactive fluids/gases shall be capable yf withstanding a two- .

yeax integrated 'dose of, 1' 10 Rads.'his value shall be used in design specifications as applicable.

Components not in contact with process fluids but located in a radiation environment shall .be"capable of Design Criteria Revision 0 Page 12

'EWR 2606 Da~e . .- .11/23/81

withstanding 1 x 10 6 rads integrated doge except Teflon which is capable of withstanding 1 x 10 rads. All components containing Teflon are to be immediately flushed after service, and to 'be designed for easy changeout. The immersion dose to LGSP components are verified by calculation not to exceed 1 x 10 Rads.

10.0 Interface Re uirements

10. 1 Process 10.1.1 The PASS will interface with the existing reactor coolant sampling system and containment air sampling system. The containment sump sample will be obtained from the Containment Sump 'A'.

10.2 Structural 10.2.1 The 253'-6" elevation of the Intermediate Building will be the location of the LGSP. The loads imposed on the existing Intermediate Building floor will be analyzed to determine is required.

if additional xeinforcement and/or bracing 10.3 Mechanical 10.3. 1 HVAC, component cooling water, demineralized water, plant air, for the PASS will interface with station facilities.

10.4 Electrical 10.4.1 Power for the PASS is to be drawn from nearby electrical supplies. It buses.

is not necessary to supply power from emergency 11.0 Material Re uirements.

11.1 Materials for the new PASS components are given in the attached Table 3.

11.2 ~ In general, material in contact with the process sample fluid will be 300 series stainless steel. Portions of the system in contact with support services (e.g.,

component cooling, instrument air, HVAC) will be of the same. material as the existing system.

11.3 Teflon or other elastomer valve packings are acceptable provided the potential for radiation damage and its consequen'ces are assessed as acceptable. Those components containing Teflon shall be immediately flushable after contact with radioactive fluids.

Design Criteria Revision 0 Page 13 EWR 2606 Date 11/23/81

12. 0 Mechanical Re uirements 12.1 The new PASS Waste Tank shall be provided with alternate means for fluid transfer such as a nitrogen displacement system.,

12.2 Motor driven components of the PASS need not be served by electxic power fxom an emergency bus. The pumps, evacuating compressoxs need not be redundant.

12.3 Piping, tubing and their supports shall be designed for normal process loads including thermal. Additional loading of seismic accelerations must be considered on pipe which, due to pipe rupture and pipe whip, may affect a nearby safety related system.

12.4 Isolation, throttling and waste valves for sample lines shall be selected to meet process requirements and to minimize crud traps.

12.5 Ventilation ductwork shall be galvanized sheetmetal constructed in accordance with the recommendations of SMACNA High Pressure Duct Construction.

Depending upon the process temperature, piping and ventilation ductwork shall be insulated for personnel protection, anti-sweat protection, or heat loss reduction.

12.7 Stainless steel, galvanized sheetmetal and non-ferrous alloy surfaces will not be painted. Other suxfaces will be painted with inorganic base paints not susceptible to scaling or peeling.

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12.8 Pressuxe relief protection shall be provided fox the LGSP. Relief discharge shall be routed to the PASS Waste Tank.

12. 9 Plenum exhaust is provided to collect leakage of radioactive gases from process- equipment unless leakproof /components axe selected or if equipment is located in properly ventilated areas not requixing access during sampling operation. 1 12.10 The Pass Waste Tank shall have level control to staxt and stop the PASS Transfer Pump and to provide high and low level alarms.

12. 11 The Pass Waste Tank shall have a rupture disc pressure relief which discharges to HVAC.

Design Criteria Revision 0 Page 14 EWR 2606 Date 11/23 81

12. 12 The Pass Trans fer Pump shall be capable of discharging to the containment sump "A" or to the plant radwaste system.

12. 13 The PASS Evacuating Compressor shall be capable of discharging to the containment. It will be controllable from the Waste Tank pressure transmitter.

13.0 Structural Re uirements 13.1 Location and sizes of structural members shall be determined to support design loads except where shielding requirements dictate greater thickness or different location without jeopardizing the structural integrity.

13.2 Loads imposed by permanent and/or portable shielding must be factored into the evaluation of structural integrity of existing structures.

13.3 Effects of seismic accelerations on those PASS components which could potentially damage adjacent safety related systems or components shall be evaluated to assure that gross failures do not occur.

14.0 H draulic Re uirement

14. 1 Existing sample lines shall be utilized to the greatest, extent practicable.

Pipe sizing shall be such as to assure sufficient velocity to minimize plateout in the lines and assure representative samples. The Reynolds number is to be in the turbulent zone throughout the system insofar as is practicable.

14. 3 Pipe routing shall avoid deadlegs, low points, and other similar crud trap orientations.

14. 4 Pipe sizing shall be such as to allow flushing of the line prior to drawing sample. Flushing flows shall be set at a rate so that representative samples will be available in about 10 minutes. Flushing flows will be about 1900 cc/min.

14. 5 Containment sump sample line design must consider possible elevated sump temperatures, debris in sump, chemical contaminants in sump, possible containment pressurization, as well as negative {subatmospheric) pressure in containment.

Design Criteria Revision 0 Page 15 EWR 2606 Date 11/23/Sl

14. 6 'The PASS Waste Tank shall be sized to hold waste from one sample acquisition which shall include at least three. line purges from the sample source.

15.0 Chemistr Re uirements 15.1 'The purpose of the PASS is to determine the chemistry of the process fluids.

15.2 The PASS Waste Tank will collect potentially low quality water from the Containment Sump sample, and chemicals from instrument calibration. Waste from these operations should not normally be returned to the volume 'contxol tank.

16.0 Electrical Re uirements

16. 1 Power supply for PASS shall be 120V, lp, 60Hz except.

for the evacuating compressor which shall be 480/3g/60Hz.

16. 2 Power (120 V) shall be obtained fxom power panel 1A circuit ll. 480 volt power will be supplied fxom (later).

16.3 Intraplant communications shall be supplied for the PASS.

s 16.4 Heat tracing with insulation will be pxovided on the containment air sample inlet line to prevent iodine plgteout up to the LGSP. Heat tracing shall be set at 10 F above maximum containment temperatuxe at t=l hours after DBA. The heat traging will be continuously adjustab3.e from 0 to 400 F, and will be set at 296 F fox post accident operation.

A I

16.5 .Electxical Power for the PASS need not be from an emexgency bus.

17.0 0 erational Re uirements 17.1 The PASS is to be designed so that it can be used for both noxmal and post-accident s'ampling without requiring any modification to change service.

17.2 For. the post-accident condition, in-line analyzers are to be provided for chemical analysis of the sample to minimize personnel exposure.

17. 3 Post accident shielding is designed using the source texm existing 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor. shutdown.

'0 >5 ~f rates to individuals from sample lines C

17. 4 Whole body dose assuming normal plant conditions (up to 0.25 percent

,Design Criteria Revision 0

.Page 16 EWR 2606 Date ll/23/81

fuel defects) will not exceed 100 mR/hr at 1 foot in normally accessable areas.

17. 5 To reduce general radiation levels, flushing and degassing means for the waste tank, piping and other potential sources shall be provided.

17.6 The LGSP is designed with integral lead shielding of sufficient thickness, to limit the direct radiation dose be'ess at one meter in fxont of the panel to than 100 mR/hr at t=l hour from souxces within panel, excluding backscatter and other background souxces.

18.0 Instrumentation and Contxol 18.1 An Electric Control Panel (ECP) shall be pxovided to indicate the status of pumps, compressors and other machinery as well as indicate valve positions.

18. 2 The PASS Waste Tank shall be provided with a means to monitor the accumulation of sample waste. High and low level alarms are to be provided as is pxessure indication with high alarm.

18.3 Valve position indication of existing reactor coolant liquid containment isolation valves shall be indicated on the new panel boaxd. Control switches for these valves shall remain in the control room and at a local station in the sample room.

18.4 Due to the highly radioactive natuxe of the process fluid, instruments shall be designed to minimize the amount of fluid necessary to perform a measurement.

I 18.5 Instruments shall be standard, commercially available devices modified as required for the service intended.

18. 6 Controls and indicators axe to be mounted on a remote panel located to minimize operator exposure. The controls shall be such that inline analysis of chemical parameters is completely remote.

18. 7 The PAbS Waste Tank will have level contxols such that.

when the Transfer Pump switch is in the automatic position the Pump will staxt and stop automatically.

18.8 The PASS Waste Tank Evacuating Compressor will be controlled by the Waste Tank pxessure when in the automatic mode.

18. 9 Interlocks will be provided throughout the system to preclude post accident fluid fxom enteringsystems not Design Criteria Revision Page 17 EWR 2606 Date ll/23 81

designed for post. accident radiation levels (e.g.

xadwaste).

19.0 Access and Administration Controls

19. 1 The PASS Electric Control Panel shall be accessible during the accident recovery phase.

19.2 The LGSP shall be accessible to the extent. necessary to obtain a post accident diluted grab sample. Flushing provisions shall be incorpoxated to reduce radiation

,levels prior to approaching the LGSP. Crud traps axe to be particularly avoided.

19.3 The sample piping is to be routed suitably to minimize personnel exposure. Nhexe such routing is not practical, local shielding is to be provided.

20. 0 Redundanc , Diversit , and Se aration Re uirements

20. 1 Diversity in returning the sample waste to containment is pxovided by means of a transfer pump and alternately by nitxogen displacement.

21.0 Failure Effects Re uirements 21.1 Although the PASS components are designated nonseismic (except for cooling water interfaces), equipment supports shall be analyzed and designed considering seismic loads to pxeclude gross failure of the fluid boundary or deleterious effects on nearby safety related sys-t,ems.

21.2 System shall be designed such that operational failure of any component will not prejudice the shutdown of the sampling system and containment of the process fluids (liquid and gas).

21.3 Failure of the PASS will not, effect. any safety related system including containment isolation.

22.0 Test Re uirements 22.1 Xmmediately prior to use of the system for post-accident.

sampling, the system shall be capable of being leak checked using air ox nitrogen.

22.2 Built in calibration methods shall be provided for online chemical analysis equipment and the containment air gas chromatogxaph.

P h Design Criteria Revision 0 Page 18 EWR 2606 Date ll/23/81

0

22. 3 The PASS shall be hydrostatically tested in accordance with ANSI B 31.1, except for the portion of the system that is ASME III. Where hydrostatic testing is not practical, leak testing will be performed in accordance with ANSI B31.1. Testing of the code poxtion of the system will be in accordance with ASME Section III, Sub-Section "ND" Class 3 components.

22.4 The new PASS shall be functionally tested to verify pxoper operation of system cooler, waste tank and pump, evacuating compressox, and LGSP components. The PASS shall be tested to verify the analytical parametexs of Table 3 are met.

23.0 Accessibilit , Maintenance, Re aix and Insexvice Ins ection Pxo ram

23. 1 Fluid containing components of the PASS shall be flushed prior to maintenance. Flushing shall be accomplished from the remote Electric Control Panel.

23.2 Adequate space shall be provided around components for maintenance personnel to facilitate maintenance functions.

23.3 Access to existing plant equipment for routine maintenance shall not be adversely affected by the PASS installation.

24.0 Personnel Re uirement

24. 1 The design of the system requixes only one operator to obtain and analyze samples with communication to the main control room.

25.0 Trans rtabilit Re uirement None 26.0 Fire Protection Re uirements 26.1 Due to lack of combustible material in the PASS axea, no automatic fire detection or suppression will be provided. Hand held portable fire extinguishexs will be relied upon to handle any outbreak of small fires.

26. 2 Pipe insulation will be fixe resistant with a flame spread of 25 or less and a smoke developed rating of 25 or less.

26.3 The design of the new PASS shall, as necessary," be compatible with the present fire protection as outlined in GAI Repoxt 1936, and xeference require-'ents 2.13; Design Criteria Revision 0 Page 19 EWR 2606 Date 11/23/81

26.4 Cable shall meet fire retardent criteria of IEEE 383.

26.5 The electrical wiring of the LGSP, ECP, and IP will me'et National Electric Code Standards.

27.0 Handlin Re uirements 27.1 The new PASS components and material to be used shall be shipped, handled, and stored in accordance with the appropriate requirements of ANSI N 45.2.2.

27.2 Level B requirements of ANSI N45.2.2 shall apply for R

all new electrical components with the exception of cable which shall meet Level C requirements.

~ s 0" p

) I P>>

27. 3 Level B, C, and D requirements shall apply for other material and equipment and shall be indicated in the appropriate procurement documents.

28.0 Public Safet Re uirements 28.1 Failure of any PASS components after an accident shall not result in Part 100 doses to be exceeded. On this basis the system is classified non-safety related.

29.0 A licabilit None

30. 0 Personnel Safet Re uirement 30.1 Shielding shall be provided for all equipment handling radioactive fluids under normal conditions to meet ALARA considerations. The design objective is to limit personnel exposure to 5 Rem per sample whole body and 75 Rem per sample additional to extremities to any individual operator during accident conditions.

30.2 Ventilation systems shall be provided to control and contain airborne radioactive releases. Hooded enclosures shall be provided as required.

30. 3 Spills of fluids are to be controlled by use of curbs, drip pans or drains.

30. 4 Grounding of electrical systems shall be provided.

30.5 Hot piping external to the LGSP, i.e., over 140 o F, shall be insulated.

31.0'Uni'e Re uirements None Design Criteria Revision 0 Page 20 ENR 2606 Date 11/23/81

TABLE 1 PASS Functional Requirements Xn-Line Anal sis for:

Reactor Coolant A) Pressurizer Vapor Space Boron, pH, dissolved oxygen, Diluted (1000:1) grab samples (post accident B) Pressurizer Liquid Space diss')yed hydrogen, conductivity, Undiluted dissolved gas C) Hot Leg note sample (normal operation)

Undiluted reactor liquid sample (normal operation)

Containment A) Sump Same as reactor coolant Diluted (1000:1)

'A')

except dissolved 02(pe sample dissolved H2, note undiluted (normal operation)

Ataasphere Hydrogen, Oxygen Diluted (1000:1) sample Sample must be obtained and analyzed within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of the decision to sample.

Grab samples to be used for isotcpic analysis in the stations counting roan or for off-site analysis.

Connections are provided for chloride analysis by a portable instrument. These connections also used for obtaining undiluted samples during routine operation.

Table 2 PASS Sample Source Design Parameters Pressure, psig Temperature, 'F Min. Max. Min./Max Reactor 200 /2485 140/680 Containment Sump 'A'liquid) Atm/60** 50/250 Containment Atmosphere Atm/60** 50/286 Detailed design will ascertain the lowest limit of pressure at which a sample can be obtained within the three hour time limit.

• • Plus head of liquid

P Table 3 PASS Ccmponent Design Parametexs

1. Li id and Gas S le Panel (LGSP), new Analytical Paxametexs Measurement Param ter ~Accura LIQUID SAMPLES:

pH 1-13 + O.l pH Unit Conductivity .0.1-500 +35 umho/cm Dissolved Oxygen (1) Probe 0.01-20 p~ +10%

Dissolved Hydrogen (1) l Gas Chrcnatogxaph 10-2000 +155 cc/kg Boron Auto-titrator 50-6,000 GAS SAMPLES:

Hydrogen Gas Chrcnntogxaph 0-10% +5%

Oxygen Gas Chrcmatogxaph 0-30%

(1) Not requixed fox sump samples.

Table 3 (Cont'd)

2. Sample Coolers, PAS-E-201 A, B, C, D; new'uantity 4

Tjgpe coil-in-shell Design heat transfer, BTU/hr 51,395 Shell Design pressure, psig 150 2485 0F 350 700 Design temperature, Design flew, ggn (Approx.) 10 0.1 Inlet temperature, 0F 105 680 0F 152 120 Oulet temperature, Fluid circulated C.C. Water Sample Material A106GRB Tp316SS Design Codes AWK VIII ANSI B.31.1.0 Seismic Catecpxy non-seismic non-seismic

Table 3 (Cont'd)

'3. Waste Tank, PAS-T-202; new Quantity Capacity, gal 18 Design pressure, psig full vacuum to 150 0F 150 Design temperature, Operating pressure, psia 14.0 to 14.7 0F 120 Operating temperature, Material MIM A312Tp 316SS Design Codes ASME VEII Seismic Category non-seismic

4. Waste Transfer Pump, PAS-P-203; new Quantity Design Pressure, psig 150 Design temperature, F 150 Design flow, gpm (Approx.)

NPSH available, Ft 24 Discharge pressure, psig 85 Material ASm ZB12 vp 316 SS Design Code mfr.stnd.

Seismic Catecpry non-seismic

Table 3 (Cont'd)

5. Waste Tank Evacuating Canpressor, PAS-C-200; new Quantity Design pressure, psig 150 0F 120 Design temperature, Design f1~, scfm 0.5 (min)

Suction Pressure, psia 14.0 to 14.7 Discharge pressure, psia 75 Material Design Code mnfr. stnd.

Seismic Category non-seismic

6. Containm nt Sutp 'A'ample Pump, PAS-P-204; new Quantity Design pressure, psig 150 o

Design temperature, F (liquid) 250 Design f3', gpn (Approx.)

I Dischaxge pressure, psig 50 Material SS Tp 316

'Design Cede rrnfr. stnd.

Seismic Cattery non-seismic Radiation Qualification N/A (air nntor)